Index to Nuclear Safety: a technical progress review by chrology, permuted title, and author, Volume 11(1) through Volume 20(6)

Energy Technology Data Exchange (ETDEWEB)

Cottrell, W B; Passiakos, M

1980-06-01

This index to Nuclear Safety, a bimonthly technical progress review, covers articles published in Nuclear Safety, Volume II, No. 1 (January-February 1970), through Volume 20, No. 6 (November-December 1979). It is divided into three sections: a chronological list of articles (including abstracts) followed by a permuted-title (KWIC) index and an author index. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center (NSIC), covers all safety aspects of nuclear power reactors and associated facilities. Over 600 technical articles published in Nuclear Safety in the last ten years are listed in this index.

Reliability Analysis of Public Survey in Satisfaction with Nuclear Safety

Energy Technology Data Exchange (ETDEWEB)

Park, Moon Soo; Moon, Joo Hyun; Kang, Chang Sun [Seoul National Univ., Seoul (Korea, Republic of)

2005-07-01

Korea Institute of Nuclear Safety (KINS) carried out a questionnaire survey on public's understanding nuclear safety and regulation in order to grasp public acceptance for nuclear energy. The survey was planned to help to analyze public opinion on nuclear energy and provide basic data for advertising strategy and policy development. In this study, based on results of the survey, the reliability of the survey was evaluated according to each nuclear site.

19th JANNAF Safety and Environmental Protection Subcommittee Meeting. Volume 1

Science.gov (United States)

Cocchiaro, J. E. (Editor); Becker, D. L. (Editor)

2002-01-01

This volume, the first of two volumes, is a compilation of 22 unclassified/unlimited technical papers presented at the 19th Joint Army-Navy-NASA-Air Force (JANNAF) Safety & Environmental Protection Subcommittee Meeting. The meeting was held 18-21 March 2002 at the Sheraton Colorado Springs Hotel, Colorado Springs, Colorado. Topics covered include green energetic materials and life cycle pollution prevention; space launch range safety; propellant/munitions demilitarization, recycling, and reuse: and environmental and occupational health aspects of propellants and energetic materials.

Measuring patient safety culture in Taiwan using the Hospital Survey on Patient Safety Culture (HSOPSC).

Science.gov (United States)

Chen, I-Chi; Li, Hung-Hui

2010-06-07

Patient safety is a critical component to the quality of health care. As health care organizations endeavour to improve their quality of care, there is a growing recognition of the importance of establishing a culture of patient safety. In this research, the authors use the Hospital Survey on Patient Safety Culture (HSOPSC) questionnaire to assess the culture of patient safety in Taiwan and attempt to provide an explanation for some of the phenomena that are unique in Taiwan. The authors used HSOPSC to measure the 12 dimensions of the patient safety culture from 42 hospitals in Taiwan. The survey received 788 respondents including physicians, nurses, and non-clinical staff. This study used SPSS 15.0 for Windows and Amos 7 software tools to perform the statistical analysis on the survey data, including descriptive statistics and confirmatory factor analysis of the structural equation model. The overall average positive response rate for the 12 patient safety culture dimensions of the HSOPSC survey was 64%, slightly higher than the average positive response rate for the AHRQ data (61%). The results showed that hospital staff in Taiwan feel positively toward patient safety culture in their organization. The dimension that received the highest positive response rate was "Teamwork within units", similar to the results reported in the US. The dimension with the lowest percentage of positive responses was "Staffing". Statistical analysis showed discrepancies between Taiwan and the US in three dimensions, including "Feedback and communication about error", "Communication openness", and "Frequency of event reporting". The HSOPSC measurement provides evidence for assessing patient safety culture in Taiwan. The results show that in general, hospital staffs in Taiwan feel positively toward patient safety culture within their organization. The existence of discrepancies between the US data and the Taiwanese data suggest that cultural uniqueness should be taken into

Hospital safety culture in Taiwan: a nationwide survey using Chinese version Safety Attitude Questionnaire.

Science.gov (United States)

Lee, Wui-Chiang; Wung, Hwei-Ying; Liao, Hsun-Hsiang; Lo, Chien-Ming; Chang, Fei-Ling; Wang, Pa-Chun; Fan, Angela; Chen, Hsin-Hsin; Yang, Han-Chuan; Hou, Sheng-Mou

2010-08-10

Safety activities have been initiated at many hospitals in Taiwan, but little is known about the safety culture at these hospitals. The aims of this study were to verify a safety culture survey instrument in Chinese and to assess hospital safety culture in Taiwan. The Taiwan Patient Safety Culture Survey was conducted in 2008, using the adapted Safety Attitude Questionnaire in Chinese (SAQ-C). Hospitals and their healthcare workers participated in the survey on a voluntary basis. The psychometric properties of the five SAQ-C dimensions were examined, including teamwork climate, safety climate, job satisfaction, perception of management, and working conditions. Additional safety measures were asked to assess healthcare workers' attitudes toward their collaboration with nurses, physicians, and pharmacists, respectively, and perceptions of hospitals' encouragement of safety reporting, safety training, and delivery delays due to communication breakdowns in clinical areas. The associations between the respondents' attitudes to each SAQ-C dimension and safety measures were analyzed by generalized estimating equations, adjusting for the clustering effects at hospital levels. A total of 45,242 valid questionnaires were returned from 200 hospitals with a mean response rate of 69.4%. The Cronbach's alpha was 0.792 for teamwork climate, 0.816 for safety climate, 0.912 for job satisfaction, 0.874 for perception of management, and 0.785 for working conditions. Confirmatory factor analyses demonstrated a good model fit for each dimension and the entire construct. The percentage of hospital healthcare workers holding positive attitude was 48.9% for teamwork climate, 45.2% for perception of management, 42.1% for job satisfaction, 37.2% for safety climate, and 31.8% for working conditions. There were wide variations in the range of SAQ-C scores in each dimension among hospitals. Compared to those without positive attitudes, healthcare workers with positive attitudes to each SAQ

Safety report concerning the reactor Pegase - volume 1 - Description of the installation - volume 2 - Safety of the installations

International Nuclear Information System (INIS)

Lacour, J.

1964-01-01

In the first volume: This report is a description of the reactor Pegase, given with a view to examine the safety of the installations. The Cadarache site at which they are situated is briefly described, in particular because of the consequences on the techniques employed for building Pegase. A description is also given of the original aspects of the reactor. The independent loops which are designed for full-scale testing of fuel elements used in natural uranium-gas-graphite reactor systems are described in this report, together with their operational and control equipment. In the second volume: In the present report are examined the accidents which could cause damage to the Pegase reactor installation. Among possible causes of accidents considered are the seismicity of the region, an excessive power excursion of the reactor and a fracture in the sealing of an independent loop. Although all possible precautions have been taken to offset the effects of such accidents, their ultimate consequences are considered here. The importance is stressed of the security action and regulations which, added to the precautions taken for the construction, ensure the safety of the installations. (authors) [fr

Thirteenth water reactor safety research information meeting: proceedings Volume 1

International Nuclear Information System (INIS)

Weiss, A.J.

1986-02-01

This six-volume report contains 151 papers out of the 178 that were presented at the Thirteenth Water Reactor Safety Research Information Meeting held at the National Bureau of Standards, Gaithersburg, Maryland, during the week of October 22-25, 1985. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included thirty-one different papers presented by researchers from Japan, Canada and eight European countries. The title of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. This volume presents information on: risk analysis PRA application; severe accident sequence analysis; risk analysis/dependent failure analysis; and industry safety research

Organizational analysis and safety for utilities with nuclear power plants: perspectives for organizational assessment. Volume 2

International Nuclear Information System (INIS)

Osborn, R.N.; Olson, J.; Sommers, P.E.

1983-08-01

This two-volume report presents the results of initial research on the feasibility of applying organizational factors in nuclear power plant (NPP) safety assessment. Volume 1 of this report contains an overview of the literature, a discussion of available safety indicators, and a series of recommendations for more systematically incorporating organizational analysis into investigations of nuclear power plant safety. The six chapters of this volume discuss the major elements in our general approach to safety in the nuclear industry. The chapters include information on organizational design and safety; organizational governance; utility environment and safety related outcomes; assessments by selected federal agencies; review of data sources in the nuclear power industry; and existing safety indicators

78 FR 65661 - Agency Information Collection Activities; Proposed Collection; Comment Request; Food Safety Survey

Science.gov (United States)

2013-11-01

... are used to measure trends in consumer food safety habits including hand and cutting board washing... notice invites comments on a voluntary consumer survey entitled, ``Food Safety Survey.'' DATES: Submit... the safety of the nation's food supply. The Food Safety Survey measures consumers' knowledge...

Sensitivity and uncertainty analyses applied to criticality safety validation. Volume 2

International Nuclear Information System (INIS)

Broadhead, B.L.; Hopper, C.M.; Parks, C.V.

1999-01-01

This report presents the application of sensitivity and uncertainty (S/U) analysis methodologies developed in Volume 1 to the code/data validation tasks of a criticality safety computational study. Sensitivity and uncertainty analysis methods were first developed for application to fast reactor studies in the 1970s. This work has revitalized and updated the existing S/U computational capabilities such that they can be used as prototypic modules of the SCALE code system, which contains criticality analysis tools currently in use by criticality safety practitioners. After complete development, simplified tools are expected to be released for general use. The methods for application of S/U and generalized linear-least-square methodology (GLLSM) tools to the criticality safety validation procedures were described in Volume 1 of this report. Volume 2 of this report presents the application of these procedures to the validation of criticality safety analyses supporting uranium operations where enrichments are greater than 5 wt %. Specifically, the traditional k eff trending analyses are compared with newly developed k eff trending procedures, utilizing the D and c k coefficients described in Volume 1. These newly developed procedures are applied to a family of postulated systems involving U(11)O 2 fuel, with H/X values ranging from 0--1,000. These analyses produced a series of guidance and recommendations for the general usage of these various techniques. Recommendations for future work are also detailed

Report of the Survey on the Design Review of New Reactor Applications. Volume 1 - Instrumentation and Control

International Nuclear Information System (INIS)

Downey, Steven

2014-06-01

At the tenth meeting of the CNRA Working Group on the Regulation of New Reactors (WGRNR) in March 2013, the members agreed to present the responses to the Second Phase, or Design Phase, of the Licensing Process Survey as a multi-volume text. As such, each report will focus on one of the eleven general technical categories covered in the survey. The general technical categories were selected to conform to the topics covered in the International Atomic Energy Agency (IAEA) Safety Guide GS-G-4.1. This report, which is the first volume, provides a discussion of the survey responses related to Instrumentation and Control (I and C). The Instrumentation and Control category includes the twelve following technical topics: Reactor trip system, actuation systems for Engineered Safety Features (ESF), safe shutdown system, safety-related display instrumentation, information and interlock systems important to safety, controls systems, main control room, supplementary control room, diverse I and C systems, data communication systems, software reliability and cyber-security. For each technical topic, the member countries described the information provided by the applicant, the scope and level of detail of the technical review, the technical basis for granting regulatory authorisation, the skill sets required and the Level of effort needed to perform the review. Based on a comparison of the information provided in response to the survey, the following observations were made: - Among the regulatory organisations that responded to the survey, there are similarities in the design information provided by an applicant. In most countries, the design information provided by an applicant includes, but is not limited to, a description of the I and C system design and functions, a description of the verification and validation programmes, and provisions for analysis, testing, and inspection of various I and C systems. - In addition to the regulations, it is a common practice for countries

A hierarchical factor analysis of a safety culture survey.

Science.gov (United States)

Frazier, Christopher B; Ludwig, Timothy D; Whitaker, Brian; Roberts, D Steve

2013-06-01

Recent reviews of safety culture measures have revealed a host of potential factors that could make up a safety culture (Flin, Mearns, O'Connor, & Bryden, 2000; Guldenmund, 2000). However, there is still little consensus regarding what the core factors of safety culture are. The purpose of the current research was to determine the core factors, as well as the structure of those factors that make up a safety culture, and establish which factors add meaningful value by factor analyzing a widely used safety culture survey. A 92-item survey was constructed by subject matter experts and was administered to 25,574 workers across five multi-national organizations in five different industries. Exploratory and hierarchical confirmatory factor analyses were conducted revealing four second-order factors of a Safety Culture consisting of Management Concern, Personal Responsibility for Safety, Peer Support for Safety, and Safety Management Systems. Additionally, a total of 12 first-order factors were found: three on Management Concern, three on Personal Responsibility, two on Peer Support, and four on Safety Management Systems. The resulting safety culture model addresses gaps in the literature by indentifying the core constructs which make up a safety culture. This clarification of the major factors emerging in the measurement of safety cultures should impact the industry through a more accurate description, measurement, and tracking of safety cultures to reduce loss due to injury. Copyright © 2013 National Safety Council and Elsevier Ltd. All rights reserved.

2009 transparency and nuclear safety report. CEA Cadarache. Volumes 1 + 2

International Nuclear Information System (INIS)

2009-01-01

After a general presentation of the Cadarache site and of its nuclear installations, the first volume of this report describes the various measures concerning the site safety (safety organisation, general measures, measures related to various risks, inspections, control of emergency situations, audits and second level control, measures in basic nuclear installations) and radioprotection (organisation, significant facts, dosimeter results). It describes significant events which occurred in relationship with nuclear safety and radioprotection, presents results of measurements of releases and of their impact on the environment (chemical and radiological assessment). Then after a description of measures to limit the volume of stored radioactive wastes and their impact on health and on the environment, tables indicate the nature and quantities of wastes which are stored in the different basic nuclear installations of Cadarache. The second volume proposes the same information for two specific nuclear installations belonging to Areva and located in Cadarache, the INB 32 and 54 (INB stands for basic nuclear installation) for which a significant event occurred on the 6 October 2009. For these installations, release measurements concern gaseous and liquid releases

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

Science.gov (United States)

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

2013-01-01

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

Proceedings of the 1984 DOE nuclear reactor and facility safety conference. Volume II

Energy Technology Data Exchange (ETDEWEB)

1984-01-01

This report is a collection of papers on reactor safety. The report takes the form of proceedings from the 1984 DOE Nuclear Reactor and Facility Safety Conference, Volume II of two. These proceedings cover Safety, Accidents, Training, Task/Job Analysis, Robotics and the Engineering Aspects of Man/Safety interfaces.

Proceedings of the 1984 DOE nuclear reactor and facility safety conference. Volume II

International Nuclear Information System (INIS)

1984-01-01

This report is a collection of papers on reactor safety. The report takes the form of proceedings from the 1984 DOE Nuclear Reactor and Facility Safety Conference, Volume II of two. These proceedings cover Safety, Accidents, Training, Task/Job Analysis, Robotics and the Engineering Aspects of Man/Safety interfaces

The patient safety climate in healthcare organizations (PSCHO) survey: Short-form development.

Science.gov (United States)

Benzer, Justin K; Meterko, Mark; Singer, Sara J

2017-08-01

Measures of safety climate are increasingly used to guide safety improvement initiatives. However, cost and respondent burden may limit the use of safety climate surveys. The purpose of this study was to develop a 15- to 20-item safety climate survey based on the Patient Safety Climate in Healthcare Organizations survey, a well-validated 38-item measure of safety climate. The Patient Safety Climate in Healthcare Organizations was administered to all senior managers, all physicians, and a 10% random sample of all other hospital personnel in 69 private sector hospitals and 30 Veterans Health Administration hospitals. Both samples were randomly divided into a derivation sample to identify a short-form subset and a confirmation sample to assess the psychometric properties of the proposed short form. The short form consists of 15 items represented 3 overarching domains in the long-form scale-organization, work unit, and interpersonal. The proposed short form efficiently captures 3 important sources of variance in safety climate: organizational, work-unit, and interpersonal. The short-form development process was a practical method that can be applied to other safety climate surveys. This safety climate short form may increase response rates in studies that involve busy clinicians or repeated measures. Published 2017. This article is a U.S. Government work and is in the public domain in the USA.

Survey of radiological safety in dental practice

Energy Technology Data Exchange (ETDEWEB)

Gill, J R [UKAEA Health and Safety Branch, London; Hudson, A P

1977-01-01

A pilot survey of radiological protection in dental practice in Great Britain has been requested by the Health and Safety Executive and is now in progress. The survey should provide more precise data on the use of X-ray equipment. There are approximately 13,000 dentists in Great Britain using X-ray apparatus, and some 600 of these have been selected, on a statistical basis, to be invited to make use of a postal survey over a six month period. The postal survey technique to be used has already been developed as a service following requests from individual dentists. The dentist receives a questionnaire and three initial films to test the timer, then two special cassettes incorporating film and filters. Film badges are worn over a 12 week period by the dentist and by any staff who assist in radiography. Follow-up visits to discuss the survey will be made to one in ten of the selected dentists. The results will give the individual dentists, without cost, assurance of the efficient functioning of their equipment, and advice, should any remedial measures be necessary. Concurrently, the resulting statistics will give an indication of how many, if any, practices fall short of the recommendations of the Code of Practice for the Protection of Persons against Ionizing Radiations arising from Medical and Dental Use. Further action in respect of the Health and Safety at Work Act will be determined in the light of the survey.

Safety culture in regulatory expert organization : analysis result of survey for KINS employees

International Nuclear Information System (INIS)

Choi, G. S.; Choi, Y. S.

2003-01-01

Much has been discussed on safety culture of operating organizations, however, little has been done on that of regulatory organization. Current issues and activities related to nuclear safety culture at IAEA, OECD/NEA, etc. were investigated and relevant literatures were reviewed. Elements essential for safety culture of regulatory organization were proposed and survey questionnaire for employees of regulatory expert organization, KINS, was developed based on the elements proposed. The survey result was presented and its implications were discussed. Based on the result, elements of safety culture in regulatory organization were proposed. The result of this survey can be used in developing safety culture model of regulatory organization, measurement method and also promotion of safety culture in regulatory organization

Proceedings of the international topical meeting on advanced reactors safety: Volume 2

International Nuclear Information System (INIS)

1997-01-01

In this volume, 89 papers are grouped under the following headings: advances in research/test reactor safety; advanced reactor accident management and emergency actions; advanced reactors instrumentation/controls/human factors; probabilistic risk/safety and reliability assessments; steam explosion research and issues; advanced reactor severe accident issues and research (analysis and assessments); advanced reactor thermal hydraulics; accelerator-driven source safety; liquid-metal reactor safety; structural assessments and issues; late papers

Environmental, health, and safety issues of sodium-sulfur batteries for electric and hybrid vehicles. Volume 1, Cell and battery safety

Energy Technology Data Exchange (ETDEWEB)

Ohi, J M

1992-09-01

This report is the first of four volumes that identify and assess the environmental, health, and safety issues involved in using sodium-sulfur (Na/S) battery technology as the energy source in electric and hybrid vehicles that may affect the commercialization of Na/S batteries. This and the other reports on recycling, shipping, and vehicle safety are intended to help the Electric and Hybrid Propulsion Division of the Office of Transportation Technologies in the US Department of Energy (DOE/EHP) determine the direction of its research, development, and demonstration (RD&D) program for Na/S battery technology. The reports review the status of Na/S battery RD&D and identify potential hazards and risks that may require additional research or that may affect the design and use of Na/S batteries. This volume covers cell design and engineering as the basis of safety for Na/S batteries and describes and assesses the potential chemical, electrical, and thermal hazards and risks of Na/S cells and batteries as well as the RD&D performed, under way, or to address these hazards and risks. The report is based on a review of the literature and on discussions with experts at DOE, national laboratories and agencies, universities, and private industry. Subsequent volumes will address environmental, health, and safety issues involved in shipping cells and batteries, using batteries to propel electric vehicles, and recycling and disposing of spent batteries. The remainder of this volume is divided into two major sections on safety at the cell and battery levels. The section on Na/S cells describes major component and potential failure modes, design, life testing and failure testing, thermal cycling, and the safety status of Na/S cells. The section on batteries describes battery design, testing, and safety status. Additional EH&S information on Na/S batteries is provided in the appendices.

International survey of living PSA and safety indicators

International Nuclear Information System (INIS)

Holmberg, J.; Laakso, K.; Lehtinen, E.; Bjoere, S.

1992-01-01

The report contains an international overview of applications of living probabilistic assessment and development of operational safety indicators. Features of an ideal living PSA tool are summarized as well as a limited survey of code systems for managing a living probabilistic safety assessment (living PSA) is included. The international survey is used as an input for planning and performance of related tasks within the nordic NKS/SIK-1 project conducted in 1990-93. The research notes are distributed to the Nordic organizations involved or interested in the subject. The report includes an overview and conclusions from technical reports and articles available and presentations and discussions related to development and use of above methods for the evaluation and management of the operational safety of nuclear power plants. A large part of this material is based on material collected and discussed in connection to international specialist meetings relating to the subject

Organizational analysis and safety for utilities with nuclear power plants: an organizational overview. Volume 1

International Nuclear Information System (INIS)

Osborn, R.N.; Olson, J.; Sommers, P.E.; McLaughlin, S.D.; Jackson, M.S.; Scott, W.G.; Connor, P.E.

1983-08-01

This two-volume report presents the results of initial research on the feasibility of applying organizational factors in nuclear power plant (NPP) safety assessment. A model is introduced for the purposes of organizing the literature review and showing key relationships among identified organizational factors and nuclear power plant safety. Volume I of this report contains an overview of the literature, a discussion of available safety indicators, and a series of recommendations for more systematically incorporating organizational analysis into investigations of nuclear power plant safety

Geothermal energy, an environmental and safety mini-overview survey

Energy Technology Data Exchange (ETDEWEB)

1976-07-01

A survey is presented in order to determine the technology status, gaps, and needs for research and development programs in the environment and safety areas of this resource. The information gathered from a survey of geothermal energy development undertaken to provide background for an environment and safety overview program is summarized. A technology assessment for resource development is presented. The three specific environmental problems identified as most potentially limiting to geothermal development; hydrogen sulfide control, brine disposal, and subsidence, are discussed. Current laws, regulations, and standards applying to geothermal systems are summarized. The elements of the environment, health, and safety program considered to be intrinsically related to the development of geothermal energy systems are discussed. Interagency interfaces are touched on briefly. (MHR)

The Fukushima Daiichi Accident. Technical Volume 2/5. Safety Assessment

International Nuclear Information System (INIS)

2015-08-01

Technical Volume 1 of this report has described what happened during the accident at the Fukushima Daiichi nuclear power plant (NPP). This volume begins (Section 2.1) with a review of how the design basis of the site for external events was assessed initially and then reassessed over the life of the NPP. The section also describes the physical changes that were made to the units as a result. The remainder of the volume describes the treatment of beyond design basis events in the safety assessment of the site, the accident management provisions, the effectiveness of regulatory programmes, human and organizational factors and the safety culture, and the role of operating experience. Further background information is contained in three annexes included on the CD-ROM of this Technical Volume which describe analytical investigations of the accident along with information on topics such as system performance, defence in depth and severe accident phenomena. Section 2.2 provides an assessment of the systems that failed, resulting in a failure to maintain the fundamental safety functions in Units 1–3, which were in operation at the time of the tsunami and in which the reactor pressure vessels (RPV) and containment vessels failed. The section also describes Units 4-6, which were shut down at the time of the tsunami, and the site’s central spent fuel storage facility. Section 2.3 discusses the probabilistic and deterministic safety assessments of beyond design basis accidents (BDBAs) that had been performed for the plant and the insights from these assessments that had led to changes in the plant’s design. The section pays particular attention to the assessment of extreme natural hazards, such as the one which led to the total loss of AC power supply on the site. The additional loss of DC power supply in Units 1 and 2 played a key role in the progression of the accident because it impeded the diagnosis of plant conditions and made the operators unaware of the status of

A survey of approaches combining safety and security for industrial control systems

International Nuclear Information System (INIS)

Kriaa, Siwar; Pietre-Cambacedes, Ludovic; Bouissou, Marc; Halgand, Yoran

2015-01-01

The migration towards digital control systems creates new security threats that can endanger the safety of industrial infrastructures. Addressing the convergence of safety and security concerns in this context, we provide a comprehensive survey of existing approaches to industrial facility design and risk assessment that consider both safety and security. We also provide a comparative analysis of the different approaches identified in the literature. - Highlights: • We raise awareness of safety and security convergence in numerical control systems. • We highlight safety and security interdependencies for modern industrial systems. • We give a survey of approaches combining safety and security engineering. • We discuss the potential of the approaches to model safety and security interactions

Report by USSR survey mission of Nuclear Safety Commission

International Nuclear Information System (INIS)

1990-01-01

The USSR survey mission of Nuclear Safety Commission drew up and presents the report as follows. In relation to the accident in Chernobyl Nuclear Power Station in USSR, in order to investigate into the present status of the countermeasures for nuclear power safety in USSR and to exchange opinion, the USSR survey mission inspected nuclear power station facilities and visited the government organs, research institutes and others in USSR. The survey mission comprised 13 members, and went to Moscow, Kiev and two nuclear power station sites, from October 22 to November 1, 1989, for 11 days. At present in USSR, 49 nuclear power plants of about 35 GWe are in operation, and by 2000, the operation of more nuclear power plants of about 30 GWe is needed, but due to the change of social situation in USSR, its attainment seems to be difficult. The plan of nuclear power generation in USSR, the ensuring of safety in general, the recent countermeasures for improving safety, the effect of the accident in Chenobyl Nuclear Power Station on health and so on are reported. The detailed record of the visit to Zaporozhe and Chernobyl Nuclear Power Stations and 7 other research institutes and government organs is given. (K.I.)

Safety of magnetic fusion facilities: Volume 2, Guidance

International Nuclear Information System (INIS)

1995-01-01

This document provides guidance for the implementation of the requirements identified in Vol. 1 of this Standard. This guidance is intended for the managers, designers, operators, and other personnel with safety responsibilities for facilities designated as magnetic fusion facilities. While Vol. 1 is generally applicable in that requirements there apply to a wide range of fusion facilities, this volume is concerned mainly with large facilities such as the International Thermonuclear Experimental Reactor (ITER). Using a risk-based prioritization, the concepts presented here may also be applied to other magnetic fusion facilities. This volume is oriented toward regulation in the Department of Energy (DOE) environment

Anesthesia Quality and Patient Safety in China: A Survey.

Science.gov (United States)

Zhu, Bin; Gao, Huan; Zhou, Xiangyong; Huang, Jeffrey

There has been no nationwide investigation into anesthesia quality and patient safety in China. The authors surveyed Chinese anesthesiologists about anesthesia quality by sending a survey to all anesthesiologist members of the New Youth Anesthesia Forum via WeChat. The respondents could choose to use a mobile device or desktop to complete the survey. The overall response rate was 43%. Intraoperative monitoring: 77.9% of respondents reported that electrocardiogram monitoring was routinely applied for all patients; only 55% of the respondents reported that they routinely used end-tidal carbon dioxide monitoring for their patients under general anesthesia. 10.3% of respondents admitted that they had at least one wrong medicine administration in the past 3 months; 12.4% reported that they had at least one case of cardiac arrest in the past year. This is the first anesthesia quality survey in China. The findings revealed potential anesthesia safety issues in China.

PETRO-SAFE '94 conference papers: Book 2. Volume 5: Emergency response ampersand spill control; Volume 6: Remediation; Volume 7: Health ampersand safety issues

International Nuclear Information System (INIS)

Anon.

1994-01-01

The Fifth Annual Environmental, Safety and Health Conference and Exhibition for the oil, gas and petrochemical industries was held January 25--27, 1994 in Houston, Texas. The objective of this conference was to provide a multidisciplinary forum dealing with state-of-the-art environmental and safety issues. This volume focuses on the following: emergency response and spill control; remediation; and health and safety issues. Individual papers have been processed separately for inclusion in the appropriate data bases

Organizational analysis and safety for utilities with nuclear power plants: perspectives for organizational assessment. Volume 2. [PWR; BWR

Energy Technology Data Exchange (ETDEWEB)

Osborn, R.N.; Olson, J.; Sommers, P.E.; McLaughlin, S.D.; Jackson, M.S.; Nadel, M.V.; Scott, W.G.; Connor, P.E.; Kerwin, N.; Kennedy, J.K. Jr.

1983-08-01

This two-volume report presents the results of initial research on the feasibility of applying organizational factors in nuclear power plant (NPP) safety assessment. Volume 1 of this report contains an overview of the literature, a discussion of available safety indicators, and a series of recommendations for more systematically incorporating organizational analysis into investigations of nuclear power plant safety. The six chapters of this volume discuss the major elements in our general approach to safety in the nuclear industry. The chapters include information on organizational design and safety; organizational governance; utility environment and safety related outcomes; assessments by selected federal agencies; review of data sources in the nuclear power industry; and existing safety indicators.

Inventory of Federal energy-related environment and safety research for FY 1978. Volume 1. Executive summary

International Nuclear Information System (INIS)

1979-12-01

The FY 1978 Federal Inventory is a compilation of 3225 federally funded energy-related environmental and safety reserch projects. It consists of three volumes: an executive summary providing an overview of the data (Volume I), a catalog listing each Inventory project followed by series of indexes (Volume II), and an interactive terminal guide giving instructions for on-line data retrieval (Volume III). Volume I reviews the inventory data as a whole and also within each of three major categories: biomedical and environmental research, environmental control technology research, and operational safety research

Survey of Biomass Gasification, Volume II: Principles of Gasification

Energy Technology Data Exchange (ETDEWEB)

Reed, T.B. (comp.)

1979-07-01

Biomass can be converted by gasification into a clean-burning gaseous fuel that can be used to retrofit existing gas/oil boilers, to power engines, to generate electricity, and as a base for synthesis of methanol, gasoline, ammonia, or methane. This survey describes biomass gasification, associated technologies, and issues in three volumes. Volume I contains the synopsis and executive summary, giving highlights of the findings of the other volumes. In Volume II the technical background necessary for understanding the science, engineering, and commercialization of biomass is presented. In Volume III the present status of gasification processes is described in detail, followed by chapters on economics, gas conditioning, fuel synthesis, the institutional role to be played by the federal government, and recommendations for future research and development.

Nuclear criticality safety experiments, calculations, and analyses: 1958 to 1982. Volume 1. Lookup tables

International Nuclear Information System (INIS)

Koponen, B.L.; Hampel, V.E.

1982-01-01

This compilation contains 688 complete summaries of papers on nuclear criticality safety as presented at meetings of the American Nuclear Society (ANS). The selected papers contain criticality parameters for fissile materials derived from experiments and calculations, as well as criticality safety analyses for fissile material processing, transport, and storage. The compilation was developed as a component of the Nuclear Criticality Information System (NCIS) now under development at the Lawrence Livermore National Laboratory. The compilation is presented in two volumes: Volume 1 contains a directory to the ANS Transaction volume and page number where each summary was originally published, the author concordance, and the subject concordance derived from the keyphrases in titles. Volume 2 contains - in chronological order - the full-text summaries, reproduced here by permission of the American Nuclear Society from their Transactions, volumes 1-41

Fast reactor safety: proceedings of the international topical meeting. Volume 1

Energy Technology Data Exchange (ETDEWEB)

1985-07-01

The emphasis of this meeting was on the safety-related aspects of fast reactor design, analysis, licensing, construction, and operation. Relative to past meetings, there was less emphasis on the scientific and technological basis for accident assessment. Because of its broad scope, the meeting attracted 217 attendees from a wide cross section of the design, safety analysis, and safety technology communities. Eight countries and two international organizations were represented. A total of 126 papers were presented, with contributions from the United States, France, Japan, the United Kingdom, Germany, and Italy. Sessions covered in Volume 1 include: impact of safety and licensing considerations on fast reactor design; safety aspects of innovative designs; intra-subassembly behavior; operational safety; design accommodation of seismic and other external events; natural circulation; safety design concepts; safety implications derived from operational plant data; decay heat removal; and assessment of HCDA consequences.

Fast reactor safety: proceedings of the international topical meeting. Volume 1

International Nuclear Information System (INIS)

1985-07-01

The emphasis of this meeting was on the safety-related aspects of fast reactor design, analysis, licensing, construction, and operation. Relative to past meetings, there was less emphasis on the scientific and technological basis for accident assessment. Because of its broad scope, the meeting attracted 217 attendees from a wide cross section of the design, safety analysis, and safety technology communities. Eight countries and two international organizations were represented. A total of 126 papers were presented, with contributions from the United States, France, Japan, the United Kingdom, Germany, and Italy. Sessions covered in Volume 1 include: impact of safety and licensing considerations on fast reactor design; safety aspects of innovative designs; intra-subassembly behavior; operational safety; design accommodation of seismic and other external events; natural circulation; safety design concepts; safety implications derived from operational plant data; decay heat removal; and assessment of HCDA consequences

The durban beach monitoring program: simple surveys speak volumes

CSIR Research Space (South Africa)

de Wet, p

2010-10-01

Full Text Available program: simple surveys speak volumes Pierre de Wet, Andrew Mather, Andr? Theron SAEON summit, 6 October 2010 ? CSIR 2010 Slide 1www.csir.co.za Outline ? Background / History ? Monitoring area circle6 Examples of survey data & trends circle6...) and near-shore deposition cf. classical understanding / scheme ? CSIR 2010 Slide 6 ? id. areas vulnerable to erosion ? effect of replenishment rates / locations visible Beach survey data s h o r e l i n e p o s i t i o n [ m...

2007 transparency and nuclear safety report. CEA Cadarache. Volumes 1 + 2

International Nuclear Information System (INIS)

2007-01-01

After a general presentation of the Cadarache site and of its nuclear installations, the first volume of this report describes the various measures concerning the site safety: safety organisation, general measures, measures related to various risks, control of emergency situations, inspections, audits and second level control, measures in basic nuclear installations. It describes the measures concerning the radioprotection on this site: organisation, significant facts, and dose measurement results. It describes significant events which occurred in relationship with nuclear safety and radioprotection, presents results of release measurements and of radiological and chemical assessments of the impact these releases on the environment. The report then describes measures implemented to limit the volume of stored radioactive wastes and also their impact on health and on the environment. It provides a series of tables indicating the nature and quantities of wastes which are stored in the different basic nuclear installations of Cadarache. It reports the recommendations expressed by the CHSCT (committee on hygiene, security and working conditions) after the 2006 report. The second volume proposes the same information for two specific nuclear installations belonging to Areva and located in Cadarache, the INB 32 and 54 (INB stands for basic nuclear installation), for which the significant events occurred on the 13. of March and on the 25. of May 2007. For these installations, release measurements concern gaseous and liquid releases

Maintaining Oversight of Licensee Safety Culture. CSNI/WGHOF Survey Results

International Nuclear Information System (INIS)

2008-01-01

In preparation for this workshop, a survey was sent to members of the WGHOF in Autumn 2006. Purpose of the Survey was to explore and share the methods and approaches used to maintain oversight of licensee safety culture. 13 countries responded to the survey. The responses were used in the development of discussion topics and themes for this workshop. This presentation (slides) summarizes the results of the survey

Occupational safety issues in residential construction surveyed in Wisconsin, United States.

Science.gov (United States)

Choi, Sang D; Carlson, Kathryn

2014-01-01

Residential construction is a high-risk industry in the U.S. due to the exposure to work-related safety hazards and fall injuries. This study aimed to examine the safety training and safe work practices of construction workers within the small residential construction industry. In order to achieve the study objectives, a survey was designed and sent to approximately 200 Wisconsin based residential construction contractors. About one third of the respondents stated that they did not have any form of safety programs. The study indicated that the most common types of work-related injuries in residential construction were slips/trips/falls and cuts/lacerations. The survey findings also suggested that the residential construction contractors needed to increase the utilization of fall protection safety equipment. Further education and subject matter expert training could provide benefits to improve occupational safety and health of the small business workforce in the residential construction industry.

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

International Nuclear Information System (INIS)

2004-07-01

the Safety Guide on 'Safety Assessment for Near Surface Disposal of Radioactive Waste' (Safety Standards Series No. WS-G- 1.1). The report of this CRP is presented in two volumes; Volume 1 contains a summary and a complete description of the ISAM project methodology and Volume 2 presents the application of the methodology to three hypothetical test cases

Survey of electronic safety systems in accelerator applications

International Nuclear Information System (INIS)

Mahoney, K.

1997-01-01

This paper presents the preliminary results and analysis of a comprehensive survey of the implementation of accelerator safety interlock systems from over 30 international labs. At the present time there is not a self consistent means to evaluate both the experiences and level of protection provided by electronic safety interlock systems. This research is intended to analyze the strength and weaknesses of several different types of interlock system implementation methodologies. Research, medical, and industrial accelerators are compared. Thomas Jefferson National Accelerator Facility (TJNAF) was one of the first large particle accelerators to implement a safety interlock system using programmable logic controllers. Since that time all of the major new U.S. accelerator construction projects plan to use some form of programmable electronics as part of a safety interlock system in some capacity

Organizational analysis and safety for utilities with nuclear power plants: an organizational overview. Volume 1. [PWR; BWR

Energy Technology Data Exchange (ETDEWEB)

Osborn, R.N.; Olson, J.; Sommers, P.E.; McLaughlin, S.D.; Jackson, M.S.; Scott, W.G.; Connor, P.E.

1983-08-01

This two-volume report presents the results of initial research on the feasibility of applying organizational factors in nuclear power plant (NPP) safety assessment. A model is introduced for the purposes of organizing the literature review and showing key relationships among identified organizational factors and nuclear power plant safety. Volume I of this report contains an overview of the literature, a discussion of available safety indicators, and a series of recommendations for more systematically incorporating organizational analysis into investigations of nuclear power plant safety.

A survey of electric and hybrid vehicles simulation programs. Volume 2: Questionnaire responses

Science.gov (United States)

Bevan, J.; Heimburger, D. A.; Metcalfe, M. A.

1978-01-01

The data received in a survey conducted within the United States to determine the extent of development and capabilities of automotive performance simulation programs suitable for electric and hybrid vehicle studies are presented. The survey was conducted for the Department of Energy by NASA's Jet Propulsion Laboratory. Volume 1 of this report summarizes and discusses the results contained in Volume 2.

Fast reactor safety: proceedings of the international topical meeting. Volume 2

International Nuclear Information System (INIS)

1985-07-01

The emphasis of this meeting was on the safety-related aspects of fast reactor design, analysis, licensing, construction, and operation. Relative to past meetings, there was less emphasis on the scientific and technological basis for accident assessment. Because of its broad scope, the meeting attracted 217 attendees from a wide cross section of the design, safety analysis, and safety technology communities. Eight countries and two international organizations were represented. A total of 126 papers were presented, with contributions from the United States, France, Japan, the United Kingdom, Germany, and Italy. Sessions covered in Volume 2 include: safety design concepts; operational transient experiments; analysis of seismic and external events; HCDA-related codes, analysis, and experiments; sodium fires; instrumentation and control/PPS design; whole-core accident analysis codes; and impact of safety design considerations on future LMFBR developments

Chemical Safety Vulnerability Working Group report. Volume 3

Energy Technology Data Exchange (ETDEWEB)

1994-09-01

The Chemical Safety Vulnerability (CSV) Working Group was established to identify adverse conditions involving hazardous chemicals at DOE facilities that might result in fires or explosions, release of hazardous chemicals to the environment, or exposure of workers or the public to chemicals. A CSV Review was conducted in 148 facilities at 29 sites. Eight generic vulnerabilities were documented related to: abandoned chemicals and chemical residuals; past chemical spills and ground releases; characterization of legacy chemicals and wastes; disposition of legacy chemicals; storage facilities and conditions; condition of facilities and support systems; unanalyzed and unaddressed hazards; and inventory control and tracking. Weaknesses in five programmatic areas were also identified related to: management commitment and planning; chemical safety management programs; aging facilities that continue to operate; nonoperating facilities awaiting deactivation; and resource allocations. Volume 3 consists of eleven appendices containing the following: Field verification reports for Idaho National Engineering Lab., Rocky Flats Plant, Brookhaven National Lab., Los Alamos National Lab., and Sandia National Laboratories (NM); Mini-visits to small DOE sites; Working Group meeting, June 7--8, 1994; Commendable practices; Related chemical safety initiatives at DOE; Regulatory framework and industry initiatives related to chemical safety; and Chemical inventory data from field self-evaluation reports.

Chemical Safety Vulnerability Working Group report. Volume 3

International Nuclear Information System (INIS)

1994-09-01

The Chemical Safety Vulnerability (CSV) Working Group was established to identify adverse conditions involving hazardous chemicals at DOE facilities that might result in fires or explosions, release of hazardous chemicals to the environment, or exposure of workers or the public to chemicals. A CSV Review was conducted in 148 facilities at 29 sites. Eight generic vulnerabilities were documented related to: abandoned chemicals and chemical residuals; past chemical spills and ground releases; characterization of legacy chemicals and wastes; disposition of legacy chemicals; storage facilities and conditions; condition of facilities and support systems; unanalyzed and unaddressed hazards; and inventory control and tracking. Weaknesses in five programmatic areas were also identified related to: management commitment and planning; chemical safety management programs; aging facilities that continue to operate; nonoperating facilities awaiting deactivation; and resource allocations. Volume 3 consists of eleven appendices containing the following: Field verification reports for Idaho National Engineering Lab., Rocky Flats Plant, Brookhaven National Lab., Los Alamos National Lab., and Sandia National Laboratories (NM); Mini-visits to small DOE sites; Working Group meeting, June 7--8, 1994; Commendable practices; Related chemical safety initiatives at DOE; Regulatory framework and industry initiatives related to chemical safety; and Chemical inventory data from field self-evaluation reports

Report on the results of the safety culture survey conducted in PNRI

International Nuclear Information System (INIS)

Garcia, Corazon M.; Nohay, Carl M.; Badinas, Nelson P.; Melendez, Johnylen V.; Parami, Vangeline K.

2001-01-01

An initial safety culture survey was conducted in the Philippine Nuclear Research Institute (PNRI). Sixty six (66) questionnaires as given in A. Adams and A. Williamson's Measurement of Safety Culture in the Nuclear Industry, UNSW, July 1999 were distributed to the different units of PNRI. The number of sets of survey sheets distributed to the different units corresponded to the number of personnel in the unit based on the information obtained from them. Results were obtained from only 33 respondents. ANSTO has been requested to analyze the results of this survey. While waiting for the results from ANSTO, we attempted to proceed with this analysis in order to learn and practice applying the procedure based on the reference cited above.The respondents from the PNRI showed on the overall neutral views towards safety and their work. Although a minority showed positive responses to safety while a small minority showed negative responses. A remarkable result is that all respondents show strong concern over the welfare of the institute, indicating that there is still a good chance for safety culture to be developed positively among the employees given the proper strategies for motivation. (author)

Workforce perceptions of hospital safety culture: development and validation of the patient safety climate in healthcare organizations survey.

Science.gov (United States)

Singer, Sara; Meterko, Mark; Baker, Laurence; Gaba, David; Falwell, Alyson; Rosen, Amy

2007-10-01

To describe the development of an instrument for assessing workforce perceptions of hospital safety culture and to assess its reliability and validity. Primary data collected between March 2004 and May 2005. Personnel from 105 U.S. hospitals completed a 38-item paper and pencil survey. We received 21,496 completed questionnaires, representing a 51 percent response rate. Based on review of existing safety climate surveys, we developed a list of key topics pertinent to maintaining a culture of safety in high-reliability organizations. We developed a draft questionnaire to address these topics and pilot tested it in four preliminary studies of hospital personnel. We modified the questionnaire based on experience and respondent feedback, and distributed the revised version to 42,249 hospital workers. We randomly divided respondents into derivation and validation samples. We applied exploratory factor analysis to responses in the derivation sample. We used those results to create scales in the validation sample, which we subjected to multitrait analysis (MTA). We identified nine constructs, three organizational factors, two unit factors, three individual factors, and one additional factor. Constructs demonstrated substantial convergent and discriminant validity in the MTA. Cronbach's alpha coefficients ranged from 0.50 to 0.89. It is possible to measure key salient features of hospital safety climate using a valid and reliable 38-item survey and appropriate hospital sample sizes. This instrument may be used in further studies to better understand the impact of safety climate on patient safety outcomes.

Safety Culture and Senior Leadership Behavior: Using Negative Safety Ratings to Align Clinical Staff and Senior Leadership.

Science.gov (United States)

O'Connor, Shawn; Carlson, Elizabeth

2016-04-01

This report describes how staff-designed behavior changes among senior leaders can have a positive impact on clinical nursing staff and enhance the culture of safety in a community hospital. A positive culture of safety in a hospital improves outcomes for patients and staff. Senior leaders are accountable for developing an environment that supports a culture of safety. At 1 community hospital, surveys demonstrated that staff members did not view senior leaders as supportive of or competent in creating a culture of safety. After approval from the hospital's institutional review board was obtained, clinical nurses generated and selected ideas for senior leader behavior change. The new behaviors were assessed by a convenience sample survey of clinical nurses. In addition, culture of safety survey results were compared. Risk reports and harm events were also measured before and after behavior changes. The volume of risk and near-miss reports increased, showing that clinical staff were more inclined to report events after senior leader communication, access, and visibility increased. Harm events went down. The culture of safety survey demonstrated an improvement in the senior leadership domain in 4 of 6 units. The anonymous convenience survey demonstrated that staff members recognized changes that senior leaders had made and felt that these changes positively impacted the culture of safety. By developing skills in communication, advocacy, visibility, and access, senior leaders can enhance a hospital's culture of safety and create stronger ties with clinical staff.

National Highway Traffic Safety Administration 1995 customer satisfaction survey

Science.gov (United States)

1996-05-01

The National Highway Traffic Safety Administration (NHTSA) conducted a national Customer Satisfaction Survey in response to the requirements of the National Performance Review and Executive Order 12862. An independent research organization, Schulman,...

Measurement of Food Safety Culture using Survey and Maturity Profiling Tools

OpenAIRE

Jespersen, Lone; Griffiths, Mansel; Maclaurin, Tanya; Chapman, Ben; Wallace, Carol A.

2016-01-01

Organizational culture is defined by dimensions and characteristics that can be used to measure food safety culture in food manufacturing through a food safety maturity model. Maturity models from quality, health care, and information technology have been used since early 1970 and this work presents a novel food safety culture maturity model with five capability areas and food safety pinpointed behaviours specific to functions and levels in a food manufacturing company. A survey tool linked t...

Comparing NICU teamwork and safety climate across two commonly used survey instruments.

Science.gov (United States)

Profit, Jochen; Lee, Henry C; Sharek, Paul J; Kan, Peggy; Nisbet, Courtney C; Thomas, Eric J; Etchegaray, Jason M; Sexton, Bryan

2016-12-01

Measurement and our understanding of safety culture are still evolving. The objectives of this study were to assess variation in safety and teamwork climate and in the neonatal intensive care unit (NICU) setting, and compare measurement of safety culture scales using two different instruments (Safety Attitudes Questionnaire (SAQ) and Hospital Survey on Patient Safety Culture (HSOPSC)). Cross-sectional survey study of a voluntary sample of 2073 (response rate 62.9%) health professionals in 44 NICUs. To compare survey instruments, we used Spearman's rank correlation coefficients. We also compared similar scales and items across the instruments using t tests and changes in quartile-level performance. We found significant variation across NICUs in safety and teamwork climate scales of SAQ and HSOPSC (pteamwork scales (teamwork climate and teamwork within units) of the two instruments correlated strongly (safety r=0.72, pteamwork r=0.67, p<0.001). However, the means and per cent agreements for all scale scores and even seemingly similar item scores were significantly different. In addition, comparisons of scale score quartiles between the two instruments revealed that half of the NICUs fell into different quartiles when translating between the instruments. Large variation and opportunities for improvement in patient safety culture exist across NICUs. Important systematic differences exist between SAQ and HSOPSC such that these instruments should not be used interchangeably. Published by the BMJ Publishing Group Limited. For permission to use (where not already granted under a licence) please go to http://www.bmj.com/company/products-services/rights-and-licensing/.

Airborne gamma-ray spectrometer and magnetometer survey. Volume I. Final report

International Nuclear Information System (INIS)

An airborne combined radiometric and magnetic survey was performed for the Department of Energy (DOE) over the area covered by the Mariposa, California and Nevada; Fresno, California; and Bakersfield, Caifornia 1:250,000 National Topographic Map Series (NTMS) 1 0 x 2 0 quadrangle maps. The survey was a part of DOE's National Aerial Radiometric Reconnaissance (ARR) program, which in turn is a part of the National Uranium Resource Evaluation (NURE) program. Data were collected by a helicopter equipped with a gamma-ray spectrometer having a large crystal volume, and a high sensitivity proton precession magnetometer. The radiometric system was calibrated at the Walker Field Calibration pads and the Lake Mead Dynamic Test range. Data quality was ensured throughout the survey by daily test flights and equipment checks. Radiometric data were corrected for live time, aircraft and equipment background, cosmic background, atmospheric radon, Compton scatter, and altitude dependence. The corrected data were statistically evaluated, plotted, and contoured to produce anomaly maps based on the radiometric response of individual geological units. These maps were interpreted and an anomaly interpretation map produced. Volume I contains a description of the systems used in the survey, a discussion of the calibration of the systems, the data processing procedures, the data display format, the interpretation rationale, and the interpretation methodology. A separate Volume II for each quadrangle contains the data displays and the interpretation results

Safety work organization in nuclear power plant. A9. Volume 2

International Nuclear Information System (INIS)

1985-01-01

The second volume provides the laws, directives, major standards, principles, lists of selected workplaces where woman work is prohibited, instructions for new personnel, general principles of workplace safety, reports and provisions by commissions for reporting accidents and injuries, recourses, etc. (J.P.)

National Highway Traffic Safety Administration : 1997 customer satisfaction survey

Science.gov (United States)

1998-03-13

In 1995, the National Highway Traffic Safety Administration (NHTSA) conducted its first Customer Satisfaction Survey in response to the requirements of the National Performance Review and Executive Order 12862. An independent research organization, S...

Survey of systems safety analysis methods and their application to nuclear waste management systems

International Nuclear Information System (INIS)

Pelto, P.J.; Winegardner, W.K.; Gallucci, R.H.V.

1981-11-01

This report reviews system safety analysis methods and examines their application to nuclear waste management systems. The safety analysis methods examined include expert opinion, maximum credible accident approach, design basis accidents approach, hazard indices, preliminary hazards analysis, failure modes and effects analysis, fault trees, event trees, cause-consequence diagrams, G0 methodology, Markov modeling, and a general category of consequence analysis models. Previous and ongoing studies on the safety of waste management systems are discussed along with their limitations and potential improvements. The major safety methods and waste management safety related studies are surveyed. This survey provides information on what safety methods are available, what waste management safety areas have been analyzed, and what are potential areas for future study

Survey of systems safety analysis methods and their application to nuclear waste management systems

Energy Technology Data Exchange (ETDEWEB)

Pelto, P.J.; Winegardner, W.K.; Gallucci, R.H.V.

1981-11-01

This report reviews system safety analysis methods and examines their application to nuclear waste management systems. The safety analysis methods examined include expert opinion, maximum credible accident approach, design basis accidents approach, hazard indices, preliminary hazards analysis, failure modes and effects analysis, fault trees, event trees, cause-consequence diagrams, G0 methodology, Markov modeling, and a general category of consequence analysis models. Previous and ongoing studies on the safety of waste management systems are discussed along with their limitations and potential improvements. The major safety methods and waste management safety related studies are surveyed. This survey provides information on what safety methods are available, what waste management safety areas have been analyzed, and what are potential areas for future study.

A survey on reliability and safety analysis techniques of robot systems in nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Eom, H S; Kim, J H; Lee, J C; Choi, Y R; Moon, S S

2000-12-01

The reliability and safety analysis techniques was surveyed for the purpose of overall quality improvement of reactor inspection system which is under development in our current project. The contents of this report are : 1. Reliability and safety analysis techniques suvey - Reviewed reliability and safety analysis techniques are generally accepted techniques in many industries including nuclear industry. And we selected a few techniques which are suitable for our robot system. They are falut tree analysis, failure mode and effect analysis, reliability block diagram, markov model, combinational method, and simulation method. 2. Survey on the characteristics of robot systems which are distinguished from other systems and which are important to the analysis. 3. Survey on the nuclear environmental factors which affect the reliability and safety analysis of robot system 4. Collection of the case studies of robot reliability and safety analysis which are performed in foreign countries. The analysis results of this survey will be applied to the improvement of reliability and safety of our robot system and also will be used for the formal qualification and certification of our reactor inspection system.

A survey on reliability and safety analysis techniques of robot systems in nuclear power plants

International Nuclear Information System (INIS)

Eom, H.S.; Kim, J.H.; Lee, J.C.; Choi, Y.R.; Moon, S.S.

2000-12-01

The reliability and safety analysis techniques was surveyed for the purpose of overall quality improvement of reactor inspection system which is under development in our current project. The contents of this report are : 1. Reliability and safety analysis techniques suvey - Reviewed reliability and safety analysis techniques are generally accepted techniques in many industries including nuclear industry. And we selected a few techniques which are suitable for our robot system. They are falut tree analysis, failure mode and effect analysis, reliability block diagram, markov model, combinational method, and simulation method. 2. Survey on the characteristics of robot systems which are distinguished from other systems and which are important to the analysis. 3. Survey on the nuclear environmental factors which affect the reliability and safety analysis of robot system 4. Collection of the case studies of robot reliability and safety analysis which are performed in foreign countries. The analysis results of this survey will be applied to the improvement of reliability and safety of our robot system and also will be used for the formal qualification and certification of our reactor inspection system

Survey of Employees' Safety Attitude in a Teaching Hospital Tehran 2010

Directory of Open Access Journals (Sweden)

M. Mahmmoudi

2011-01-01

Full Text Available Background and aimsThe Medical Errors and the potential unsafe actions are always regarded as a serious trouble by the managers and health care providers. Using the employees' attitude data as a measurement criterion in the evaluation of the hospitals performance in the field of the “Safety” can improve the safety level among the personnel and patients . Survey of employees' attitude about safety and its comparison with different groups of offering health services in a teaching Hospital was the main objective of present study.   MethodsIn order to specify patient safety culture in Moddares hospital, all employees including physicians, nurses, managers and employees of Para-clinic, a volume sample consisting of 212 persons were selected. Then it was used from questionnaire of safety attitude within 6 dimensions including Teamwork climate, Safety climate, perceptions of Management , Job Satisfaction, Working Conditions and Stress Recognition. At first this questionnaire was gone under assessing validity and trust. The scale of measuring, Likert was 5 grades. In order to specify difference between groups under study it was used from ANOVA test.   Results Positive safety culture within 6 dimensions including Teamwork Climate, Safety climate, Job Satisfaction, Stress Recognition, Perception of Management , Working Conditions for doctors were 3, 4.13, 17.4, 0, 4.3, and 8.7 respectively; the aforesaid Dimensions for nurses were 19, 2.6, 10.3, 7.8, 2.6 and 15.5 respectively, the aforesaid Dimensions for managers were 30.3, 6.1, 33.3, 0, 18.2 and 21.2 respectively and the aforesaid Dimensions for employees of Para-clinic Were 50, 12.5, 25, 12.5, 10 and 37.5 respectively. There was Significant difference from View Point of statistics (p<0.5 from Dimensions of Job satisfaction among managers and nurses, employees of Para-clinic and nurses this difference Were zero and 0.001. From View Point of Stress recognition among managers and employees of Para

PTAC driving safety survey results

Energy Technology Data Exchange (ETDEWEB)

Lloyd, E. [Petroleum Technology Alliance Canada, Calgary, AB (Canada)

2005-07-01

The results of a survey conducted by the Petroleum Technology Alliance Canada were presented. The survey identified ways in which companies in the oil and gas industry can reduce the potential for vehicle incidents, as well as improve fleet management techniques. Respondents provided a list of over 60 relevant technologies with high potential for application. Top driving safety challenges included adverse weather and road conditions, as well as driver attitude and awareness. Driver speed and fatigue were also seen as significant challenges, as well as encounters with wildlife and road conditions. Poor site conditions were also identified as a challenge, along with poor hazard recognition training, and lack of experience. A total of 157 representatives responded, whose fleets collectively drive approximately 136,500,000 km per year. The fleets totalled 15,800 vehicles. Respondents' affiliations with the oil and gas industry were included, as well as ownership classifications and company fleet sizes. Total annual fleet kilometers were presented, as well as the number of incidents per company per year, along with the number of respondents' animal strikes per year. tabs, figs.

Fast reactor safety: proceedings of the international topical meeting. Volume 2. [R

Energy Technology Data Exchange (ETDEWEB)

1985-07-01

The emphasis of this meeting was on the safety-related aspects of fast reactor design, analysis, licensing, construction, and operation. Relative to past meetings, there was less emphasis on the scientific and technological basis for accident assessment. Because of its broad scope, the meeting attracted 217 attendees from a wide cross section of the design, safety analysis, and safety technology communities. Eight countries and two international organizations were represented. A total of 126 papers were presented, with contributions from the United States, France, Japan, the United Kingdom, Germany, and Italy. Sessions covered in Volume 2 include: safety design concepts; operational transient experiments; analysis of seismic and external events; HCDA-related codes, analysis, and experiments; sodium fires; instrumentation and control/PPS design; whole-core accident analysis codes; and impact of safety design considerations on future LMFBR developments.

Analysis of the survey results for the safety culture attitudes of HANARO management division staff

Energy Technology Data Exchange (ETDEWEB)

Lee, M.; Hwang, S. Y.; Lim, I. C.; Kang, T. J.; Choi, H. Y

2003-12-01

This report provides the that analysis results of the surveys on the safety culture attitude and related topics for the HANARO Management Division staff. The survey form consisted of the questionnaire on the safety culture attitude, happiness and life style, drinking habit and traffic safety attitude. The key information drawn from the analysis are as follow; First, the level of safety culture attitude of the staff was confirmed and it was found that the attitude improved when the present analysis results were compared with them for the survey in 1998. Second, the degree of happiness that the staff feel is higher than the average Korean and they enjoy more leisure time than the average Korean. Third, the staff drink more alcohol than the average Korean. Thus, the drinking habit must be improved for the health of the staff. Fourth, the questionnaire of the happiness and the traffic safety attitude should be improved to verify the hypotheses on the relation between them and the safety culture attitude.

Analysis of the survey results for the safety culture attitudes of HANARO management division staff

International Nuclear Information System (INIS)

Lee, M.; Hwang, S. Y.; Lim, I. C.; Kang, T. J.; Choi, H. Y.

2003-12-01

This report provides the that analysis results of the surveys on the safety culture attitude and related topics for the HANARO Management Division staff. The survey form consisted of the questionnaire on the safety culture attitude, happiness and life style, drinking habit and traffic safety attitude. The key information drawn from the analysis are as follow; First, the level of safety culture attitude of the staff was confirmed and it was found that the attitude improved when the present analysis results were compared with them for the survey in 1998. Second, the degree of happiness that the staff feel is higher than the average Korean and they enjoy more leisure time than the average Korean. Third, the staff drink more alcohol than the average Korean. Thus, the drinking habit must be improved for the health of the staff. Fourth, the questionnaire of the happiness and the traffic safety attitude should be improved to verify the hypotheses on the relation between them and the safety culture attitude

Survey of factors associated with nurses' perception of patient safety.

Science.gov (United States)

Park, Sun A; Lee, Sui Jin; Choi, Go Un

2011-01-01

To describe the nurses' perception of hospital organization related to cultural issues on the safety of the patient and reporting medical errors. In addition, to identify factors associated with the safety of the patient and the nurse. A survey conducted during December 2008-Jannuary 2009, with 126 nurses using the Korean version of the AHRQ patient safety survey, a self-report 5-point Likert scale. Stata 10.0 was used for descriptive analysis, ANOVA (Analysis of variance) and logistic regression. National Cancer Center in Korea. The means for a working environment related to patient safety was 3.4 (±0.62). The associated factors of duration were at a present hospital, a special area, and direct contact with patients. Among organizational culture factors related to patient safety, the means were 3.81(±0.54) for the boss/manager's perception of patient safety and 3.37(±0.49) for the cooperation/collaboration between units. The frequent number of errors reported by nurses were 1~2(22.2%) times over the past 12 months. For incidence reporting, the items that the 'nurses perceived for communication among clinicians as fair' had a means of 3.23(±0.40) and the 'overall evaluation of patient safety was a good' 3.34(±0.73). The nurses' perception of cooperation and collaboration between units were associated with the direct contact between the patient and the nurse. The frequency of incidence reporting was associated with the duration of working hours at the present hospital and also their work experience. The nurses' perception of hospital environment, organizational culture, and incidence reporting was above average and mostly associated with organizational culture.

Chemical Safety Vulnerability Working Group report. Volume 1

Energy Technology Data Exchange (ETDEWEB)

1994-09-01

The Chemical Safety Vulnerability (CSV) Working Group was established to identify adverse conditions involving hazardous chemicals at DOE facilities that might result in fires or explosions, release of hazardous chemicals to the environment, or exposure of workers or the public to chemicals. A CSV Review was conducted in 148 facilities at 29 sites. Eight generic vulnerabilities were documented related to: abandoned chemicals and chemical residuals; past chemical spills and ground releases; characterization of legacy chemicals and wastes; disposition of legacy chemicals; storage facilities and conditions; condition of facilities and support systems; unanalyzed and unaddressed hazards; and inventory control and tracking. Weaknesses in five programmatic areas were also identified related to: management commitment and planning; chemical safety management programs; aging facilities that continue to operate; nonoperating facilities awaiting deactivation; and resource allocations. Volume 1 contains the Executive summary; Introduction; Summary of vulnerabilities; Management systems weaknesses; Commendable practices; Summary of management response plan; Conclusions; and a Glossary of chemical terms.

Chemical Safety Vulnerability Working Group report. Volume 1

International Nuclear Information System (INIS)

1994-09-01

The Chemical Safety Vulnerability (CSV) Working Group was established to identify adverse conditions involving hazardous chemicals at DOE facilities that might result in fires or explosions, release of hazardous chemicals to the environment, or exposure of workers or the public to chemicals. A CSV Review was conducted in 148 facilities at 29 sites. Eight generic vulnerabilities were documented related to: abandoned chemicals and chemical residuals; past chemical spills and ground releases; characterization of legacy chemicals and wastes; disposition of legacy chemicals; storage facilities and conditions; condition of facilities and support systems; unanalyzed and unaddressed hazards; and inventory control and tracking. Weaknesses in five programmatic areas were also identified related to: management commitment and planning; chemical safety management programs; aging facilities that continue to operate; nonoperating facilities awaiting deactivation; and resource allocations. Volume 1 contains the Executive summary; Introduction; Summary of vulnerabilities; Management systems weaknesses; Commendable practices; Summary of management response plan; Conclusions; and a Glossary of chemical terms

A Survey of Pilots on the Dissemination of Safety Information

National Research Council Canada - National Science Library

Rakovan, Lori

1999-01-01

A survey was conducted to obtain information from the pilot population on erections of safety-related training currently being offered, its usefulness, and the process through which it might be better...

Work health and safety in cotton ginning industry: a survey of practices in australia

International Nuclear Information System (INIS)

Soomro, N.

2015-01-01

This survey focuses on the WH and S (Work Health and Safety) practices in Australia and relates them with those in Pakistan. It also highlights the planned areas of work required on WH and S in cotton ginning industry of Pakistan. This article is one a series of research studies that will inform a broader approach development. The aim of the survey was to design a standardized health and safety Act for cotton ginning industry of Pakistan and to help ginners meet their due industry obligations under the model WH and S Act. The first component of the research study survey was to review the relevant Australian work and safety model as this provides a framework to protect the health, safety and welfare of all employees at work and of other people who might be affected by the job. The second aspect of the research study survey concerned site visits to cotton gins with the support of Australian Centre for Agricultural Health and Safety, Moree, NSW. During these visits the existing ginning process in terms of WH and S were reviewed. Informal interviews were also conducted with Gin Managers and Ginning Experts regarding WH and S in the Australian cotton ginning industry. (author)

Safety practices, perceptions, and behaviors in radiation oncology: A national survey of radiation therapists.

Science.gov (United States)

Woodhouse, Kristina Demas; Hashemi, David; Betcher, Kathryn; Doucette, Abigail; Weaver, Allison; Monzon, Brian; Rosenthal, Seth A; Vapiwala, Neha

Radiation therapy is complex and demands high vigilance and precise coordination. Radiation therapists (RTTs) directly deliver radiation and are often the first to discover an error. Yet, few studies have examined the practices of RTTs regarding patient safety. We conducted a national survey to explore the perspectives of RTTs related to quality and safety. In 2016, an electronic survey was sent to a random sample of 1500 RTTs in the United States. The survey assessed department safety, error reporting, safety knowledge, and culture. Questions were multiple choice or recorded on a Likert scale. Results were summarized using descriptive statistics and analyzed using multivariate logistic regression. A total of 702 RTTs from 49 states (47% response rate) completed the survey. Respondents represented a broad distribution across practice settings. Most RTTs rated department patient safety as excellent (61%) or very good (32%), especially if they had an incident learning system (ILS) (odds ratio, 2.0). Only 21% reported using an ILS despite 58% reporting an accessible ILS in their department. RTTs felt errors were most likely to occur with longer shifts and poor multidisciplinary communication; 40% reported that burnout and anxiety negatively affected their ability to deliver care. Workplace bullying was also reported among 17%. Overall, there was interest (62%) in improving knowledge in patient safety. Although most RTTs reported excellent safety cultures within their facilities, overall, there was limited access to and utilization of ILSs by RTTs. Workplace issues identified may also represent barriers to delivering quality care. RTTs were also interested in additional resources regarding quality and safety. These results will further enhance safety initiatives and inform future innovative educational efforts in radiation oncology. Copyright © 2017 American Society for Radiation Oncology. Published by Elsevier Inc. All rights reserved.

[Adaptation of the Medical Office Survey on Patient Safety Culture (MOSPSC) tool].

Science.gov (United States)

Silvestre-Busto, C; Torijano-Casalengua, M L; Olivera-Cañadas, G; Astier-Peña, M P; Maderuelo-Fernández, J A; Rubio-Aguado, E A

2015-01-01

To adapt the Medical Office Survey on Patient Safety Culture (MOSPSC) Excel(®) tool for its use by Primary Care Teams of the Spanish National Public Health System. The process of translation and adaptation of MOSPSC from the Agency for Healthcare and Research in Quality (AHRQ) was performed in five steps: Original version translation, Conceptual equivalence evaluation, Acceptability and viability assessment, Content validity and Questionnaire test and response analysis, and psychometric properties assessment. After confirming MOSPSC as a valid, reliable, consistent and useful tool for assessing patient safety culture in our setting, an Excel(®) worksheet was translated and adapted in the same way. It was decided to develop a tool to analyze the "Spanish survey" and to keep it linked to the "Original version" tool. The "Spanish survey" comparison data are those obtained in a 2011 nationwide Spanish survey, while the "Original version" comparison data are those provided by the AHRQ in 2012. The translated and adapted tool and the analysis of the results from a 2011 nationwide Spanish survey are available on the website of the Ministry of Health, Social Services and Equality. It allows the questions which are decisive in the different dimensions to be determined, and it provides a comparison of the results with graphical representation. Translation and adaptation of this tool enables a patient safety culture in Primary Care in Spain to be more effectively applied. Copyright © 2014 SECA. Published by Elsevier Espana. All rights reserved.

Factors controlling volume errors through 2D gully erosion assessment: guidelines for optimal survey design

Science.gov (United States)

Castillo, Carlos; Pérez, Rafael

2017-04-01

The assessment of gully erosion volumes is essential for the quantification of soil losses derived from this relevant degradation process. Traditionally, 2D and 3D approaches has been applied for this purpose (Casalí et al., 2006). Although innovative 3D approaches have recently been proposed for gully volume quantification, a renewed interest can be found in literature regarding the useful information that cross-section analysis still provides in gully erosion research. Moreover, the application of methods based on 2D approaches can be the most cost-effective approach in many situations such as preliminary studies with low accuracy requirements or surveys under time or budget constraints. The main aim of this work is to examine the key factors controlling volume error variability in 2D gully assessment by means of a stochastic experiment involving a Monte Carlo analysis over synthetic gully profiles in order to 1) contribute to a better understanding of the drivers and magnitude of gully erosion 2D-surveys uncertainty and 2) provide guidelines for optimal survey designs. Owing to the stochastic properties of error generation in 2D volume assessment, a statistical approach was followed to generate a large and significant set of gully reach configurations to evaluate quantitatively the influence of the main factors controlling the uncertainty of the volume assessment. For this purpose, a simulation algorithm in Matlab® code was written, involving the following stages: - Generation of synthetic gully area profiles with different degrees of complexity (characterized by the cross-section variability) - Simulation of field measurements characterised by a survey intensity and the precision of the measurement method - Quantification of the volume error uncertainty as a function of the key factors In this communication we will present the relationships between volume error and the studied factors and propose guidelines for 2D field surveys based on the minimal survey

Chemical Safety Vulnerability Working Group report. Volume 2

International Nuclear Information System (INIS)

1994-09-01

The Chemical Safety Vulnerability (CSV) Working Group was established to identify adverse conditions involving hazardous chemicals at DOE facilities that might result in fires or explosions, release of hazardous chemicals to the environment, or exposure of workers or the public to chemicals. A CSV Review was conducted in 148 facilities at 29 sites. Eight generic vulnerabilities were documented related to: abandoned chemicals and chemical residuals; past chemical spills and ground releases; characterization of legacy chemicals and wastes; disposition of legacy chemicals; storage facilities and conditions; condition of facilities and support systems; unanalyzed and unaddressed hazards; and inventory control and tracking. Weaknesses in five programmatic areas were also identified related to: management commitment and planning; chemical safety management programs; aging facilities that continue to operate; nonoperating facilities awaiting deactivation; and resource allocations. Volume 2 consists of seven appendices containing the following: Tasking memorandums; Project plan for the CSV Review; Field verification guide for the CSV Review; Field verification report, Lawrence Livermore National Lab.; Field verification report, Oak Ridge Reservation; Field verification report, Savannah River Site; and the Field verification report, Hanford Site

Chemical Safety Vulnerability Working Group report. Volume 2

Energy Technology Data Exchange (ETDEWEB)

1994-09-01

The Chemical Safety Vulnerability (CSV) Working Group was established to identify adverse conditions involving hazardous chemicals at DOE facilities that might result in fires or explosions, release of hazardous chemicals to the environment, or exposure of workers or the public to chemicals. A CSV Review was conducted in 148 facilities at 29 sites. Eight generic vulnerabilities were documented related to: abandoned chemicals and chemical residuals; past chemical spills and ground releases; characterization of legacy chemicals and wastes; disposition of legacy chemicals; storage facilities and conditions; condition of facilities and support systems; unanalyzed and unaddressed hazards; and inventory control and tracking. Weaknesses in five programmatic areas were also identified related to: management commitment and planning; chemical safety management programs; aging facilities that continue to operate; nonoperating facilities awaiting deactivation; and resource allocations. Volume 2 consists of seven appendices containing the following: Tasking memorandums; Project plan for the CSV Review; Field verification guide for the CSV Review; Field verification report, Lawrence Livermore National Lab.; Field verification report, Oak Ridge Reservation; Field verification report, Savannah River Site; and the Field verification report, Hanford Site.

Agricultural Health and Safety Survey in Friuli Venezia Giulia

Directory of Open Access Journals (Sweden)

Sirio Rossano Secondo Cividino

2018-01-01

Full Text Available The work in the agricultural sector has taken on a fundamental role in the last decades, due to the still too high rate of fatal injuries, workplace accidents, and dangerous occurrences reported each year. The average old age of agricultural machinery is one of the main issues at stake in Italy. Numerous safety problems stem from that; therefore, two surveys were conducted in two different periods, on current levels of work safety in agriculture in relation to agricultural machinery’s age and efficiency, and to show the levels of actual implementation of the Italian legislation on safety and health at work in the agricultural sector. The surveys were carried out, considering a sample of 161 farms located in the region Friuli Venezia Giulia (North-East of Italy. The research highlights the most significant difficulties the sample of farms considered have in enforcing the law. One hand, sanitary surveillance and workers’ information and training represent the main deficiencies and weakest points in family farms. Moreover, family farms do not generally provide the proper documentation concerning health and safety at workplaces, when they award the contract to other companies. On the other hand, lack of maintenance program for machinery and equipment, and of emergency plans and participation of workers’ health and safety representative, are the most common issues in farms with employees. Several difficulties are also evident in planning workers’ training programs. Furthermore, the company physician’s task is often limited to medical controls, so that he is not involved in risk assessment and training. Interviews in heterogeneous samples of farms have shown meaningful outcomes, which have subsequently been used to implement new databases and guidelines for Health and Safety Experts and courses in the field of Work Safety in agriculture. In conclusion, although the legislation making training courses for tractor operators and tractor

Environmental, health, and safety issues of sodium-sulfur batteries for electric and hybrid vehicles. Volume 4, In-vehicle safety

Energy Technology Data Exchange (ETDEWEB)

Mark, J.

1992-11-01

This report is the last of four volumes that identify and assess the environmental, health, and safety issues that may affect the commercial-scale use of sodium-sulfur (Na/S) battery technology as the energy source in electric and hybrid vehicles. The reports are intended to help the Electric and Hybrid Propulsion Division of the Office of Transportation Technologies in the US Department of Energy (DOE/EHP) determine the direction of its research, development, and demonstration (RD&D) program for Na/S battery technology. The reports review the status of Na/S battery RD&D and identify potential hazards and risks that may require additional research or that may affect the design and use of Na/S batteries. This volume covers the in-vehicle safety issues of electric vehicles powered by Na/S batteries. The report is based on a review of the literature and on discussions with experts at DOE, national laboratories and agencies, and private industry. It has three major goals: (1) to identify the unique hazards associated with electric vehicle (EV) use; (2) to describe the existing standards, regulations, and guidelines that are or could be applicable to these hazards; and (3) to discuss the adequacy of the existing requirements in addressing the safety concerns of EVs.

A VOLUME-LIMITED PHOTOMETRIC SURVEY OF 114 γ DORADUS CANDIDATES

International Nuclear Information System (INIS)

Henry, Gregory W.; Fekel, Francis C.; Henry, Stephen M.

2011-01-01

We have carried out a photometric survey of a complete, volume-limited sample of γ Doradus candidates. The sample was extracted from the Hipparcos catalog and consists of 114 stars with colors and absolute magnitudes within the range of known γ Doradus stars and that also lie within a specified volume of 266,600 pc 3 . We devoted one year of observing time with our T12 0.8 m automatic photometric telescope to acquire nightly observations of the complete sample of stars. From these survey observations, we identify 37 stars with intrinsic variability of 0.002 mag or more. Of these 37 variables, 8 have already been confirmed as γ Doradus stars in our earlier papers; we scheduled the remaining 29 variables on our T3 0.4 m automatic telescope to acquire more intensive observations over the next two years. As promising new γ Doradus candidates were identified from the photometry, we obtained complementary spectroscopic observations of each candidate with the Kitt Peak coude feed telescope. Analysis of our new photometric and spectroscopic data reveals 15 new γ Doradus variables (and confirms two others), 8 new δ Scuti variables (and confirms one other), and 3 new variables with unresolved periodicity. Therefore, of the 114 γ Doradus candidates in our volume-limited sample, we find 25 stars that are new or previously known γ Doradus variables. This results in an incidence of 22% for γ Doradus variability among candidate field stars for this volume of the solar neighborhood. The corresponding space density of γ Doradus stars in this volume of space is 0.094 stars per 10 3 pc 3 or 94 stars per 10 6 pc 3 . We provide an updated list of 86 bright, confirmed, γ Doradus field stars.

Safety in Academic Chemistry Laboratories: Volume 2. Accident Prevention for Faculty and Administrators, 7th Edition.

Science.gov (United States)

American Chemical Society, Washington, DC.

This book contains volume 2 of 2 and describes safety guidelines for academic chemistry laboratories to prevent accidents for college and university students. Contents include: (1) "Organizing for Accident Prevention"; (2) "Personal Protective Equipment"; (3) "Labeling"; (4) "Material Safety Data Sheets (MSDSs)"; (5) "Preparing for Medical…

Survey of instrumentation for environmental monitoring: major update. Volume 3. Radiation

Energy Technology Data Exchange (ETDEWEB)

1979-09-01

This is the third volume of a four-volume (seven-part) series, the culmination of a comprehensive survey of instrumentation for environmental monitoring. Consideration is given to instruments and techniques presently in use and to those developed for other purposes but having possible applications to radiation monitoring. The results of the survey are given as descriptions of the physical and operating characteristics of available instruments, critical comparisons among instrumentation methods, and recommendations of promising methodology and development of new instrumentation. Information is also given regarding the pollutants to be monitored, their characteristics and forms, their sources and pathways, their effects on the ecosystem, and the means of controlling them through process and regulatory controls. The discussion is presented under sections entitled radiation sources; instrumentation: by type of radiation or instrument type; and, instrumentation for specific radionuclides. (JGB)

Survey of instrumentation for environmental monitoring: major update. Volume 3. Radiation

International Nuclear Information System (INIS)

1979-09-01

This is the third volume of a four-volume (seven-part) series, the culmination of a comprehensive survey of instrumentation for environmental monitoring. Consideration is given to instruments and techniques presently in use and to those developed for other purposes but having possible applications to radiation monitoring. The results of the survey are given as descriptions of the physical and operating characteristics of available instruments, critical comparisons among instrumentation methods, and recommendations of promising methodology and development of new instrumentation. Information is also given regarding the pollutants to be monitored, their characteristics and forms, their sources and pathways, their effects on the ecosystem, and the means of controlling them through process and regulatory controls. The discussion is presented under sections entitled radiation sources; instrumentation: by type of radiation or instrument type; and, instrumentation for specific radionuclides

Photonics for safety and security

CERN Document Server

Mignani, Anna Grazia; Tajani, Antonella

2014-01-01

This volume aims to illustrate the state-of-the-art as well as the newest and latest applications of photonics in safety and security. The contributions from renowned and experienced Italian and international scientists, both from the academic and industrial community, present a multidisciplinary and comprehensive overview of this popular topic. The volume is self-contained and offers a broad survey of the various emerging technologies, as well as their applications in the real world. It spans from applications in cultural heritage, to environment, space, monitoring of coasts, quantum cryptogr

Evaluation of a survey tool to measure safety climate in Australian hospital pharmacy staff.

Science.gov (United States)

Walpola, Ramesh L; Chen, Timothy F; Fois, Romano A; Ashcroft, Darren M; Lalor, Daniel J

Safety climate evaluation is increasingly used by hospitals as part of quality improvement initiatives. Consequently, it is necessary to have validated tools to measure changes. To evaluate the construct validity and internal consistency of a survey tool to measure Australian hospital pharmacy patient safety climate. A 42 item cross-sectional survey was used to evaluate the patient safety climate of 607 Australian hospital pharmacy staff. Survey responses were initially mapped to the factor structure previously identified in European community pharmacy. However, as the data did not adequately fit the community pharmacy model, participants were randomly split into two groups with exploratory factor analysis performed on the first group (n = 302) and confirmatory factor analyses performed on the second group (n = 305). Following exploratory factor analysis (59.3% variance explained) and confirmatory factor analysis, a 6-factor model containing 28 items was obtained with satisfactory model fit (χ 2 (335) = 664.61 p  0.643) and model nesting between the groups (Δχ 2 (22) = 30.87, p = 0.10). Three factors (blame culture, organisational learning and working conditions) were similar to those identified in European community pharmacy and labelled identically. Three additional factors (preoccupation with improvement; comfort to question authority; and safety issues being swept under the carpet) highlight hierarchical issues present in hospital settings. This study has demonstrated the validity of a survey to evaluate patient safety climate of Australian hospital pharmacy staff. Importantly, this validated factor structure may be used to evaluate changes in safety climate over time. Copyright © 2016 Elsevier Inc. All rights reserved.

School Safety, Severe Disciplinary Actions, and School Characteristics: A Secondary Analysis of the School Survey on Crime and Safety

Science.gov (United States)

Han, Seunghee; Akiba, Motoko

2011-01-01

On the basis of a secondary analysis of survey data collected from 1,872 secondary school principals in the 2005-2006 School Survey on Crime and Safety, we examined the frequency of and reasons for severe disciplinary actions and the relationship between school characteristics and severe disciplinary actions. We found that severe disciplinary…

Patient safety in practical nurses' education: A cross-sectional survey of newly registered practical nurses in Canada.

Science.gov (United States)

VanDenKerkhof, Elizabeth; Sears, Nancy; Edge, Dana S; Tregunno, Deborah; Ginsburg, Liane

2017-04-01

Practical nurses have experienced an increasing scope of practice, including an expectation to care for complex patients and function on interdisciplinary teams. Little is known about the degree to which patient safety principles are addressed in practical nursing education. To examine self-reported patient safety competencies of practical nurses. A cross-sectional online survey (July 2014) and face-to-face interviews (June 2015). Ontario, Canada. Survey participants were practical nurses newly registered with the College of Nurses of Ontario between January 2012 and December 2013. Interview participants were faculty and students in a practical nursing program in Ontario. Survey respondents completed the Health Professional Education in Patient Safety Survey online. Self-reported competencies in various patient safety domains were compared between classroom and clinical settings. Faculty members were interviewed about educational preparation of practical nurses and students were interviewed to provide insight into interpretation of survey questions. The survey response rate was 28.4% (n=1104/3883). Mean domain scores indicated a high level of confidence in patient safety competence (Nurses of Ontario >2years and in those who obtained their education outside of Canada. Faculty believed their approach to teaching and learning instilled a deep understanding of the limits to practical nurse autonomous practice. Practical nurses were confident in what they learned about patient safety in their educational programs. The high degree of patient safety competence may be a true reflection of practical nurses understanding of, and comfort with, the limits of their knowledge and, ultimately, the limits of their individual autonomous practice. Further exploration as to whether the questionnaire requires additional modification for use with practical nurse populations is warranted. However, this study provides the first examination of practical nurses' perspectives and

Probabilistic safety analysis procedures guide, Sections 8-12. Volume 2, Rev. 1

International Nuclear Information System (INIS)

McCann, M.; Reed, J.; Ruger, C.; Shiu, K.; Teichmann, T.; Unione, A.; Youngblood, R.

1985-08-01

A procedures guide for the performance of probabilistic safety assessment has been prepared for interim use in the Nuclear Regulatory Commission programs. It will be revised as comments are received, and as experience is gained from its use. 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 issues affecting reactor safety. The first volume of the guide describes the determination of the probability (per year) of core damage resulting from accident initiators internal to the plant (i.e., intrinsic to plant operation) and from loss of off-site electric power. The scope includes human reliability analysis, a determination of the importance of various core damage accident sequences, and an explicit treatment and display of uncertainties for key accident sequences. This second volume deals with the treatment of the so-called external events including seismic disturbances, fires, floods, etc. Ultimately, the guide will be augmented to include the plant-specific analysis of in-plant processes (i.e., containment performance). This guide provides the structure of a probabilistic safety study to be performed, and indicates what products of the study are valuable for regulatory decision making. For internal events, 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. For external events, more explicit guidance is given

The Local Volume HI Survey (LVHIS)

Science.gov (United States)

Koribalski, Bärbel S.; Wang, Jing; Kamphuis, P.; Westmeier, T.; Staveley-Smith, L.; Oh, S.; López-Sánchez, Á. R.; Wong, O. I.; Ott, J.; de Blok, W. J. G.; Shao, L.

2018-02-01

The `Local Volume HI Survey' (LVHIS) comprises deep H I spectral line and 20-cm radio continuum observations of 82 nearby, gas-rich galaxies, supplemented by multi-wavelength images. Our sample consists of all galaxies with Local Group velocities vLG atlas, including the overall gas distribution, mean velocity field, velocity dispersion and position-velocity diagrams, together with a homogeneous set of measured and derived galaxy properties. Our primary goal is to investigate the H I morphologies, kinematics and environment at high resolution and sensitivity. LVHIS galaxies represent a wide range of morphologies and sizes; our measured H I masses range from ˜107 to 1010 M⊙, based on independent distance estimates. The LVHIS galaxy atlas (incl. FITS files) is available on-line.

THE SPITZER LOCAL VOLUME LEGACY: SURVEY DESCRIPTION AND INFRARED PHOTOMETRY

International Nuclear Information System (INIS)

Dale, D. A.; Cohen, S. A.; Johnson, L. C.; Schuster, M. D.; Calzetti, D.; Engelbracht, C. W.; Kennicutt, R. C.; Block, M.; Marble, A. R.; Gil de Paz, A.; Lee, J. C.; Begum, A.; Dalcanton, J. J.; Funes, J. G.; Gordon, K. D.; Johnson, B. D.; Sakai, S.; Skillman, E. D.; Van Zee, L.; Walter, F.

2009-01-01

The survey description and the near-, mid-, and far-infrared flux properties are presented for the 258 galaxies in the Local Volume Legacy (LVL). LVL is a Spitzer Space Telescope legacy program that surveys the local universe out to 11 Mpc, built upon a foundation of ultraviolet, Hα, and Hubble Space Telescope imaging from 11HUGS (11 Mpc Hα and Ultraviolet Galaxy Survey) and ANGST (ACS Nearby Galaxy Survey Treasury). LVL covers an unbiased, representative, and statistically robust sample of nearby star-forming galaxies, exploiting the highest extragalactic spatial resolution achievable with Spitzer. As a result of its approximately volume-limited nature, LVL augments previous Spitzer observations of present-day galaxies with improved sampling of the low-luminosity galaxy population. The collection of LVL galaxies shows a large spread in mid-infrared colors, likely due to the conspicuous deficiency of 8 μm polycyclic aromatic hydrocarbon emission from low-metallicity, low-luminosity galaxies. Conversely, the far-infrared emission tightly tracks the total infrared emission, with a dispersion in their flux ratio of only 0.1 dex. In terms of the relation between the infrared-to-ultraviolet ratio and the ultraviolet spectral slope, the LVL sample shows redder colors and/or lower infrared-to-ultraviolet ratios than starburst galaxies, suggesting that reprocessing by dust is less important in the lower mass systems that dominate the LVL sample. Comparisons with theoretical models suggest that the amplitude of deviations from the relation found for starburst galaxies correlates with the age of the stellar populations that dominate the ultraviolet/optical luminosities.

[Patient safety culture in hospitals: experiences in planning, organising and conducting a survey among hospital staff].

Science.gov (United States)

van Vegten, Amanda; Pfeiffer, Yvonne; Giuliani, Francesca; Manser, Tanja

2011-01-01

This article presents the first hospital-wide survey on patient safety climate, involving all staff (medical and non-medical), in the German-speaking area. Its aim is to share our experiences with planning, organising and conducting this survey. The study was performed at the university hospital in Zurich and had a response rate of 46.8% (2,897 valid questionnaires). The survey instrument ("Patientensicherheitsklimainventar") was based on the Hospital Survey on Patient Safety Culture (AHRQ). Primarily it allowed for assessing the current patient safety climate as well as identifying specific areas for improvement and creating a hospital-wide awareness and acceptance for patient safety issues and interventions (e.g., the introduction of a Critical Incident Reporting System [CIRS]). We discuss the basic principles and the feedback concept guiding the organisation of the overall project. Critical to the success of this project were the guaranteed anonymity of the respondents, adequate communication through well-established channels within the organisation and the commitment of the management across all project phases. Copyright © 2011. Published by Elsevier GmbH.

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

Science.gov (United States)

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

2014-06-30

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

A Study of Coal Miners’ Safety Psychological Elements Based on Questionnaire Survey

Directory of Open Access Journals (Sweden)

Li Zeng-bo

2016-01-01

Full Text Available During the production process, the instability of safety psychological elements of coal miners contributes to unsafe behaviors that may result in fatal accident. To search the dominant psychological elements, three types of unsafe psychology, comprising 18 unsafe psychological elements, are obtained by theoretical analysis and site survey. Then, an assessment model is established, and a matched questionnaire is applied to two large modern coal mines in Inner Mongolia Autonomous Region. Based on questionnaire survey results and analytic hierarchy process (AHP, assessment judgment matrixes are constructed, effect weight is calculated, and consistency check is conducted. The analysis results show that safety psychology elements of defective type are the dominant elements that trigger unsafe behaviors of coal miners.

The impact of nurse working hours on patient safety culture: a cross-national survey including Japan, the United States and Chinese Taiwan using the Hospital Survey on Patient Safety Culture

OpenAIRE

Wu, Yinghui; Fujita, Shigeru; Seto, Kanako; Ito, Shinya; Matsumoto, Kunichika; Huang, Chiu-Chin; Hasegawa, Tomonori

2013-01-01

Background A positive patient safety culture (PSC) is one of the most critical components to improve healthcare quality and safety. The Hospital Survey on Patient Safety Culture (HSOPS), developed by the US Agency for Healthcare Research and Quality, has been used to assess PSC in 31 countries. However, little is known about the impact of nurse working hours on PSC. We hypothesized that long nurse working hours would deteriorate PSC, and that the deterioration patterns would vary between coun...

NIOSH national survey of long-haul truck drivers: Injury and safety

Science.gov (United States)

Chen, Guang X.; Sieber, W. Karl; Lincoln, Jennifer E.; Birdsey, Jan; Hitchcock, Edward M.; Nakata, Akinori; Robinson, Cynthia F.; Collins, James W.; Sweeney, Marie H.

2015-01-01

Approximately 1,701,500 people were employed as heavy and tractor-trailer truck drivers in the United States in 2012. The majority of them were long-haul truck drivers (LHTDs). There are limited data on occupational injury and safety in LHTDs, which prompted a targeted national survey. The National Institute of Occupational Safety and Health conducted a nationally representative survey of 1265 LHTDs at 32 truck stops across the contiguous United States in 2010. Data were collected on truck crashes, near misses, moving violations, work-related injuries, work environment, safety climate, driver training, job satisfaction, and driving behaviors. Results suggested that an estimated 2.6% of LHTDs reported a truck crash in 2010, 35% reported at least one crash while working as an LHTD, 24% reported at least one near miss in the previous 7 days, 17% reported at least one moving violation ticket and 4.7% reported a non-crash injury involving days away from work in the previous 12 months. The majority (68%) of non-crash injuries among company drivers were not reported to employers. An estimate of 73% of LHTDs (16% often and 58% sometimes) perceived their delivery schedules unrealistically tight; 24% often continued driving despite fatigue, bad weather, or heavy traffic because they needed to deliver or pick up a load at a given time; 4.5% often drove 10 miles per hours or more over the speed limit; 6.0% never wore a seatbelt; 36% were often frustrated by other drivers on the road; 35% often had to wait for access to a loading dock; 37% reported being noncompliant with hours-of-service rules (10% often and 27% sometimes); 38% of LHTDs perceived their entry-level training inadequate; and 15% did not feel that safety of workers was a high priority with their management. This survey brings to light a number of important safety issues for further research and interventions, e.g., high prevalence of truck crashes, injury underreporting, unrealistically tight delivery schedules

A security/safety survey of long term care facilities.

Science.gov (United States)

Acorn, Jonathan R

2010-01-01

What are the major security/safety problems of long term care facilities? What steps are being taken by some facilities to mitigate such problems? Answers to these questions can be found in a survey of IAHSS members involved in long term care security conducted for the IAHSS Long Term Care Security Task Force. The survey, the author points out, focuses primarily on long term care facilities operated by hospitals and health systems. However, he believes, it does accurately reflect the security problems most long term facilities face, and presents valuable information on security systems and practices which should be also considered by independent and chain operated facilities.

Safety in Academic Chemistry Laboratories: Volume 1. Accident Prevention for College and University Students, 7th Edition.

Science.gov (United States)

American Chemical Society, Washington, DC.

This book contains volume 1 of 2 and describes safety guidelines for academic chemistry laboratories to prevent accidents for college and university students. Contents include: (1) "Your Responsibility for Accident Prevention"; (2) "Guide to Chemical Hazards"; (3) "Recommended Laboratory Techniques"; and (4) "Safety Equipment and Emergency…

SURVEYS OF ORGANIZATIONAL CULTURE AND SAFETY CULTURE IN NUCLEAR POWER

International Nuclear Information System (INIS)

BROWN, B.S.

2000-01-01

The results of a survey of organizational culture at a nuclear power plant are summarized and compared with those of a similar survey which has been described in the literature on high-reliability organizations. A general-purpose cultural inventory showed a profile of organizational style similar to that reported in the literature; the factor structure for the styles was also similar to that of the plant previously described. A specialized scale designed to measure safety culture did not distinguish among groups within the organization that would be expected to differ

The 8th questionnaire survey report of safety control in nuclear medicine

International Nuclear Information System (INIS)

2008-01-01

A questionnaire survey on safety of nuclear medicine studies was conducted under the subcommittee for radionuclide imaging and nuclear medicine technology of Japan Radioisotope Association to promote patient safety. Questionnaires were sent to 1300 hospitals and 21 clinical laboratories in Japan with 1034 facilities responded (78.3%). Sixty percents of the workers in the facilities were nuclear medicine technologists. Medical doctors comprised 20% of the workers, but 32% in the university hospitals. The number of laboratory technologists decreased in all categories of the facilities. Composite PET/CT scanners increased sharply, whereas 2-detector and 3-detector imaging systems decreased. Regular maintenance was performed in approximately 80% of the SPECT imaging systems, while the single head imaging systems were maintained less frequently. Filmless systems were employed in 25.3% of all of the facilities responded, with the higher rate in the university hospitals. The number of accidents and incidents in the facilities decreased. Falls on floor and fall from an examination bed were reported. The nuclear medicine technologists were concerned about safety mechanism of imaging systems, and dimension and height of examination beds. They also wanted prompt supply of safety information and easy interconnectivity among different data of various vendors' systems. The results of this survey may be a valuable source of information on safety of nuclear medicine procedures. (author)

Patient safety education at Japanese medical schools: results of a nationwide survey.

Science.gov (United States)

Maeda, Shoichi; Kamishiraki, Etsuko; Starkey, Jay

2012-05-10

Patient safety education, including error prevention strategies and management of adverse events, has become a topic of worldwide concern. The importance of the patient safety is also recognized in Japan following two serious medical accidents in 1999. Furthermore, educational curriculum guideline revisions in 2008 by relevant the Ministry of Education includes patient safety as part of the core medical curriculum. However, little is known about the patient safety education in Japanese medical schools partly because a comprehensive study has not yet been conducted in this field. Therefore, we have conducted a nationwide survey in order to clarify the current status of patient safety education at medical schools in Japan. Response rate was 60.0% (n = 48/80). Ninety-eight-percent of respondents (n = 47/48) reported integration of patient safety education into their curricula. Thirty-nine percent reported devoting less than five hours to the topic. All schools that teach patient safety reported use of lecture based teaching methods while few used alternative methods, such as role-playing or in-hospital training. Topics related to medical error theory and legal ramifications of error are widely taught while practical topics related to error analysis such as root cause analysis are less often covered. Based on responses to our survey, most Japanese medical schools have incorporated the topic of patient safety into their curricula. However, the number of hours devoted to the patient safety education is far from the sufficient level with forty percent of medical schools that devote five hours or less to it. In addition, most medical schools employ only the lecture based learning, lacking diversity in teaching methods. Although most medical schools cover basic error theory, error analysis is taught at fewer schools. We still need to make improvements to our medical safety curricula. We believe that this study has the implications for the rest of the world as a

Patient safety education at Japanese medical schools: results of a nationwide survey

Directory of Open Access Journals (Sweden)

Maeda Shoichi

2012-05-01

Full Text Available Abstract Background Patient safety education, including error prevention strategies and management of adverse events, has become a topic of worldwide concern. The importance of the patient safety is also recognized in Japan following two serious medical accidents in 1999. Furthermore, educational curriculum guideline revisions in 2008 by relevant the Ministry of Education includes patient safety as part of the core medical curriculum. However, little is known about the patient safety education in Japanese medical schools partly because a comprehensive study has not yet been conducted in this field. Therefore, we have conducted a nationwide survey in order to clarify the current status of patient safety education at medical schools in Japan. Results Response rate was 60.0% (n = 48/80. Ninety-eight-percent of respondents (n = 47/48 reported integration of patient safety education into their curricula. Thirty-nine percent reported devoting less than five hours to the topic. All schools that teach patient safety reported use of lecture based teaching methods while few used alternative methods, such as role-playing or in-hospital training. Topics related to medical error theory and legal ramifications of error are widely taught while practical topics related to error analysis such as root cause analysis are less often covered. Conclusions Based on responses to our survey, most Japanese medical schools have incorporated the topic of patient safety into their curricula. However, the number of hours devoted to the patient safety education is far from the sufficient level with forty percent of medical schools that devote five hours or less to it. In addition, most medical schools employ only the lecture based learning, lacking diversity in teaching methods. Although most medical schools cover basic error theory, error analysis is taught at fewer schools. We still need to make improvements to our medical safety curricula. We believe that this

Inventory of Federal energy-related environment and safety research for FY 1977. Volume II. Project listings

Energy Technology Data Exchange (ETDEWEB)

1978-07-01

This volume contains Biomedical and Environmental Research, Environmental Control Technology Research, and Operational and Environmental Safety Research project listings. The projects are ordered numerically by log number.

Site Environmental Report for 2006. Volume I, Environment, Health, and Safety Division

Energy Technology Data Exchange (ETDEWEB)

None

2007-09-30

Each year, Ernest Orlando Lawrence Berkeley National Laboratory prepares an integrated report on its environmental programs to satisfy the requirements of United States Department of Energy Order 231.1A, Environment, Safety, and Health Reporting.1 The Site Environmental Report for 2006 summarizes Berkeley Lab’s environmental management performance, presents environmental monitoring results, and describes significant programs for calendar year 2006. (Throughout this report, Ernest Orlando Lawrence Berkeley National Laboratory is referred to as “Berkeley Lab,” “the Laboratory,” “Lawrence Berkeley National Laboratory,” and “LBNL.”) The report is separated into two volumes. Volume I is organized into an executive summary followed by six chapters that contain an overview of the Laboratory, a discussion of the Laboratory’s environmental management system, the status of environmental programs, and summarized results from surveillance and monitoring activities. Volume II contains individual data results from surveillance and monitoring activities.

Survey of the state of the German safety study

International Nuclear Information System (INIS)

Heuser, F.W.; Kotthoff, K.

1977-01-01

In spring 1976 the Federal Ministry of Research and Technology has ordered a safety study to assess the risk for a nuclear power plant with a PWR. Giving first a survey on the main subtasks of the study the present state of work and some first results are discussed. Assuming a failure of safety systems a core melt event and a subsequent failure of the containment could occur. Corresponding accident sequences are discussed in some detail. Related hereto the results of some calculations for fission product release with respect to different containment failure modes are given. According to the results obtained so far the consequences of a core melt event can essentially be restricted by the retention function of the containment. (orig.) [de

Applying the results of probablistic safety analysis of nuclear power plants: a survey of experience

International Nuclear Information System (INIS)

Andrews, W.B.; Herttrich, M.; Koeberlein, K.; Schwager.

1985-01-01

To date, discussions of the many different types of potential applications of PRA/PSA results and insights to safety-decision-making have been mainly theoretical. Various safety goals have been proposed as decision criteria. However, the discussion on the role of PRA/PSA and Safety Goals in safety-decision-making, especially in licensing, is controversial. A Working Group of the OECD Nuclear Energy Agency is completing a compilation and evaluation of real examples of past and present practical experience with the application of probabilistic methods in reactor safety decision-making, with the idea of developing a common understanding in this area. More than fifty different cases where PRA has influenced decision-making have been surveyed. These include, for example, regulatory changes, fixing of licensing requirements, plant specific modifications of design of operation, prioritization of safety issues and emergency planning. This feedback of experience - both positive and negative - with PRA/PSA applications is considered to provide guidance on how probabilistic approaches can be introduced into current safety practices, and on desirable future developments in probabilistic methods and specific PSA/PRA studies. Generic insights from the survey are given

The comparison of road safety survey answers between web-panel and face-to-face; Dutch results of SARTRE-4 survey.

Science.gov (United States)

Goldenbeld, C; de Craen, S

2013-09-01

In the Netherlands, a comparison of an online and a face-to-face sample of car drivers was made to study differences on a number of selected questions from the SARTRE-4 road safety survey. Contrary to expectations, there was no indication that online respondents were more likely to come from higher educated or more privileged social groups. Confirming earlier research, the results indicated that online respondents were less inclined to give socially desirable answers and were less inclined to use more extreme ratings in their opinions about measures. Contrary to expectations, face-to-face respondents did not tend to give more positive answers in judgment of road safety measures. Weighting to make samples comparable on gender, age, and education had almost no effect on outcomes. The implications for a transition from face-to-face survey to online panel method are discussed. Copyright © 2013 National Safety Council and Elsevier Ltd. All rights reserved.

Measuring safety culture: Application of the Hospital Survey on Patient Safety Culture to radiation therapy departments worldwide.

Science.gov (United States)

Leonard, Sarah; O'Donovan, Anita

Minimizing errors and improving patient safety has gained prominence worldwide in high-risk disciplines such as radiation therapy. Patient safety culture has been identified as an important factor in reducing the incidence of adverse events and improving patient safety in the health care setting. The aim of distributing the Hospital Survey on Patient Safety Culture (HSPSC) to radiation therapy departments worldwide was to assess the current status of safety culture, identify areas for improvement and areas that excel, examine factors that influence safety culture, and raise staff awareness. The safety culture in radiation therapy departments worldwide was evaluated by distributing the HSPSC. A total of 266 participants were recruited from radiation therapy departments and included radiation oncologists, radiation therapists, physicists, and dosimetrists. The positive percent scores for the 12 dimensions of the HSPSC varied from 50% to 79%. The highest composite score among the 12 dimensions was teamwork within units; the lowest composite score was handoffs and transitions. The results indicated that health care professionals in radiation therapy departments felt positively toward patient safety. The HSPSC was successfully applied to radiation therapy departments and provided valuable insight into areas of potential improvement such as teamwork across units, staffing, and handoffs and transitions. Managers and policy makers in radiation therapy may use this assessment tool for focused improvement efforts toward patient safety culture. Copyright © 2017 American Society for Radiation Oncology. Published by Elsevier Inc. All rights reserved.

Between demarcation and discretion: The medical-administrative boundary as a locus of safety in high-volume organisational routines.

Science.gov (United States)

Grant, Suzanne; Guthrie, Bruce

2018-04-01

Patient safety is an increasing concern for health systems internationally. The majority of administrative work in UK general practice takes place in the context of organisational routines such as repeat prescribing and test results handling, where high workloads and increased clinician dependency on administrative staff have been identified as an emerging safety issue. Despite this trend, most research to date has focused on the redistribution of the clinical workload between doctors, nurses and allied health professionals within individual care settings. Drawing on Strauss's negotiated order perspective, we examine ethnographically the achievement of safety across the medical-administrative boundary in key high-volume routines in UK general practice. We focus on two main issues. First, GPs engaged in strategies of demarcation by defining receptionist work as routine, unspecialised and dependent upon GP clinical knowledge and oversight as the safety net to deal with complexity and risk. Receptionists consented to this 'social closure' when describing their role, thus reinforcing the underlying inter-occupational relationship of medical domination. Second, in everyday practice, GPs and receptionists engaged in informal boundary-blurring to safely accommodate the complexity of everyday high-volume routine work. This comprised additional informal discretionary spaces for receptionist decision-making and action that went beyond the routine safety work formally assigned to them. New restratified intra-occupational hierarchies were also being created between receptionists based on the complexity of the safety work that they were authorised to do at practice level, with specialised roles constituting a new form of administrative 'professional project'. The article advances negotiated order theory by providing an in-depth examination of the ways in which medical-administrative boundary-making and boundary-blurring constitute distinct modes of safety in high-volume

Development and applicability of Hospital Survey on Patient Safety Culture (HSOPS) in Japan.

Science.gov (United States)

Ito, Shinya; Seto, Kanako; Kigawa, Mika; Fujita, Shigeru; Hasegawa, Toshihiko; Hasegawa, Tomonori

2011-02-07

Patient safety culture at healthcare organizations plays an important role in guaranteeing, improving and promoting overall patient safety. Although several conceptual frameworks have been proposed in the past, no standard measurement tool has yet been developed for Japan. In order to examine possibilities to introduce the Hospital Survey on Patient Safety Culture (HSOPS) in Japan, the authors of this study translated the HSOPS into Japanese, and evaluated its factor structure, internal consistency, and construct validity. Healthcare workers (n = 6,395) from 13 acute care general hospitals in Japan participated in this survey. Confirmatory factor analysis indicated that the Japanese HSOPS' 12-factor model was selected as the most pertinent, and showed a sufficiently high standard partial regression coefficient. The internal reliability of the subscale scores was 0.46-0.88. The construct validity of each safety culture sub-dimension was confirmed by polychoric correlation, and by an ordered probit analysis. The results of the present study indicate that the factor structures of the Japanese and the American HSOPS are almost identical, and that the Japanese HSOPS has acceptable levels of internal reliability and construct validity. This shows that the HSOPS can be introduced in Japan.

Older Driver Safety: A Survey of Psychologists' Attitudes, Knowledge, and Practices.

Science.gov (United States)

Love, Janet; Tuokko, Holly

2016-09-01

Using an online survey, we examined the knowledge, attitudes, and practices with respect to older driver safety concerns of clinical psychologists from across Canada who self-identified as working with at least some drivers over 60 years of age. Eighty-four psychologists completed the survey, and many were aware of the issues relevant to older driver safety, although only about half reported that assessing fitness to drive was an important issue in their practice. The majority (75%) reported that they would benefit from education concerning evaluation of fitness to drive. The primary recommendation emerging from this investigation is to increase efforts to inform and educate psychologists about driving-related assessment and regulatory issues in general, and specifically with respect to older adults. As the population ages, it is of growing importance for all health care providers to understand the influence of mental health conditions-including cognitive impairment and dementia-on driving skills.

Patient safety: Safety culture and patient safety ethics

DEFF Research Database (Denmark)

Madsen, Marlene Dyrløv

2006-01-01

,demonstrating significant, consistent and sometimes large differences in terms of safety culture factors across the units participating in the survey. Paper 5 is the results of a study of the relation between safety culture, occupational health andpatient safety using a safety culture questionnaire survey......Patient safety - the prevention of medical error and adverse events - and the initiative of developing safety cultures to assure patients from harm have become one of the central concerns in quality improvement in healthcare both nationally andinternationally. This subject raises numerous...... challenging issues of systemic, organisational, cultural and ethical relevance, which this dissertation seeks to address through the application of different disciplinary approaches. The main focus of researchis safety culture; through empirical and theoretical studies to comprehend the phenomenon, address...

Patient Safety Culture Survey in Pediatric Complex Care Settings: A Factor Analysis.

Science.gov (United States)

Hessels, Amanda J; Murray, Meghan; Cohen, Bevin; Larson, Elaine L

2017-04-19

Children with complex medical needs are increasing in number and demanding the services of pediatric long-term care facilities (pLTC), which require a focus on patient safety culture (PSC). However, no tool to measure PSC has been tested in this unique hybrid acute care-residential setting. The objective of this study was to evaluate the psychometric properties of the Nursing Home Survey on Patient Safety Culture tool slightly modified for use in the pLTC setting. Factor analyses were performed on data collected from 239 staff at 3 pLTC in 2012. Items were screened by principal axis factoring, and the original structure was tested using confirmatory factor analysis. Exploratory factor analysis was conducted to identify the best model fit for the pLTC data, and factor reliability was assessed by Cronbach alpha. The extracted, rotated factor solution suggested items in 4 (staffing, nonpunitive response to mistakes, communication openness, and organizational learning) of the original 12 dimensions may not be a good fit for this population. Nevertheless, in the pLTC setting, both the original and the modified factor solutions demonstrated similar reliabilities to the published consistencies of the survey when tested in adult nursing homes and the items factored nearly identically as theorized. This study demonstrates that the Nursing Home Survey on Patient Safety Culture with minimal modification may be an appropriate instrument to measure PSC in pLTC settings. Additional psychometric testing is recommended to further validate the use of this instrument in this setting, including examining the relationship to safety outcomes. Increased use will yield data for benchmarking purposes across these specialized settings to inform frontline workers and organizational leaders of areas of strength and opportunity for improvement.

Probabilistic safety analysis procedures guide. Sections 1-7 and appendices. Volume 1, Revision 1

International Nuclear Information System (INIS)

Bari, R.A.; Buslik, A.J.; Cho, N.Z.

1985-08-01

A procedures guide for the performance of probabilistic safety assessment has been prepared for interim use in the Nuclear Regulatory Commission programs. It will be revised as comments are received, and as experience is gained from its use. 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 issues affecting reactor safety. This first volume of the guide describes the determination of the probability (per year) of core damage resulting from accident initiators internal to the plant (i.e., intrinsic to plant operation) and from loss of off-site electric power. The scope includes human reliability analysis, a determination of the importance of various core damage accident sequences, and an explicit treatment and display of uncertainties for key accident sequences. The second volume deals with the treatment of the so-called external events including seismic disturbances, fires, floods, etc. Ultimately, the guide will be augmented to include the plant-specific analysis of in-plant processes (i.e., containment performance). This guide provides the structure of a probabilistic safety study to be performed, and indicates what products of the study are valuable for regulatory decision making. For internal events, 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. For external events, more explicit guidance is given

Psychometric properties of the Hospital Survey on Patient Safety Culture for hospital management (HSOPS_M

Directory of Open Access Journals (Sweden)

Pfeiffer Yvonne

2011-07-01

Full Text Available Abstract Background From a management perspective, it is necessary to examine how a hospital's top management assess the patient safety culture in their organisation. This study examines whether the Hospital Survey on Patient Safety Culture for hospital management (HSOPS_M has the same psychometric properties as the HSOPS for hospital employees does. Methods In 2008, a questionnaire survey including the HSOPS_M was conducted with 1,224 medical directors from German hospitals. When assessing the psychometric properties, we performed a confirmatory factor analysis (CFA. Additionally, we proved construct validity and internal consistency. Results A total of 551 medical directors returned the questionnaire. The results of the CFA suggested a satisfactory global data fit. The indices of local fit indicated a good, but not satisfactory convergent validity. Analyses of construct validity indicated that not all safety culture dimensions were readily distinguishable. However, Cronbach's alpha indicated that the dimensions had an acceptable level of reliability. Conclusion The analyses of the psychometric properties of the HSOPS_M resulted in reasonably good levels of property values. Although the set of dimensions within the HSOPS_M needs further scale refinement, the questionnaire covers a broad range of sub-dimensions and supplies important information on safety culture. The HSOPS_M, therefore, is eligible to measure safety culture from the hospital management's points of view and could be used in nationwide hospital surveys to make inter-organisational comparisons.

Airborne gamma-ray spectrometer and magnetometer survey: Lund quadrangle, Ely quadrangle, Nevada. Volume I. Final report

International Nuclear Information System (INIS)

1980-01-01

An airborne combined radiometric and magnetic survey was performed for the Department of Energy (DOE) over the area covered by the Ely and Lund 1:250,000 National Topographic Map Series (NTMS quadrangle maps). The survey was part of DOE's National Uranium Resource Evaluation (NURE) Aerial Radiometric Reconnaissance program. Data were collected by a helicopter equipped with a gamma-ray spectrometer having a large crystal volume, and a high sensitivity proton precession magnetometer. The radiometric system was calibrated at the Walker Field Calibration pads and the Lake Mead Dynamic Test range. Data quality was ensured during the survey by daily test flights and equipment checks. Radiometric data were corrected for live time, aircraft and equipment background, cosmic background, atmospheric radon, Compton scatter, and altitude dependence. The corrected data were statistically evaluated, plotted, and contoured to produce anomaly maps based on the radiometric response of individual geological units. The maps were interpreted and an anomaly interpretation map produced. Volume I contains a description of the systems used in the survey, a discussion of the calibration of the systems, the data processing procedures, the data display format, the interpretation rationale, and interpretation methodology. Volume II contains the data displays for a quadrangle and the interpretation results

The 1985 ARI Survey of Army Recruits: Tabular Description of NPS (active) Army Accessions. Volume 2

Science.gov (United States)

1987-04-01

ACTIVE) ARMY ACCESSIONS, VOLUME 2 INTRODUCTION The purpose of this document and a companion volume, The 1985 Survey of Armv Recruits; Tabular...supsnssrket. Stock shelves in a eupenserket Check out goods in a auperserkst 143. 145. Lssrn *out being a chef . Lasrn about being an auto «echenic

Perceptions of clinical safety climate of the multicultural nursing workforce in Saudi Arabia: a cross-sectional survey.

Science.gov (United States)

Almutairi, Adel F; Gardner, Glenn; McCarthy, Alexandra

2013-01-01

The purpose of this study is to explore the safety climate perceptions of the multicultural nursing workforce, and to investigate the influence of diversity of the multicultural nursing workforce on clinical safety in a large tertiary hospital in Saudi Arabia. Working in a multicultural environment is challenging. Each culture has its own unique characteristics and dimensions that shape the language, lifestyle, beliefs, values, customs, traditions, and patterns of behaviour, which expatriate nurses must come to terms with. However, cultural diversity in the health care environment can potentially affect the quality of care and patient safety. A mixed-method case study (survey, interview and document analysis) was employed. A primary study phase entailed the administration of the Safety Climate Survey (SCS). A population sampling strategy was used and 319 nurses participated, yielding a 76.8% response rate. Descriptive and inferential statistics (Kruskal-Wallis test) were used to analyse survey data. The data revealed the nurses' perceptions of the clinical safety climate in this multicultural environment was unsafe, with a mean score of 3.9 out of 5. No significant difference was found between the age groups, years of nursing experience and their perceptions of the safety climate in this context. A significant difference was observed between the national background categories of nurses and perceptions of safety climate. Cultural diversity within the nursing workforce could have a significant influence on perceptions of clinical safety. These findings have the potential to inform policy and practice related to cultural diversity in Saudi Arabia.

Biennial Survey of Education, 1916-18. Volume II. Bulletin, 1919, No. 89

Science.gov (United States)

Bureau of Education, Department of the Interior, 1921

1921-01-01

Volume II of the Biennial Survey of Education, 1916-1918 includes the following chapters: (1) Education in Great Britain and Ireland (I. L. Kandel); (2) Education in parts of the British Empire: Educational Developments in the Dominion of Canada (Walter A. Montgomery), Public School System of Jamaica (Charles A. Asbury), Recent Progress of…

Twenty-third water reactor safety information meeting: Volume 1, plenary session, high burnup fuel behavior, thermal hydraulic research. Proceedings

Energy Technology Data Exchange (ETDEWEB)

Monteleone, S. [comp.] [Brookhaven National Lab., Upton, NY (United States)

1996-03-01

This three-volume report contains papers presented at the Twenty- Third Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, October 23-25, 1995. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Italy, Japan, Norway, Russia, Sweden, and Switzerland. This document, Volume 1, present topics on High Burnup Fuel Behavior, Thermal Hydraulic Research, and Plenary Session topics. Individual papers have been cataloged separately.

Twenty-third water reactor safety information meeting: Volume 1, plenary session, high burnup fuel behavior, thermal hydraulic research. Proceedings

International Nuclear Information System (INIS)

Monteleone, S.

1996-03-01

This three-volume report contains papers presented at the Twenty- Third Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, October 23-25, 1995. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Italy, Japan, Norway, Russia, Sweden, and Switzerland. This document, Volume 1, present topics on High Burnup Fuel Behavior, Thermal Hydraulic Research, and Plenary Session topics. Individual papers have been cataloged separately

Development of a multilevel health and safety climate survey tool within a mining setting.

Science.gov (United States)

Parker, Anthony W; Tones, Megan J; Ritchie, Gabrielle E

2017-09-01

This study aimed to design, implement and evaluate the reliability and validity of a multifactorial and multilevel health and safety climate survey (HSCS) tool with utility in the Australian mining setting. An 84-item questionnaire was developed and pilot tested on a sample of 302 Australian miners across two open cut sites. A 67-item, 10 factor solution was obtained via exploratory factor analysis (EFA) representing prioritization and attitudes to health and safety across multiple domains and organizational levels. Each factor demonstrated a high level of internal reliability, and a series of ANOVAs determined a high level of consistency in responses across the workforce, and generally irrespective of age, experience or job category. Participants tended to hold favorable views of occupational health and safety (OH&S) climate at the management, supervisor, workgroup and individual level. The survey tool demonstrated reliability and validity for use within an open cut Australian mining setting and supports a multilevel, industry specific approach to OH&S climate. Findings suggested a need for mining companies to maintain high OH&S standards to minimize risks to employee health and safety. Future research is required to determine the ability of this measure to predict OH&S outcomes and its utility within other mine settings. As this tool integrates health and safety, it may have benefits for assessment, monitoring and evaluation in the industry, and improving the understanding of how health and safety climate interact at multiple levels to influence OH&S outcomes. Copyright © 2017 National Safety Council and Elsevier Ltd. All rights reserved.

TIBER II/ETR final design report: Volume 3, 5.0 Radiation safety and environment; 6.0 Physics and technology R and D needs

International Nuclear Information System (INIS)

Lee, J.D.

1987-09-01

This paper discusses the design of the TIBER II Tokamak. This particular volume discusses: safety and environmental requirements and design targets; accident analyses; personnel safety and maintenance exposure; effluent control; waste management and decommissioning; safety considerations in building design; and safety and environmental conclusions and recommendations

Morphological pyramids in multiresolution MIP rendering of large volume data : Survey and new results

NARCIS (Netherlands)

Roerdink, J.B.T.M.

We survey and extend nonlinear signal decompositions based on morphological pyramids, and their application to multiresolution maximum intensity projection (MIP) volume rendering with progressive refinement and perfect reconstruction. The structure of the resulting multiresolution rendering

Survey of bayesian belif nets for quantitative reliability assessment of safety critical software used in nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Eom, H.S.; Sung, T.Y.; Jeong, H.S.; Park, J.H.; Kang, H.G.; Lee, K

2001-03-01

As part of the Probabilistic Safety Assessment of safety grade digital systems used in Nuclear Power plants research, measures and methodologies applicable to quantitative reliability assessment of safety critical software were surveyed. Among the techniques proposed in the literature we selected those which are in use widely and investigated their limitations in quantitative software reliability assessment. One promising methodology from the survey is Bayesian Belief Nets (BBN) which has a formalism and can combine various disparate evidences relevant to reliability into final decision under uncertainty. Thus we analyzed BBN and its application cases in digital systems assessment area and finally studied the possibility of its application to the quantitative reliability assessment of safety critical software.

Survey of bayesian belif nets for quantitative reliability assessment of safety critical software used in nuclear power plants

International Nuclear Information System (INIS)

Eom, H. S.; Sung, T. Y.; Jeong, H. S.; Park, J. H.; Kang, H. G.; Lee, K.

2001-03-01

As part of the Probabilistic Safety Assessment of safety grade digital systems used in Nuclear Power plants research, measures and methodologies applicable to quantitative reliability assessment of safety critical software were surveyed. Among the techniques proposed in the literature we selected those which are in use widely and investigated their limitations in quantitative software reliability assessment. One promising methodology from the survey is Bayesian Belief Nets (BBN) which has a formalism and can combine various disparate evidences relevant to reliability into final decision under uncertainty. Thus we analyzed BBN and its application cases in digital systems assessment area and finally studied the possibility of its application to the quantitative reliability assessment of safety critical software

Inventory of Federal energy-related environment and safety research for FY 1979. Volume 1. Executive summary

International Nuclear Information System (INIS)

1980-12-01

The FY 1979 Federal Inventory contains information on 3506 federally funded energy-related environmental and safety research projects. The Inventory is published in two volumes: Volume I, an executive summary and overview of the data and Volume II, project listings, summaries, and indexes. Research and development (R and D) categories were reorganized into three main areas; environmental and safety control technology, technology impacts overview and assessments, and biological and environmental R and D and assessments. Federal offices submitting project data were: Council on Environmental Quality; Department of Agriculture; Department of Commerce; Department of Defense; Department of Energy; Department of Health, Education, and Welfare; Department of Housing and Urban Development; Department of the Interior; Department of Transportation; Environmental Protection Agency; National Aeronautics and Space Administration; Nuclear Regulatory Commission; National Science Foundation; Office of Technology Assessment; and Tennessee Valley Authority. The inventory also breaks out research sponsored by various federal agencies and the amount of funding provided by each in various research categories. The format and index system allows efficient access to information compiled. Users are able to identify projects by log agency, performing organization, principal investigator and subject

Survey on the use of configuration risk and safety management tools at nuclear power plants. Final report

International Nuclear Information System (INIS)

Fleming, K.N.; Read, J.W.; Dagan, W.J.; Bidwell, D.A.

1998-09-01

In order to provide input to Electricite de France's (EDF) evaluation of the use of configuration safety and risk management tools in the French plants and to collect information to guide the EPRI efforts to provide useful tools for the EPRI member utilities and international partners, a joint effort to survey US and selected non-US nuclear power stations was conducted. This survey examined the use of various approaches, techniques, and software tools that are being used to evaluate the safety and risk aspects of plant configuration changes and configuration changes during plant outages as well as during power operation. The use of these tools has increased in recent years as a result of efforts to optimize plant maintenance programs, improve plant safety, and increase plant reliability and availability. This report provides the results of the survey of 37 organizations covering 54 nuclear plant sites and 97 reactor units

Results of a survey on accident and safety analysis codes, benchmarks, verification and validation methods

International Nuclear Information System (INIS)

Lee, A.G.; Wilkin, G.B.

1995-01-01

This report is a compilation of the information submitted by AECL, CIAE, JAERI, ORNL and Siemens in response to a need identified at the 'Workshop on R and D Needs' at the IGORR-3 meeting. The survey compiled information on the national standards applied to the Safety Quality Assurance (SQA) programs undertaken by the participants. Information was assembled for the computer codes and nuclear data libraries used in accident and safety analyses for research reactors and the methods used to verify and validate the codes and libraries. Although the survey was not comprehensive, it provides a basis for exchanging information of common interest to the research reactor community

Technology, safety and costs of decommissioning a reference small mixed oxide fuel fabrication plant. Volume 2. Appendices

Energy Technology Data Exchange (ETDEWEB)

Jenkins, C. E.; Murphy, E. S.; Schneider, K. J.

1979-01-01

Volume 2 contains appendixes on small MOX fuel fabrication facility description, site description, residual radionuclide inventory estimates, decommissioning, financing, radiation dose methodology, general considerations, packaging and shipping of radioactive materials, cost assessment, and safety (JRD)

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

Science.gov (United States)

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

1999-07-01

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

Radiation safety considerations and compliance within equine veterinary clinics: Results of an Australian survey

International Nuclear Information System (INIS)

Surjan, Y.; Ostwald, P.; Milross, C.; Warren-Forward, H.

2015-01-01

Objective: To examine current knowledge and the level of compliance of radiation safety principles in equine veterinary clinics within Australia. Method: Surveys were sent to equine veterinary surgeons working in Australia. The survey was delivered both online and in hardcopy format; it comprised 49 questions, 15 of these directly related to radiation safety. The participants were asked about their current and previous use of radiation-producing equipment. Information regarding their level of knowledge and application of radiation safety principles and practice standards was collected and analysed. Results: The use of radiation-producing equipment was evident in 94% of responding clinics (a combination of X-ray, CT and/or Nuclear Medicine Cameras). Of those with radiation-producing equipment, 94% indicated that they hold a radiation licence, 78% had never completed a certified radiation safety course and 19% of participants did not use a personal radiation monitor. In 14% of cases, radiation safety manuals or protocols were not available within clinics. Conclusions: The study has shown that knowledge and application of guidelines as provided by the Code of Practice for Radiation Protection in Veterinary Medicine (2009) is poorly adhered to. The importance of compliance with regulatory requirements is pivotal in minimising occupational exposure to ionising radiation in veterinary medicine, thus there is a need for increased education and training in the area. - Highlights: • Application of the Code of Practice for Veterinary Medicine is poorly adhered to. • Majority of veterinary clinics had not completed certified radiation safety course. • One-fifth of participants did not use personal radiation monitoring. • Increased education and training in area of radiation safety and protection required to generate compliance in clinics

Undetected latent failures of safety-related systems. Preliminary survey of events in nuclear power plants 1980-1997

International Nuclear Information System (INIS)

Lydell, B.

1998-03-01

This report summarizes results and insights from a preliminary survey of events involving undetected, latent failures of safety-related systems. The survey was limited to events where mispositioned equipment (e.g., valves, switches) remained undetected, thus rendering standby equipment or systems unavailable for short or long time periods. Typically, these events were symptoms of underlying latent errors (e.g., design errors, procedure errors, unanalyzed safety conditions) and programmatic errors. The preliminary survey identified well over 300 events. Of these, 95 events are documented in this report. Events involving mispositioned equipment are commonplace. Most events are discovered soon after occurrence, however. But as evidenced by the survey results, some events remained undetected beyond several shift changes. The recommendations developed by the survey emphasize the importance of applying modern root cause analysis techniques to the event analysis to ensure that the causes and implications of occurred events are fully understood

Report on the Survey of the Design Review of New Reactor Applications. Volume 4: Reactor Coolant and Associated Systems

International Nuclear Information System (INIS)

Downey, Steven; Monninger, John; Nevalainen, Janne; Joyer, Philippe; Koley, Jaharlal; Kawamura, Tomonori; Chung, Yeon-Ki; Haluska, Ladislav; Persic, Andreja; Reierson, Craig; Monninger, John; Choi, Young-Joon; )

2017-01-01

At the tenth meeting of the Committee on Nuclear Regulatory Activities (CNRA) Working Group on the Regulation of New Reactors (WGRNR) in March 2013, the Working Group agreed to present the responses to the Second Phase, or Design Phase, of the licensing process survey as a multi-volume text. As such, each report will focus on one of the eleven general technical categories covered in the survey. The general technical categories were selected to conform to the topics covered in the International Atomic Energy Agency (IAEA) Safety Guide GS-G-4.1. This report provides a discussion of the survey responses related to the Reactor Coolant and Associated Systems category. The Reactor Coolant and Associated Systems category includes the following technical topics: overpressure protection, reactor coolant pressure boundary, reactor vessel, and design of the reactor coolant system. For each technical topic, the member countries described the information provided by the applicant, the scope and level of detail of the technical review, the technical basis for granting regulatory authorisation, the skill sets required and the level of effort needed to perform the review. Based on a comparison of the information provided by the member countries in response to the survey, the following observations were made: - Although the description of the information provided by the applicant differs in scope and level of detail among the member countries that provided responses, there are similarities in the information that is required. - All of the technical topics covered in the survey are reviewed in some manner by all of the regulatory authorities that provided responses. - It is common to consider operating experience and lessons learnt from the current fleet during the review process. - The most commonly and consistently identified technical expertise needed to perform design reviews related to this category are mechanical engineering and materials engineering. The complete survey

Space Biology and Medicine. Volume 4; Health, Performance, and Safety of Space Crews

Science.gov (United States)

Dietlein, Lawrence F. (Editor); Pestov, Igor D. (Editor)

2004-01-01

Volume IV is devoted to examining the medical and associated organizational measures used to maintain the health of space crews and to support their performance before, during, and after space flight. These measures, collectively known as the medical flight support system, are important contributors to the safety and success of space flight. The contributions of space hardware and the spacecraft environment to flight safety and mission success are covered in previous volumes of the Space Biology and Medicine series. In Volume IV, we address means of improving the reliability of people who are required to function in the unfamiliar environment of space flight as well as the importance of those who support the crew. Please note that the extensive collaboration between Russian and American teams for this volume of work resulted in a timeframe of publication longer than originally anticipated. Therefore, new research or insights may have emerged since the authors composed their chapters and references. This volume includes a list of authors' names and addresses should readers seek specifics on new information. At least three groups of factors act to perturb human physiological homeostasis during space flight. All have significant influence on health, psychological, and emotional status, tolerance, and work capacity. The first and most important of these factors is weightlessness, the most specific and radical change in the ambient environment; it causes a variety of functional and structural changes in human physiology. The second group of factors precludes the constraints associated with living in the sealed, confined environment of spacecraft. Although these factors are not unique to space flight, the limitations they entail in terms of an uncomfortable environment can diminish the well-being and performance of crewmembers in space. The third group of factors includes the occupational and social factors associated with the difficult, critical nature of the

Abbreviations [Annex to The Fukushima Daiichi Accident, Technical Volume 5/5

International Nuclear Information System (INIS)

2015-01-01

This annex is a list of abbreviations used in the publication The Fukushima Daiichi Accident, Technical Volume 5/5. The list includes the abbreviations for: • General Safety Requirements; • International Commission on Radiological Protection; • Intensive Contamination Survey Area; • International Experts Meeting; • Ministry of Education, Culture, Sports, Science and Technology; • Ministry of the Environment; • Nuclear Damage Compensation and Decommissioning Facilitation Corporation; • Nuclear Emergency Response Headquarters; • nuclear power plant; • Nuclear Safety Commission; • OECD Nuclear Energy Agency; • Special Decontamination Area; • Specific Safety Requirements; • technical cooperation; • Three Mile Island; • United Nations Scientific Committee on the Effects of Atomic Radiation

Site Environmental Report for 2004. Volume 1, Environment, Health, and Safety Division

Energy Technology Data Exchange (ETDEWEB)

None

2005-09-30

Each year, Ernest Orlando Lawrence Berkeley National Laboratory prepares an integrated report on its environmental programs to satisfy the requirements of United States Department of Energy Order 231.1A, Environment, Safety, and Health Reporting.1 The Site Environmental Report for 2004 summarizes Berkeley Lab’s environmental management performance, presents environmental monitoring results, and describes significant programs for calendar year 2004. (Throughout this report, Ernest Orlando Lawrence Berkeley National Laboratory is referred to as “Berkeley Lab,” “the Laboratory,” “Lawrence Berkeley National Laboratory,” and “LBNL.”) The report is separated into two volumes. Volume I contains an overview of the Laboratory, the status of environmental programs, and summarized results from surveillance and monitoring activities. Volume II contains individual data results from these activities. This year, the Site Environmental Report was distributed by releasing it on the Web from the Berkeley Lab Environmental Services Group (ESG) home page, which is located at http://www.lbl.gov/ehs/esg/. Many of the documents cited in this report also are accessible from the ESG Web page. CD and printed copies of this Site Environmental Report are available upon request.

DOE standard: Integration of environment, safety, and health into facility disposition activities. Volume 2: Appendices

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-05-01

This volume contains the appendices that provide additional environment, safety, and health (ES and H) information to complement Volume 1 of this Standard. Appendix A provides a set of candidate DOE ES and H directives and external regulations, organized by hazard types that may be used to identify potentially applicable directives to a specific facility disposition activity. Appendix B offers examples and lessons learned that illustrate implementation of ES and H approaches discussed in Section 3 of Volume 1. Appendix C contains ISMS performance expectations to guide a project team in developing and implementing an effective ISMS and in developing specific performance criteria for use in facility disposition. Appendix D provides guidance for identifying potential Applicable or Relevant and Appropriate Requirements (ARARs) when decommissioning facilities fall under the Comprehensive Environmental Response, Compensation, Liability Act (CERCLA) process. Appendix E discusses ES and H considerations for dispositioning facilities by privatization. Appendix F is an overview of the WSS process. Appendix G provides a copy of two DOE Office of Nuclear Safety Policy and Standards memoranda that form the bases for some of the guidance discussed within the Standard. Appendix H gives information on available hazard analysis techniques and references. Appendix I provides a supplemental discussion to Sections 3.3.4, Hazard Baseline Documentation, and 3.3.6, Environmental Permits. Appendix J presents a sample readiness evaluation checklist.

DOE standard: Integration of environment, safety, and health into facility disposition activities. Volume 2: Appendices

International Nuclear Information System (INIS)

1998-05-01

This volume contains the appendices that provide additional environment, safety, and health (ES and H) information to complement Volume 1 of this Standard. Appendix A provides a set of candidate DOE ES and H directives and external regulations, organized by hazard types that may be used to identify potentially applicable directives to a specific facility disposition activity. Appendix B offers examples and lessons learned that illustrate implementation of ES and H approaches discussed in Section 3 of Volume 1. Appendix C contains ISMS performance expectations to guide a project team in developing and implementing an effective ISMS and in developing specific performance criteria for use in facility disposition. Appendix D provides guidance for identifying potential Applicable or Relevant and Appropriate Requirements (ARARs) when decommissioning facilities fall under the Comprehensive Environmental Response, Compensation, Liability Act (CERCLA) process. Appendix E discusses ES and H considerations for dispositioning facilities by privatization. Appendix F is an overview of the WSS process. Appendix G provides a copy of two DOE Office of Nuclear Safety Policy and Standards memoranda that form the bases for some of the guidance discussed within the Standard. Appendix H gives information on available hazard analysis techniques and references. Appendix I provides a supplemental discussion to Sections 3.3.4, Hazard Baseline Documentation, and 3.3.6, Environmental Permits. Appendix J presents a sample readiness evaluation checklist

Undetected latent failures of safety-related systems. Preliminary survey of events in nuclear power plants 1980-1997

Energy Technology Data Exchange (ETDEWEB)

Lydell, B. [RSA Technologies, Vista, CA (United States)

1998-03-01

This report summarizes results and insights from a preliminary survey of events involving undetected, latent failures of safety-related systems. The survey was limited to events where mispositioned equipment (e.g., valves, switches) remained undetected, thus rendering standby equipment or systems unavailable for short or long time periods. Typically, these events were symptoms of underlying latent errors (e.g., design errors, procedure errors, unanalyzed safety conditions) and programmatic errors. The preliminary survey identified well over 300 events. Of these, 95 events are documented in this report. Events involving mispositioned equipment are commonplace. Most events are discovered soon after occurrence, however. But as evidenced by the survey results, some events remained undetected beyond several shift changes. The recommendations developed by the survey emphasize the importance of applying modern root cause analysis techniques to the event analysis to ensure that the causes and implications of occurred events are fully understood. 7 refs, 4 tabs, 3 figs. Also available at the SKI Home page: //www.ski.se.

John F. Kennedy Space Center, Safety, Reliability, Maintainability and Quality Assurance, Survey and Audit Program

Science.gov (United States)

1994-01-01

This document is the product of the KSC Survey and Audit Working Group composed of civil service and contractor Safety, Reliability, and Quality Assurance (SR&QA) personnel. The program described herein provides standardized terminology, uniformity of survey and audit operations, and emphasizes process assessments rather than a program based solely on compliance. The program establishes minimum training requirements, adopts an auditor certification methodology, and includes survey and audit metrics for the audited organizations as well as the auditing organization.

Animal-assisted interventions: A national survey of health and safety policies in hospitals, eldercare facilities, and therapy animal organizations.

Science.gov (United States)

Linder, Deborah E; Siebens, Hannah C; Mueller, Megan K; Gibbs, Debra M; Freeman, Lisa M

2017-08-01

Animal-assisted intervention (AAI) programs are increasing in popularity, but it is unknown to what extent therapy animal organizations that provide AAI and the hospitals and eldercare facilities they work with implement effective animal health and safety policies to ensure safety of both animals and humans. Our study objective was to survey hospitals, eldercare facilities, and therapy animal organizations on their AAI policies and procedures. A survey of United States hospitals, eldercare facilities, and therapy animal organizations was administered to assess existing health and safety policies related to AAI programs. Forty-five eldercare facilities, 45 hospitals, and 27 therapy animal organizations were surveyed. Health and safety policies varied widely and potentially compromised human and animal safety. For example, 70% of therapy animal organizations potentially put patients at risk by allowing therapy animals eating raw meat diets to visit facilities. In general, hospitals had stricter requirements than eldercare facilities. This information suggests that there are gaps between the policies of facilities and therapy animal organizations compared with recent guidelines for animal visitation in hospitals. Facilities with AAI programs need to review their policies to address recent AAI guidelines to ensure the safety of animals and humans involved. Copyright © 2017 Association for Professionals in Infection Control and Epidemiology, Inc. Published by Elsevier Inc. All rights reserved.

AGN Populations in Large-volume X-Ray Surveys: Photometric Redshifts and Population Types Found in the Stripe 82X Survey

Science.gov (United States)

Ananna, Tonima Tasnin; Salvato, Mara; LaMassa, Stephanie; Urry, C. Megan; Cappelluti, Nico; Cardamone, Carolin; Civano, Francesca; Farrah, Duncan; Gilfanov, Marat; Glikman, Eilat; Hamilton, Mark; Kirkpatrick, Allison; Lanzuisi, Giorgio; Marchesi, Stefano; Merloni, Andrea; Nandra, Kirpal; Natarajan, Priyamvada; Richards, Gordon T.; Timlin, John

2017-11-01

Multiwavelength surveys covering large sky volumes are necessary to obtain an accurate census of rare objects such as high-luminosity and/or high-redshift active galactic nuclei (AGNs). Stripe 82X is a 31.3 X-ray survey with Chandra and XMM-Newton observations overlapping the legacy Sloan Digital Sky Survey Stripe 82 field, which has a rich investment of multiwavelength coverage from the ultraviolet to the radio. The wide-area nature of this survey presents new challenges for photometric redshifts for AGNs compared to previous work on narrow-deep fields because it probes different populations of objects that need to be identified and represented in the library of templates. Here we present an updated X-ray plus multiwavelength matched catalog, including Spitzer counterparts, and estimated photometric redshifts for 5961 (96% of a total of 6181) X-ray sources that have a normalized median absolute deviation, σnmad=0.06, and an outlier fraction, η = 13.7%. The populations found in this survey and the template libraries used for photometric redshifts provide important guiding principles for upcoming large-area surveys such as eROSITA and 3XMM (in X-ray) and the Large Synoptic Survey Telescope (optical).

Association of Safety Culture with Surgical Site Infection Outcomes.

Science.gov (United States)

Fan, Caleb J; Pawlik, Timothy M; Daniels, Tania; Vernon, Nora; Banks, Katie; Westby, Peggy; Wick, Elizabeth C; Sexton, J Bryan; Makary, Martin A

2016-02-01

Hospital workplace culture may have an impact on surgical outcomes; however, this association has not been established. We designed a study to evaluate the association between safety culture and surgical site infection (SSI). Using the Hospital Survey on Patient Safety Culture and National Healthcare Safety Network definitions, we measured 12 dimensions of safety culture and colon SSI rates, respectively, in the surgical units of Minnesota community hospitals. A Pearson's r correlation was calculated for each of 12 dimensions of surgical unit safety culture and SSI rate and then adjusted for surgical volume and American Society of Anesthesiologists (ASA) classification. Seven hospitals participated in the study, with a mean survey response rate of 43%. The SSI rates ranged from 0% to 30%, and surgical unit safety culture scores ranged from 16 to 92 on a scale of 0 to 100. Ten dimensions of surgical unit safety culture were associated with colon SSI rates: teamwork across units (r = -0.96; 95% CI [-0.76, -0.99]), organizational learning (r = -0.95; 95% CI [-0.71, -0.99]), feedback and communication about error (r = -0.92; 95% CI [-0.56, -0.99]), overall perceptions of safety (r = -0.90; 95% CI [-0.45, -0.99]), management support for patient safety (r = -0.90; 95% CI [-0.44, -0.98]), teamwork within units (r = -0.88; 95% CI [-0.38, -0.98]), communication openness (r = -0.85; 95% CI [-0.26, -0.98]), supervisor/manager expectations and actions promoting safety (r = -0.85; 95% CI [-0.25, -0.98]), non-punitive response to error (r = -0.78; 95% CI [-0.07, -0.97]), and frequency of events reported (r = -0.76; 95% CI [-0.01, -0.96]). After adjusting for surgical volume and ASA classification, 9 of 12 dimensions of surgical unit safety culture were significantly associated with lower colon SSI rates. These data suggest an important role for positive safety and teamwork culture and engaged hospital management in producing high-quality surgical

Report on the Survey of the Design Review of New Reactor Applications. Volume 3: Reactor

International Nuclear Information System (INIS)

Downey, Steven; Monninger, John; Nevalainen, Janne; Lorin, Aurelie; ); Webster, Philip; Joyer, Philippe; Kawamura, Tomonori; Lankin, Mikhail; Kubanyi, Jozef; Haluska, Ladislav; Persic, Andreja; Reierson, Craig; Kang, Kyungmin; Kim, Walter

2016-01-01

At the tenth meeting of the CNRA Working Group on the Regulation of New Reactors (WGRNR) in March 2013, the Working Group agreed to present the responses to the Second Phase, or Design Phase, of the Licensing Process Survey as a multi-volume text. As such, each report will focus on one of the eleven general technical categories covered in the survey. The general technical categories were selected to conform to the topics covered in the International Atomic Energy Agency (IAEA) Safety Guide GS-G-4.1. This document, which is the third report on the results of the Design Phase Survey, focuses on the Reactor. The Reactor category includes the following technical topics: fuel system design, reactor internals and core support, nuclear design and core nuclear performance, thermal and hydraulic design, reactor materials, and functional design of reactivity control system. For each technical topic, the member countries described the information provided by the applicant, the scope and level of detail of the technical review, the technical basis for granting regulatory authorisation, the skill sets required and the level of effort needed to perform the review. Based on a comparison of the information provided by the member countries in response to the survey, the following observations were made: - Although the description of the information provided by the applicant differs in scope and level of detail among the member countries that provided responses, there are similarities in the information that is required. - All of the technical topics covered in the survey are reviewed in some manner by all of the regulatory authorities that provided responses. - Design review strategies most commonly used to confirm that the regulatory requirements have been met include document review and independent verification of calculations, computer codes, or models used to describe the design and performance of the core and the fuel. - It is common to consider operating experience and

Status of safety issues at licensed power plants: TMI action plan requirements, unresolved safety issues, generic safety issues

International Nuclear Information System (INIS)

1991-12-01

As part of ongoing US Nuclear Regulatory Commission (NRC) efforts to ensure the quality and accountability of safety issue information, a program was established whereby an annual NUREG report would be published on the status of licensee implementation and NRC verification of safety issues in major NRC requirements areas. This information was compiled and reported in three NUREG volumes. Volume 1, published in March 1991, addressed the status of of Three Mile Island (TMI) Action Plan Requirements. Volume 2, published in May 1991, addressed the status of unresolved safety issues (USIs). Volume 3, published in June 1991, addressed the implementation and verification status of generic safety issues (GSIs). This annual NUREG report combines these volumes into a single report and provides updated information as of September 30, 1991. The data contained in these NUREG reports are a product of the NRC's Safety Issues Management System (SIMS) database, which is maintained by the Project Management Staff in the Office of Nuclear Reactor Regulation and by NRC regional personnel. This report is to provide a comprehensive description of the implementation and verification status of TMI Action Plan Requirements, safety issues designated as USIs, and GSIs that have been resolved and involve implementation of an action or actions by licensees. This report makes the information available to other interested parties, including the public. An additional purpose of this NUREG report is to serve as a follow-on to NUREG-0933, ''A Prioritization of Generic Safety Issues,'' which tracks safety issues up until requirements are approved for imposition at licensed plants or until the NRC issues a request for action by licensees

Patient safety climate profiles across time: Strength and level of safety climate associated with a quality improvement program in Switzerland—A cross-sectional survey study

Science.gov (United States)

Mascherek, Anna C.

2017-01-01

Safety Climate has been acknowledged as an unspecific factor influencing patient safety. However, studies rarely provide in-depth analysis of climate data. As a helpful approach, the concept of “climate strength” has been proposed. In the present study we tested the hypotheses that even if safety climate remains stable on mean-level across time, differences might be evident in strength or shape. The data of two hospitals participating in a large national quality improvement program were analysed for differences in climate profiles at two measurement occasions. We analysed differences on mean-level, differences in percent problematic response, agreement within groups, and frequency histograms in two large hospitals in Switzerland at two measurement occasions (2013 and 2015) applying the Safety Climate Survey. In total, survey responses of 1193 individuals were included in the analyses. Overall, small but significant differences on mean-level of safety climate emerged for some subgroups. Also, although agreement was strong at both time-points within groups, tendencies of divergence or consensus were present in both hospitals. Depending on subgroup and analyses chosen, differences were more or less pronounced. The present study illustrated that taking several measures into account and describing safety climate from different perspectives is necessary in order to fully understand differences and trends within groups and to develop interventions addressing the needs of different groups more precisely. PMID:28753633

Challenging patient safety culture: survey results

NARCIS (Netherlands)

Hellings, Johan; Schrooten, Ward; Klazinga, Niek; Vleugels, Arthur

2007-01-01

PURPOSE: The purpose of this paper is to measure patient safety culture in five Belgian general hospitals. Safety culture plays an important role in the approach towards greater patient safety in hospitals. DESIGN/METHODOLOGY/APPROACH: The Patient Safety Culture Hospital questionnaire was

Proceedings of the US Nuclear Regulatory Commission fifteenth water reactor safety information meeting: Volume 6, Decontamination and decommissioning, accident management, TMI-2

International Nuclear Information System (INIS)

Weiss, A.J.

1988-02-01

This six-volume report contains 140 papers out of the 164 that were presented at the Fifteenth Water Reactor Safety Information Meeting held at the National Bureau of Standards, Gaithersburg, Maryland, during the week of October 26-29, 1987. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. This report, Volume 6, discusses decontamination and decommissioning, accident management, and the Three Mile Island-2 reactor accident. Thirteen reports have been cataloged separately

National Food Safety Systems in the European Union: A Comparative Survey

Directory of Open Access Journals (Sweden)

Andreas Hadjigeorgiou

2013-04-01

Full Text Available This paper is a comparative survey of the National Food Safety Systems (NFSS of the European Union (EU Member-States (MS and the Central EU level. The main organizational structures of the NFSS, their legal frameworks, their responsibilities, their experiences, and challenges relating to food safety are discussed. Growing concerns about food safety have led the EU itself, its MS and non-EU countries, which are EU trade-partners, to review and modify their food safety systems. Our study suggests that the EU and 22 out of 27 Member States (MS have reorganized their NFSS by establishing a single food safety authority or a similar organization on the national or central level. In addition, the study analyzes different approaches towards the establishment of such agencies. Areas where marked differences in approaches were seen included the division of responsibilities for risk assessment (RA, risk management (RM, and risk communication (RC. We found that in 12 Member States, all three areas of activity (RA, RM, and RC are kept together, whereas in 10 Member States, risk management is functionally or institutionally separate from risk assessment and risk communication. No single ideal model for others to follow for the organization of a food safety authority was observed; however, revised NFSS, either in EU member states or at the EU central level, may be more effective from the previous arrangements, because they provide central supervision, give priority to food control programs, and maintain comprehensive risk analysis as part of their activities.

Nuclear criticality safety experiments, calculations, and analyses - 1958 to 1982. Volume 2. Summaries. Complilation of papers from the Transactions of the American Nuclear Society

International Nuclear Information System (INIS)

Koponen, B.L.; Hampel, V.E.

1982-01-01

This compilation contains 688 complete summaries of papers on nuclear criticality safety as presented at meetings of the American Nuclear Society (ANS). The selected papers contain criticality parameters for fissile materials derived from experiments and calculations, as well as criticality safety analyses for fissile material processing, transport, and storage. The compilation was developed as a component of the Nuclear Criticality Information System (NCIS) now under development at the Lawrence Livermore National Laboratory. The compilation is presented in two volumes: Volume 1 contains a directory to the ANS Transaction volume and page number where each summary was originally published, the author concordance, and the subject concordance derived from the keyphrases in titles. Volume 2 contains-in chronological order-the full-text summaries, reproduced here by permission of the American Nuclear Society from their Transactions, volumes 1-41

Nuclear criticality safety experiments, calculations, and analyses - 1958 to 1982. Volume 2. Summaries. Complilation of papers from the Transactions of the American Nuclear Society

Energy Technology Data Exchange (ETDEWEB)

Koponen, B.L.; Hampel, V.E.

1982-10-21

This compilation contains 688 complete summaries of papers on nuclear criticality safety as presented at meetings of the American Nuclear Society (ANS). The selected papers contain criticality parameters for fissile materials derived from experiments and calculations, as well as criticality safety analyses for fissile material processing, transport, and storage. The compilation was developed as a component of the Nuclear Criticality Information System (NCIS) now under development at the Lawrence Livermore National Laboratory. The compilation is presented in two volumes: Volume 1 contains a directory to the ANS Transaction volume and page number where each summary was originally published, the author concordance, and the subject concordance derived from the keyphrases in titles. Volume 2 contains-in chronological order-the full-text summaries, reproduced here by permission of the American Nuclear Society from their Transactions, volumes 1-41.

Self-reported confidence in patient safety knowledge among Australian undergraduate nursing students: A multi-site cross-sectional survey study.

Science.gov (United States)

Usher, Kim; Woods, Cindy; Parmenter, Glenda; Hutchinson, Marie; Mannix, Judy; Power, Tamara; Chaboyer, Wendy; Latimer, Sharon; Mills, Jane; Siegloff, Lesley; Jackson, Debra

2017-06-01

Patient safety is critical to the provision of quality health care and thus is an essential component of nurse education. To describe first, second and third year Australian undergraduate nursing students' confidence in patient safety knowledge acquired in the classroom and clinical settings across the three years of the undergraduate nursing program. A cross-sectional online survey conducted in 2015. Seven Australian universities with campuses across three states (Queensland, New South Wales, South Australia). A total of 1319 Australian undergraduate nursing students. Participants were surveyed using the 31-item Health Professional Education in Patient Safety Survey (H-PEPSS). Descriptive statistics summarised the sample and survey responses. Paired t-tests, ANOVA and generalized-estimating-equations models were used to compare responses across learning settings (classroom and clinical), and year of nursing course. Participants were most confident in their learning of clinical safety skills and least confident in learning about the sociocultural dimensions of working in teams with other health professionals, managing safety risks and understanding human and environmental factors. Only 59% of students felt confident they could approach someone engaging in unsafe practice, 75% of students agreed it was difficult to question the decisions or actions of those with more authority, and 78% were concerned they would face disciplinary action if they made a serious error. One patient safety subscale, Recognising and responding to remove immediate safety risks, was rated significantly higher by third year nursing students than by first and second year students. Two broader aspects of patient safety scales, Consistency in how patient safety issues are dealt with by different preceptors, and System aspects of patient safety are well covered in our program, were rated significantly higher by first year nursing students than by second and third year students. One scale

Surveying wearable human assistive technology for life and safety critical applications: standards, challenges and opportunities.

Science.gov (United States)

Alam, Muhammad Mahtab; Ben Hamida, Elyes

2014-05-23

In this survey a new application paradigm life and safety for critical operations and missions using wearable Wireless Body Area Networks (WBANs) technology is introduced. This paradigm has a vast scope of applications, including disaster management, worker safety in harsh environments such as roadside and building workers, mobile health monitoring, ambient assisted living and many more. It is often the case that during the critical operations and the target conditions, the existing infrastructure is either absent, damaged or overcrowded. In this context, it is envisioned that WBANs will enable the quick deployment of ad-hoc/on-the-fly communication networks to help save many lives and ensuring people's safety. However, to understand the applications more deeply and their specific characteristics and requirements, this survey presents a comprehensive study on the applications scenarios, their context and specific requirements. It explores details of the key enabling standards, existing state-of-the-art research studies, and projects to understand their limitations before realizing aforementioned applications. Application-specific challenges and issues are discussed comprehensively from various perspectives and future research and development directions are highlighted as an inspiration for new innovative solutions. To conclude, this survey opens up a good opportunity for companies and research centers to investigate old but still new problems, in the realm of wearable technologies, which are increasingly evolving and getting more and more attention recently.

The comparison of road safety survey answers between web-panel and face-to-face : Dutch results of SARTRE-4 survey.

NARCIS (Netherlands)

Goldenbeld, C. & Craen, S. de

2013-01-01

In The Netherlands, a comparison of an online and a face-to-face sample of car drivers was made to study differences on a number of selected questions from the SARTRE-4 road safety survey. Contrary to expectations, there was no indication that online respondents were more likely to come from higher

Measurable improvement in patient safety culture: A departmental experience with incident learning.

Science.gov (United States)

Kusano, Aaron S; Nyflot, Matthew J; Zeng, Jing; Sponseller, Patricia A; Ermoian, Ralph; Jordan, Loucille; Carlson, Joshua; Novak, Avrey; Kane, Gabrielle; Ford, Eric C

2015-01-01

Rigorous use of departmental incident learning is integral to improving patient safety and quality of care. The goal of this study was to quantify the impact of a high-volume, departmental incident learning system on patient safety culture. A prospective, voluntary, electronic incident learning system was implemented in February 2012 with the intent of tracking near-miss/no-harm incidents. All incident reports were reviewed weekly by a multiprofessional team with regular department-wide feedback. Patient safety culture was measured at baseline with validated patient safety culture survey questions. A repeat survey was conducted after 1 and 2 years of departmental incident learning. Proportional changes were compared by χ(2) or Fisher exact test, where appropriate. Between 2012 and 2014, a total of 1897 error/near-miss incidents were reported, representing an average of 1 near-miss report per patient treated. Reports were filed by a cross section of staff, with the majority of incidents reported by therapists, dosimetrists, and physicists. Survey response rates at baseline and 1 and 2 years were 78%, 80%, and 80%, respectively. Statistically significant and sustained improvements were noted in several safety metrics, including belief that the department was openly discussing ways to improve safety, the sense that reports were being used for safety improvement, and the sense that changes were being evaluated for effectiveness. None of the surveyed dimensions of patient safety culture worsened. Fewer punitive concerns were noted, with statistically significant decreases in the worry of embarrassment in front of colleagues and fear of getting colleagues in trouble. A comprehensive incident learning system can identify many areas for improvement and is associated with significant and sustained improvements in patient safety culture. These data provide valuable guidance as incident learning systems become more widely used in radiation oncology. Copyright © 2015

"Against the silence": Development and first results of a patient survey to assess experiences of safety-related events in hospital

Directory of Open Access Journals (Sweden)

Schwappach David LB

2008-03-01

Full Text Available Abstract Background Involvement of patients in the detection and prevention of safety related events and medical errors have been widely recommended. However, it has also been questioned whether patients at large are willing and able to identify safety-related events in their care. The aim of this study was to develop and pilot test a brief patient safety survey applicable to inpatient care in Swiss hospitals. Methods A survey instrument was developed in an iterative procedure. The instrument asks patients to report whether they have experienced specific undesirable events during their hospital stay. The preliminary version was developed together with experts and tested in focus groups with patients. The adapted survey instrument was pilot-tested in random samples of patients of two Swiss hospitals (n = 400. Responders to the survey that had reported experience of any incident were sampled for qualitative interviews (n = 18. Based on the interview, the researcher classified the reported incidents as confirmed or discarded. Results The survey was generally well accepted in the focus groups and interviews. In the quantitative pilot test, 125 patients returned the survey (response rate: 31%. The mean age of responders was 55 years (range 17–91, SD 18 years and 62.5% were female. The 125 participating patients reported 94 "definitive" and 34 "uncertain" events. 14% of the patients rated any of the experienced events as "serious". The definitive and uncertain events reported with highest frequency were phlebitis, missing hand hygiene, allergic drug reaction, unavailability of documents, and infection. 23% of patients reported some or serious concerns about their safety. The qualitative interviews indicate that both, the extent of patients' uncertainty in the classification of events and the likelihood of confirmation by the interviewer vary very much by type of incident. Unexpectedly, many patients reported problems and incidents related to food

Computational needs survey of NASA automation and robotics missions. Volume 1: Survey and results

Science.gov (United States)

Davis, Gloria J.

1991-01-01

NASA's operational use of advanced processor technology in space systems lags behind its commercial development by more than eight years. One of the factors contributing to this is that mission computing requirements are frequently unknown, unstated, misrepresented, or simply not available in a timely manner. NASA must provide clear common requirements to make better use of available technology, to cut development lead time on deployable architectures, and to increase the utilization of new technology. A preliminary set of advanced mission computational processing requirements of automation and robotics (A&R) systems are provided for use by NASA, industry, and academic communities. These results were obtained in an assessment of the computational needs of current projects throughout NASA. The high percent of responses indicated a general need for enhanced computational capabilities beyond the currently available 80386 and 68020 processor technology. Because of the need for faster processors and more memory, 90 percent of the polled automation projects have reduced or will reduce the scope of their implementation capabilities. The requirements are presented with respect to their targeted environment, identifying the applications required, system performance levels necessary to support them, and the degree to which they are met with typical programmatic constraints. Volume one includes the survey and results. Volume two contains the appendixes.

Safety as experienced by patients themselves: a Finnish survey of the most recent period of care.

Science.gov (United States)

Sahlström, Merja; Partanen, Pirjo; Turunen, Hannele

2014-06-01

We examined patients' experiences of patient safety and participation in promoting safe care during their most recent care period. A survey of patients (N = 175) revealed that treatment, medication, and device safety were mostly experienced as very good or excellent, but responses varied by age and experience. Patients ages 66-75 were most critical of treatment and medication safety. Device safety was rated the worst aspect of safety. Twenty percent of respondents had experienced errors at some time during their care. Patients who had experienced errors and those who were treated at inpatient wards versus a day surgery unit were most critical towards patient participation. Open and transparent error management involving patients is needed to promote treatment, medication, and especially device safety. © 2014 Wiley Periodicals, Inc.

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

Management response plan for the Chemical Safety Vulnerability Working Group report. Volume 1

International Nuclear Information System (INIS)

1994-09-01

The Chemical Safety Vulnerability (CSV) Working Group was established to identify adverse conditions involving hazardous chemicals at DOE facilities that might result in fires or explosions, release of hazardous chemicals to the environment, or exposure of workers or the public to chemicals. A CSV Review was conducted in 146 facilities at 29 sites. Eight generic vulnerabilities were documented related to: abandoned chemicals and chemical residuals; past chemical spills and ground releases; characterization of legacy chemicals and wastes; disposition of legacy chemicals; storage facilities and conditions; condition of facilities and support systems; unanalyzed and unaddressed hazards; and inventory control and tracking. Weaknesses in five programmatic areas were also identified related to: management commitment and planning; chemical safety management programs; aging facilities that continue to operate; nonoperating facilities awaiting deactivation; and resource allocations. Volume 1 contains a discussion of the chemical safety improvements planned or already underway at DOE sites to correct facility or site-specific vulnerabilities. The main part of the report is a discussion of each of the programmatic deficiencies; a description of the tasks to be accomplished; the specific actions to be taken; and the organizational responsibilities for implementation

Proceedings of the twenty-fourth water reactor safety information meeting. Volume 1: Plenary session; High burnup fuel; Containment and structural aging

International Nuclear Information System (INIS)

Monteleone, S.

1997-01-01

This three-volume report contains papers presented at the Twenty-Fourth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, maryland, October 21--23, 1996. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from Czech Republic, Finland, France, Japan, Norway, Russia and United Kingdom. This first volume is divided into 3 sections: plenary session; high burnup fuel; and containment and structural aging. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database

Proceedings of the twenty-fourth water reactor safety information meeting. Volume 1: Plenary session; High burnup fuel; Containment and structural aging

Energy Technology Data Exchange (ETDEWEB)

Monteleone, S. [comp.] [Brookhaven National Lab., Upton, NY (United States)

1997-01-01

This three-volume report contains papers presented at the Twenty-Fourth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, maryland, October 21--23, 1996. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from Czech Republic, Finland, France, Japan, Norway, Russia and United Kingdom. This first volume is divided into 3 sections: plenary session; high burnup fuel; and containment and structural aging. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume VI. Safety and environmental considerations for licensing

International Nuclear Information System (INIS)

1980-06-01

This volume of the Nonproliferation Alternative Systems Assessment Program report addresses safety and environmental considerations in licensing the principal alternative nuclear reactors and fuel cycles in the United States for large-scale commercial nuclear power plants. In addition, this volume examines the safety and environmental considerations for licensing fuel service centers. These centers, which have been proposed for controlling sensitive fuel-cycle facilities and special nuclear materials, would contain a combination of such facilities as reprocessing plants, fabrication plants, and reactors. For this analysis, two fuel service center concepts were selected - one with power - generating capability and one without

Motorcycle Safety Education Programs: Report of a Survey of State Departments of Education and of Colleges and Universities.

Science.gov (United States)

American Driver and Traffic Safety Education Association, Washington, DC.

A survey of State departments of education and colleges and universities, conducted by the Motorcycle Industry Council Safety and Education Foundation, revealed the need for more teacher education programs, instructional materials, and organized workshops that promote motorcycle safety education. The primary interest indicated by State departments…

Behavioral integrity for safety, priority of safety, psychological safety, and patient safety : a team-level study

NARCIS (Netherlands)

Leroy, H.; Dierynck, B.; Anseel, F.; Simons, T.; Halbesleben, J.R.; McCaughey, D.; Savage, G.T.; Sels, L.

2012-01-01

This article clarifies how leader behavioral integrity for safety helps solve follower's double bind between adhering to safety protocols and speaking up about mistakes against protocols. Path modeling of survey data in 54 nursing teams showed that head nurse behavioral integrity for safety

Treatment of plutonium-bearing solutions: A brief survey of the DOE complex

International Nuclear Information System (INIS)

Conner, C.; Chamberlain, D.B.; Chen, L.; Vandegrift, G.F.

1995-03-01

With the abrupt shutdown of some DOE facilities, a significant volume of in-process material was left in place and still requires treatment for interim storage. Because the systems containing these process streams have deteriorated since shutdown, a portable system for treating the solutions may be useful. A brief survey was made of the DOE complex on the need for a portable treatment system to treat plutonium-bearing solutions. A survey was completed to determine (1) the compositions and volumes of solutions and heels present, (2) the methods that have been used to treat these solutions and heels in the past, and (3) the potential problems that exist in removing and treating these solutions. Based on the surveys and on the Defense Nuclear Facilities Safety Board Recommendation 94-1, design criteria for a portable treatment system were generated

Renal studies in safety pharmacology and toxicology: A survey conducted in the top 15 pharmaceutical companies.

Science.gov (United States)

Benjamin, Amanda; Gallacher, David J; Greiter-Wilke, Andrea; Guillon, Jean-Michel; Kasai, Cheiko; Ledieu, David; Levesque, Paul; Prelle, Katja; Ratcliffe, Sian; Sannajust, Frederick; Valentin, Jean-Pierre

2015-01-01

With the recent development of more sensitive biomarkers to assess kidney injury preclinically, a survey was designed i) to investigate what strategies are used to investigate renal toxicity in both ICH S7A compliant Safety Pharmacology (SP) studies after a single dose of a compound and within repeat-dose toxicity studies by large pharmaceutical companies today; ii) to understand whether renal SP studies have impact or utility in drug development and/or if it may be more appropriate to assess renal effects after multiple doses of compounds; iii) to ascertain how much mechanistic work is performed by the top 15 largest pharmaceutical companies (as determined by R&D revenue size); iv) to gain an insight into the impact of the validation of DIKI biomarkers and their introduction in the safety evaluation paradigm; and v) to understand the impact of renal/urinary safety study data on progression of projects. Two short anonymous surveys were submitted to SP leaders of the top 15 pharmaceutical companies, as defined by 2012 R&D portfolio size. Fourteen multiple choice questions were designed to explore the strategies used to investigate renal effects in both ICH S7A compliant SP studies and within toxicology studies. A 67% and 60% response rate was obtained in the first and second surveys, respectively. Nine out of ten respondent companies conduct renal excretory measurements (eg. urine analysis) in toxicology studies whereas only five out of ten conduct specific renal SP studies; and all of those 5 also conduct the renal excretory measurements in toxicology studies. These companies measure and/or calculate a variety of parameters as part of these studies, and also on a case by case basis include regulatory qualified and non-qualified DIKI biomarkers. Finally, only one company has used renal/urinary functional data alone to stop a project, whereas the majority of respondents combine renal data with other target organ assessments to form an integrated decision-making set

Sodium fast reactor safety and licensing research plan - Volume II

International Nuclear Information System (INIS)

Ludewig, H.; Powers, D.A.; Hewson, John C.; LaChance, Jeffrey L.; Wright, A.; Phillips, J.; Zeyen, R.; Clement, B.; Garner, Frank; Walters, Leon; Wright, Steve; Ott, Larry J.; Suo-Anttila, Ahti Jorma; Denning, Richard; Ohshima, Hiroyuki; Ohno, S.; Miyhara, S.; Yacout, Abdellatif; Farmer, M.; Wade, D.; Grandy, C.; Schmidt, R.; Cahalen, J.; Olivier, Tara Jean; Budnitz, R.; Tobita, Yoshiharu; Serre, Frederic; Natesan, Ken; Carbajo, Juan J.; Jeong, Hae-Yong; Wigeland, Roald; Corradini, Michael; Thomas, Justin; Wei, Tom; Sofu, Tanju; Flanagan, George F.; Bari, R.; Porter D.

2012-01-01

Expert panels comprised of subject matter experts identified at the U.S. National Laboratories (SNL, ANL, INL, ORNL, LBL, and BNL), universities (University of Wisconsin and Ohio State University), international agencies (IRSN, CEA, JAEA, KAERI, and JRC-IE) and private consultation companies (Radiation Effects Consulting) were assembled to perform a gap analysis for sodium fast reactor licensing. Expert-opinion elicitation was performed to qualitatively assess the current state of sodium fast reactor technologies. Five independent gap analyses were performed resulting in the following topical reports: (1) Accident Initiators and Sequences (i.e., Initiators/Sequences Technology Gap Analysis), (2) Sodium Technology Phenomena (i.e., Advanced Burner Reactor Sodium Technology Gap Analysis), (3) Fuels and Materials (i.e., Sodium Fast Reactor Fuels and Materials: Research Needs), (4) Source Term Characterization (i.e., Advanced Sodium Fast Reactor Accident Source Terms: Research Needs), and (5) Computer Codes and Models (i.e., Sodium Fast Reactor Gaps Analysis of Computer Codes and Models for Accident Analysis and Reactor Safety). Volume II of the Sodium Research Plan consolidates the five gap analysis reports produced by each expert panel, wherein the importance of the identified phenomena and necessities of further experimental research and code development were addressed. The findings from these five reports comprised the basis for the analysis in Sodium Fast Reactor Research Plan Volume I.

Sodium fast reactor safety and licensing research plan. Volume II.

Energy Technology Data Exchange (ETDEWEB)

Ludewig, H. (Brokhaven National Laboratory, Upton, NY); Powers, D. A.; Hewson, John C.; LaChance, Jeffrey L.; Wright, A. (Argonne National Laboratory, Argonne, IL); Phillips, J.; Zeyen, R. (Institute for Energy Petten, Saint-Paul-lez-Durance, France); Clement, B. (IRSN/DPAM.SEMIC Bt 702, Saint-Paul-lez-Durance, France); Garner, Frank (Radiation Effects Consulting, Richland, WA); Walters, Leon (Advanced Reactor Concepts, Los Alamos, NM); Wright, Steve; Ott, Larry J. (Oak Ridge National Laboratory, Oak Ridge, TN); Suo-Anttila, Ahti Jorma; Denning, Richard (Ohio State University, Columbus, OH); Ohshima, Hiroyuki (Japan Atomic Energy Agency, Ibaraki, Japan); Ohno, S. (Japan Atomic Energy Agency, Ibaraki, Japan); Miyhara, S. (Japan Atomic Energy Agency, Ibaraki, Japan); Yacout, Abdellatif (Argonne National Laboratory, Argonne, IL); Farmer, M. (Argonne National Laboratory, Argonne, IL); Wade, D. (Argonne National Laboratory, Argonne, IL); Grandy, C. (Argonne National Laboratory, Argonne, IL); Schmidt, R.; Cahalen, J. (Argonne National Laboratory, Argonne, IL); Olivier, Tara Jean; Budnitz, R. (Lawrence Berkeley National Laboratory, Berkeley, CA); Tobita, Yoshiharu (Japan Atomic Energy Agency, Ibaraki, Japan); Serre, Frederic (Centre d' %C3%94etudes nucl%C3%94eaires de Cadarache, Cea, France); Natesan, Ken (Argonne National Laboratory, Argonne, IL); Carbajo, Juan J. (Oak Ridge National Laboratory, Oak Ridge, TN); Jeong, Hae-Yong (Korea Atomic Energy Research Institute, Daejeon, Korea); Wigeland, Roald (Idaho National Laboratory, Idaho Falls, ID); Corradini, Michael (University of Wisconsin-Madison, Madison, WI); Thomas, Justin (Argonne National Laboratory, Argonne, IL); Wei, Tom (Argonne National Laboratory, Argonne, IL); Sofu, Tanju (Argonne National Laboratory, Argonne, IL); Flanagan, George F. (Oak Ridge National Laboratory, Oak Ridge, TN); Bari, R. (Brokhaven National Laboratory, Upton, NY); Porter D. (Idaho National Laboratory, Idaho Falls, ID); Lambert, J. (Argonne National Laboratory, Argonne, IL); Hayes, S. (Idaho National Laboratory, Idaho Falls, ID); Sackett, J. (Idaho National Laboratory, Idaho Falls, ID); Denman, Matthew R.

2012-05-01

Expert panels comprised of subject matter experts identified at the U.S. National Laboratories (SNL, ANL, INL, ORNL, LBL, and BNL), universities (University of Wisconsin and Ohio State University), international agencies (IRSN, CEA, JAEA, KAERI, and JRC-IE) and private consultation companies (Radiation Effects Consulting) were assembled to perform a gap analysis for sodium fast reactor licensing. Expert-opinion elicitation was performed to qualitatively assess the current state of sodium fast reactor technologies. Five independent gap analyses were performed resulting in the following topical reports: (1) Accident Initiators and Sequences (i.e., Initiators/Sequences Technology Gap Analysis), (2) Sodium Technology Phenomena (i.e., Advanced Burner Reactor Sodium Technology Gap Analysis), (3) Fuels and Materials (i.e., Sodium Fast Reactor Fuels and Materials: Research Needs), (4) Source Term Characterization (i.e., Advanced Sodium Fast Reactor Accident Source Terms: Research Needs), and (5) Computer Codes and Models (i.e., Sodium Fast Reactor Gaps Analysis of Computer Codes and Models for Accident Analysis and Reactor Safety). Volume II of the Sodium Research Plan consolidates the five gap analysis reports produced by each expert panel, wherein the importance of the identified phenomena and necessities of further experimental research and code development were addressed. The findings from these five reports comprised the basis for the analysis in Sodium Fast Reactor Research Plan Volume I.

Development of a patient safety climate survey for Chinese hospitals: cross-national adaptation and psychometric evaluation.

Science.gov (United States)

Zhu, Junya; Li, Liping; Zhao, Hailei; Han, Guangshu; Wu, Albert W; Weingart, Saul N

2014-10-01

Existing patient safety climate instruments, most of which have been developed in the USA, may not accurately reflect the conditions in the healthcare systems of other countries. To develop and evaluate a patient safety climate instrument for healthcare workers in Chinese hospitals. Based on a review of existing instruments, expert panel review, focus groups and cognitive interviews, we developed items relevant to patient safety climate in Chinese hospitals. The draft instrument was distributed to 1700 hospital workers from 54 units in six hospitals in five Chinese cities between July and October 2011, and 1464 completed surveys were received. We performed exploratory and confirmatory factor analyses and estimated internal consistency reliability, within-unit agreement, between-unit variation, unit-mean reliability, correlation between multi-item composites, and association between the composites and two single items of perceived safety. The final instrument included 34 items organised into nine composites: institutional commitment to safety, unit management support for safety, organisational learning, safety system, adequacy of safety arrangements, error reporting, communication and peer support, teamwork and staffing. All composites had acceptable unit-mean reliabilities (≥0.74) and within-unit agreement (Rwg ≥0.71), and exhibited significant between-unit variation with intraclass correlation coefficients ranging from 9% to 21%. Internal consistency reliabilities ranged from 0.59 to 0.88 and were ≥0.70 for eight of the nine composites. Correlations between composites ranged from 0.27 to 0.73. All composites were positively and significantly associated with the two perceived safety items. The Chinese Hospital Survey on Patient Safety Climate demonstrates adequate dimensionality, reliability and validity. The integration of qualitative and quantitative methods is essential to produce an instrument that is culturally appropriate for Chinese hospitals

Exploring relationships between hospital patient safety culture and Consumer Reports safety scores.

Science.gov (United States)

Smith, Scott Alan; Yount, Naomi; Sorra, Joann

2017-02-16

A number of private and public companies calculate and publish proprietary hospital patient safety scores based on publicly available quality measures initially reported by the U.S. federal government. This study examines whether patient safety culture perceptions of U.S. hospital staff in a large national survey are related to publicly reported patient safety ratings of hospitals. The Agency for Healthcare Research and Quality Hospital Survey on Patient Safety Culture (Hospital SOPS) assesses provider and staff perceptions of hospital patient safety culture. Consumer Reports (CR), a U.S. based non-profit organization, calculates and shares with its subscribers a Hospital Safety Score calculated annually from patient experience survey data and outcomes data gathered from federal databases. Linking data collected during similar time periods, we analyzed relationships between staff perceptions of patient safety culture composites and the CR Hospital Safety Score and its five components using multiple multivariate linear regressions. We analyzed data from 164 hospitals, with patient safety culture survey responses from 140,316 providers and staff, with an average of 856 completed surveys per hospital and an average response rate per hospital of 56%. Higher overall Hospital SOPS composite average scores were significantly associated with higher overall CR Hospital Safety Scores (β = 0.24, p Consumer Reports Hospital Safety Score, which is a composite of patient experience and outcomes data from federal databases. As hospital managers allocate resources to improve patient safety culture within their organizations, their efforts may also indirectly improve consumer-focused, publicly reported hospital rating scores like the Consumer Reports Hospital Safety Score.

Implementation of the surgical safety checklist in Switzerland and perceptions of its benefits: cross-sectional survey.

Directory of Open Access Journals (Sweden)

Stéphane Cullati

Full Text Available OBJECTIVES: To examine the implementation of the Surgical Safety Checklist (SSC among surgeons and anaesthetists working in Swiss hospitals and clinics and their perceptions of the SSC. METHODS: Cross-sectional survey at the 97th Annual Meeting of the Swiss Society of Surgery, Switzerland, 2010. Opinions of the SSC were assessed with a 6-item questionnaire. RESULTS: 152 respondents answered the questionnaire (participation rate 35.1%. 64.7% respondents acknowledged having a checklist in their hospital or their clinic. Median implementation year was 2009. More than 8 out of 10 respondents reported their team applied the Sign In and the Time Out very often or quasi systematically, whereas almost half of respondents acknowledged the Sign Out was applied never or rarely. The majority of respondents agreed that the checklist improves safety and team communication, and helps to develop a safety culture. However, they were less supportive about the opinion that the checklist facilitates teamwork and eliminates social hierarchy between caregivers. CONCLUSIONS: This survey indicates that the SSC has been largely implemented in many Swiss hospitals and clinics. Both surgeons and anaesthetists perceived the SSC as a valuable tool in improving intraoperative patient safety and communication among health care professionals, with lesser importance in facilitating teamwork (and eliminating hierarchical categories.

Design data and safety features of commercial nuclear power plants including cumulative index for Volumes I--VI

International Nuclear Information System (INIS)

Heddleson, F.A.

1977-01-01

Design data, safety features, and site characteristics are summarized for 12 nuclear power units in 6 power stations in the United States. Six pages of data are presented for each station, consisting of thermal-hydraulic and nuclear factors, containment features, emergency-core-cooling systems, site features, circulating water system data, and miscellaneous factors. In addition, an aerial perspective is presented for each plant. This volume covers plants with docket numbers 50-553 through 50-569 (Phipps Bend, Black Fox, Yellow Creek, and NEP) and two earlier plants not previously reported--Hope Creek (50-354, 50-355) and WPPSS 1 and 4 (50-460, 50-513). Indexes for this volume and the five earlier volumes are presented in three forms--by docket number, by plant name, and by participating utility

Sensitivity and uncertainty analyses applied to criticality safety validation, methods development. Volume 1

International Nuclear Information System (INIS)

Broadhead, B.L.; Hopper, C.M.; Childs, R.L.; Parks, C.V.

1999-01-01

This report presents the application of sensitivity and uncertainty (S/U) analysis methodologies to the code/data validation tasks of a criticality safety computational study. Sensitivity and uncertainty analysis methods were first developed for application to fast reactor studies in the 1970s. This work has revitalized and updated the available S/U computational capabilities such that they can be used as prototypic modules of the SCALE code system, which contains criticality analysis tools currently used by criticality safety practitioners. After complete development, simplified tools are expected to be released for general use. The S/U methods that are presented in this volume are designed to provide a formal means of establishing the range (or area) of applicability for criticality safety data validation studies. The development of parameters that are analogous to the standard trending parameters forms the key to the technique. These parameters are the D parameters, which represent the differences by group of sensitivity profiles, and the ck parameters, which are the correlation coefficients for the calculational uncertainties between systems; each set of parameters gives information relative to the similarity between pairs of selected systems, e.g., a critical experiment and a specific real-world system (the application)

Perception of risks and safety. Results of the November 2001 survey

International Nuclear Information System (INIS)

2001-01-01

After having recalled the themes present in the survey on the perception of risks and safety as far as nuclear energy is concerned, this report proposes an analysis of the obtained results. It discusses the current general concerns, the perception of risks (confidence, truth), the perception of technological and natural risks for the environment (hazardous installations, demand for environmental acceptability of installations, disasters), the opinions on nuclear activities (image, actors, control of these activities, possibility of a nuclear accident), and finally the risks associated with radon

JANNAF 28th Propellant Development and Characterization Subcommittee and 17th Safety and Environmental Protection Subcommittee Joint Meeting. Volume 1

Science.gov (United States)

Cocchiaro, James E. (Editor); Mulder, Edwin J. (Editor); Gomez-Knight, Sylvia J. (Editor)

1999-01-01

This volume contains 37 unclassified/unlimited-distribution technical papers that were presented at the JANNAF 28th Propellant Development & Characterization Subcommittee (PDCS) and 17th Safety & Environmental Protection Subcommittee (S&EPS) Joint Meeting, held 26-30 April 1999 at the Town & Country Hotel and the Naval Submarine Base, San Diego, California. Volume II contains 29 unclassified/limited-distribution papers that were presented at the 28th PDCS and 17th S&EPS Joint Meeting. Volume III contains a classified paper that was presented at the 28th PDCS Meeting on 27 April 1999. Topics covered in PDCS sessions include: solid propellant rheology; solid propellant surveillance and aging; propellant process engineering; new solid propellant ingredients and formulation development; reduced toxicity liquid propellants; characterization of hypergolic propellants; and solid propellant chemical analysis methods. Topics covered in S&EPS sessions include: space launch range safety; liquid propellant hazards; vapor detection methods for toxic propellant vapors and other hazardous gases; toxicity of propellants, ingredients, and propellant combustion products; personal protective equipment for toxic liquid propellants; and demilitarization/treatment of energetic material wastes.

1980 survey and evaluation of utility conservation, load management, and solar end-use projects. Volume 3: utility load management projects. Final report

Energy Technology Data Exchange (ETDEWEB)

1982-01-01

The results of the 1980 survey of electric utility-sponsored energy conservation, load management, and end-use solar energy conversion projects are described. The work is an expansion of a previous survey and evaluation and has been jointly sponsored by EPRI and DOE through the Oak Ridge National Laboratory. There are three volumes and a summary document. Each volume presents the results of an extensive survey to determine electric utility involvement in customer-side projects related to the particular technology (i.e., conservation, solar, or load management), selected descriptions of utility projects and results, and first-level technical and economic evaluations.

Survey of fish impingement at power plants in the United States. Volume II. Inland waters

International Nuclear Information System (INIS)

Freeman, R.F. III; Sharma, R.K.

1977-03-01

Impingement of fish at cooling-water intakes of 33 power plants located on inland waters other than the Great Lakes has been surveyed and data are presented. Descriptions of site, plant, and intake design and operation are provided. Reports in this volume summarize impingement data for individual plants in tabular and histogram formats. Information was available from differing sources such as the utilities themselves, public documents, regulatory agencies, and others. Thus, the extent of detail in the reports varies greatly from plant to plant. Histogram preparation involved an extrapolation procedure that has inadequacies. The reader is cautioned in the use of information presented in this volume to determine intake-design acceptability or intensity of impacts on ecosystems. No conclusions are presented herein; data comparisons are made in Volume IV

Kempe's engineers year-book for 1977. Volume II

Energy Technology Data Exchange (ETDEWEB)

Prockter, C.E. (ed.)

1977-01-01

The second volume of this two-volume yearbook contains data on: electrical and electronic engineering; aerodynamics and aircraft propulsion; gas turbines; internal combustion engines; motor vehicles; fuels; fluidics; nuclear energy; gas and gas engineering; steam engineering and steam turbines; marine diesel engines; naval architecture; mining engineering; industrial explosives; air compression, pneumatic equipment, etc.; refrigeration, heating, ventilation and air conditioning; lighting; industrial safety and protection; fire protection; highway engineering; surveying; foundation and earthwork; cements, mortars and clay products; buildings; public health engineering; concretes; design of steel structures; bridges and bridgework; paints and coatings; patents, designs and trade marks; depreciation; legal notes for engineers; factory planning and layout; and agricultural engineering. (1325p.) A subject index is provided. (LCL)

Nuclear proliferation and civilian nuclear power: report of the Nonproliferation Alternative Systems Assessment Program. Volume VI. Safety and environmental considerations for licensing

International Nuclear Information System (INIS)

1979-12-01

Volume 6 of the Nonproliferation Alternative Systems Assessment Program report addresses safety and environmental considerations in licensing the principal alternative nuclear reactors and fuel cycles in the United States for large-scale commercial nuclear power plants. In addition, this volume examines the safety and environmental considerations for licensing fuel service centers. These centers, which have been proposed for controlling sensitive fuel-cycle facilities and special nuclear materials, would contain a combination of such facilities as reprocessing plants, fabrication plants, and reactors. For this analysis, two fuel service center concepts were selected - one with power-generating capability and one without. This volume also provides estimates of the time required for development of large-scale commercial reactor systems to reach the construction permit application stage and for fuel-cycle facilities to reach the operating license application stage, which is a measure of the relative technical status of alternative nuclear systems

Introducing standardized “readbacks” to improve patient safety in surgery: a prospective survey in 92 providers at a public safety-net hospital

Directory of Open Access Journals (Sweden)

Prabhakar Hari

2012-06-01

Full Text Available Abstract Background Communication breakdowns represent the main root cause of preventable complications which lead to harm to surgical patients. Standardized readbacks have been successfully implemented as a main pillar of professional aviation safety for decades, to ensure a safe closed-loop communication between air traffic control and individual pilots. The present study was designed to determine the perception of staff in perioperative services regarding the role of standardized readbacks for improving patient safety in surgery at a single public safety-net hospital and level 1 trauma center. Methods A 12-item questionnaire was sent to 180 providers in perioperative services at Denver Health Medical Center. The survey was designed to determine the individual participants’ perception of (1 appropriateness of current readback processes; (2 willingness to attend a future training module on this topic; (3 specific scenarios in which readbacks may be effective; and (4 perceived major barriers to the implementation of standardized readbacks. Survey results were compared between departments (surgery versus anesthesia and between specific staff roles (attending or midlevel provider, resident physician, nursing staff, using non-parametric tests. Results The response rate to the survey was 50.1 % (n = 92. Respondents overwhelmingly recognized the role of readbacks in reducing communication errors and improving patient safety. There was a strong agreement among respondents to support participation in a readbacks training program. There was no difference in the responses between the surgery and anesthesia departments. There was a statistically significant difference in the healthcare providers willingness to attend a short training module on readbacks (p  The main challenge for respondents, which emanated from their responses, appeared to relate to determining the ideal scenarios in which readbacks may be most appropriately used. Overall

Nurse perceptions of safety climate in Australian acute hospitals: a cross-sectional survey.

Science.gov (United States)

Soh, Sze-Ee; Morello, Renata; Rifat, Sheral; Brand, Caroline; Barker, Anna

2017-03-16

Objectives The aim of the present study was to explore nurse perceptions of safety climate in acute Australian hospitals. Methods Participants included 420 nurses who have worked on 24 acute wards from six Australian hospitals. The Safety Attitudes Questionnaire (SAQ) Short Form was used to quantify nurse perceptions of safety climate and benchmarked against international data. Generalised linear mixed models were used to explore factors that may influence safety climate. Results On average, 53.5% of nurses held positive attitudes towards job satisfaction followed by teamwork climate (50.5%). There was variability in SAQ domain scores across hospitals. The safety climate and perceptions of hospital management domains also varied across wards within a hospital. Nurses who had worked longer at a hospital were more likely to have poorer perceptions of hospital management (β=-5.2; P=0.014). Overall, nurse perceptions of safety climate appeared higher than international data. Conclusions The perceptions of nurses working in acute Victorian and New South Wales hospitals varied between hospitals as well as across wards within each hospital. This highlights the importance of surveying all hospital wards and examining the results at the ward level when implementing strategies to improve patient safety and the culture of safety in organisations. What is known about the topic? Prior studies in American nursing samples have shown that hospitals with higher levels of safety climate have a lower relative incidence of preventable patient complications and adverse events. Developing a culture of safety in hospitals may be useful in targeting efforts to improve patient safety. What does this paper add? This paper has shown that the perceptions of safety climate among nurses working in acute Australian hospitals varied between hospitals and across wards within a hospital. Only half the nurses also reported positive attitudes towards job satisfaction and teamwork climate. What are

Statistical Analysis of the Worker Engagement Survey Administered at the Worker Safety and Security Team Festival

Energy Technology Data Exchange (ETDEWEB)

Davis, Adam Christopher [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2015-08-25

The Worker Safety and Security Team (WSST) at Los Alamos National Laboratory holds an annual festival, WSST-fest, to engage workers and inform them about safety- and securityrelated matters. As part of the 2015 WSST-fest, workers were given the opportunity to participate in a survey assessing their engagement in their organizations and work environments. A total of 789 workers participated in the 23-question survey where they were also invited, optionally, to identify themselves, their organization, and to give open-ended feedback. The survey consisted of 23 positive statements (i.e. “My organization is a good place to work.”) with which the respondent could express a level of agreement. The text of these statements are provided in Table 1. The level of agreement corresponds to a 5-level Likert scale ranging from “Strongly Disagree” to “Strongly Agree.” In addition to assessing the overall positivity or negativity of the scores, the results were partitioned into several cohorts based on the response meta-data (self-identification, comments, etc.) to explore trends. Survey respondents were presented with the options to identify themselves, their organizations and to provide comments. These options suggested the following questions about the data set.

Kilowatt isotope power system. Phase II plan. Volume V. Safety, quality assurance and reliability

International Nuclear Information System (INIS)

1978-01-01

The development of a Kilowatt Isotope Power System (KIPS) was begun in 1975 for the purpose of satisfying the power requirements of satellites in the 1980's. The KIPS is a 238 PuO 2 -fueled organic Rankine cycle turbine power system to provide a design output of 500 to 2000 W. Included in this volume are: launch and flight safety considerations; quality assurance techniques and procedures to be followed through system fabrication, assembly and inspection; and the reliability program made up of reliability prediction analysis, failure mode analysis and criticality analysis

Evaluation of patient safety culture among Malaysian retail pharmacists: results of a self-reported survey

Science.gov (United States)

Sivanandy, Palanisamy; Maharajan, Mari Kannan; Rajiah, Kingston; Wei, Tan Tyng; Loon, Tan Wee; Yee, Lim Chong

2016-01-01

Background Patient safety is a major public health issue, and the knowledge, skills, and experience of health professionals are very much essential for improving patient safety. Patient safety and medication error are very much associated. Pharmacists play a significant role in patient safety. The function of pharmacists in the medication use process is very different from medical and nursing colleagues. Medication dispensing accuracy is a vital element to ensure the safety and quality of medication use. Objective To evaluate the attitude and perception of the pharmacist toward patient safety in retail pharmacies setup in Malaysia. Methods A Pharmacy Survey on Patient Safety Culture questionnaire was used to assess patient safety culture, developed by the Agency for Healthcare Research and Quality, and the convenience sampling method was adopted. Results The overall positive response rate ranged from 31.20% to 87.43%, and the average positive response rate was found to be 67%. Among all the eleven domains pertaining to patient safety culture, the scores of “staff training and skills” were less. Communication openness, and patient counseling are common, but not practiced regularly in the Malaysian retail pharmacy setup compared with those in USA. The overall perception of patient safety of an acceptable level in the current retail pharmacy setup. Conclusion The study revealed that staff training, skills, communication in patient counseling, and communication across shifts and about mistakes are less in current retail pharmacy setup. The overall perception of patient safety should be improved by educating the pharmacists about the significance and essential of patient safety. PMID:27524887

Evaluation of patient safety culture among Malaysian retail pharmacists: results of a self-reported survey.

Science.gov (United States)

Sivanandy, Palanisamy; Maharajan, Mari Kannan; Rajiah, Kingston; Wei, Tan Tyng; Loon, Tan Wee; Yee, Lim Chong

2016-01-01

Patient safety is a major public health issue, and the knowledge, skills, and experience of health professionals are very much essential for improving patient safety. Patient safety and medication error are very much associated. Pharmacists play a significant role in patient safety. The function of pharmacists in the medication use process is very different from medical and nursing colleagues. Medication dispensing accuracy is a vital element to ensure the safety and quality of medication use. To evaluate the attitude and perception of the pharmacist toward patient safety in retail pharmacies setup in Malaysia. A Pharmacy Survey on Patient Safety Culture questionnaire was used to assess patient safety culture, developed by the Agency for Healthcare Research and Quality, and the convenience sampling method was adopted. The overall positive response rate ranged from 31.20% to 87.43%, and the average positive response rate was found to be 67%. Among all the eleven domains pertaining to patient safety culture, the scores of "staff training and skills" were less. Communication openness, and patient counseling are common, but not practiced regularly in the Malaysian retail pharmacy setup compared with those in USA. The overall perception of patient safety of an acceptable level in the current retail pharmacy setup. The study revealed that staff training, skills, communication in patient counseling, and communication across shifts and about mistakes are less in current retail pharmacy setup. The overall perception of patient safety should be improved by educating the pharmacists about the significance and essential of patient safety.

Survey of fish impingement at power plants in the United States. Volume I. The Great Lakes

International Nuclear Information System (INIS)

Sharma, R.K.; Freeman, R.F. III.

1977-03-01

Impingement of fish at cooling-water intakes of 20 power plants located on the Great Lakes has been surveyed and data are presented. Descriptions of site, plant, and intake design and operation are provided. Reports in this volume summarize impingement data for individual plants in tabular and histogram formats. Information was available from differing sources such as the utilities themselves, public documents, regulatory agencies, and others. Thus, the extent of detail in the reports varies greatly from plant to plant. Histogram preparation involved an extrapolation procedure that has inadequacies. The reader is cautioned in the use of information presented in this volume to determine intake-design acceptability or intensity of impacts on ecosystems. No conclusions are presented herein; data comparisons are made in Volume IV

Safety Evakuation Of Triga-2000 Reactor Operation Viewed From Safety Culture

International Nuclear Information System (INIS)

Karliana, Itjeu

2001-01-01

The safety evaluation activities of TRIGA-2000 operation viewed from safety culture performed by questioners data collected from the operators and supervisor site of TRIGA-2000 P3TN, Bandung. There are 9 activity aspects surveyed, for instant to avail the policy of safety from their chairman, safety management, education and training, emergency aids planning, safety consultancy, accident information, safety analysis, safety devices, safety and occupational health. The surveying undertaken by filling the questioner that containing of 9 activity aspects and 20 samples of employees. The safety evaluation results' of the operation personnel in TRIGA-2000 P3TN are good implemented by both the operators and supervisors should be improve and attention need to provide the equipment's. The education and training especially for safety refreshment must be performing

Results of a survey on accident and safety analysis codes, benchmarks, verification and validation methods

International Nuclear Information System (INIS)

Lee, A.G.; Wilkin, G.B.

1996-03-01

During the 'Workshop on R and D needs' at the 3rd Meeting of the International Group on Research Reactors (IGORR-III), the participants agreed that it would be useful to compile a survey of the computer codes and nuclear data libraries used in accident and safety analyses for research reactors and the methods various organizations use to verify and validate their codes and libraries. Five organizations, Atomic Energy of Canada Limited (AECL, Canada), China Institute of Atomic Energy (CIAE, People's Republic of China), Japan Atomic Energy Research Institute (JAERI, Japan), Oak Ridge National Laboratories (ORNL, USA), and Siemens (Germany) responded to the survey. The results of the survey are compiled in this report. (author) 36 refs., 3 tabs

Safety Gear Decontamination Practices Among Florida Firefighters: Analysis of a Text-Based Survey Methodology.

Science.gov (United States)

Moore, Kevin J; Koru-Sengul, Tulay; Alvarez, Armando; Schaefer-Solle, Natasha; Harrison, Tyler R; Kobetz, Erin N; Caban-Martinez, Alberto J

2018-02-01

Despite the National Fire Protection Association (NFPA) 1851 Personal Protective Equipment Care and Maintenance guidelines, little is known about the routine cleaning of firefighter bunker gear. In collaboration with a large Florida firefighter union, a mobile phone text survey was administered, which included eight questions in an item logic format. In total, 250 firefighters participated in the survey of which 65% reported cleaning their bunker gear in the past 12 months. Approximately 32% ( n = 52) indicated that they had above average confidence in gear cleaning procedures. Arriving at a fire incident response was a significant predictor of gear cleaning in the 12 months preceding survey administration. Using mobile phone-based texting for periodic queries on adherence to NFPA cleaning guidelines and safety message distribution may assist firefighters to increase decontamination procedure frequency.

Patient safety in surgical environments: Cross-countries comparison of psychometric properties and results of the Norwegian version of the Hospital Survey on Patient Safety

Directory of Open Access Journals (Sweden)

Nortvedt Monica W

2010-09-01

Full Text Available Abstract Background How hospital health care personnel perceive safety climate has been assessed in several countries by using the Hospital Survey on Patient Safety (HSOPS. Few studies have examined safety climate factors in surgical departments per se. This study examined the psychometric properties of a Norwegian translation of the HSOPS and also compared safety climate factors from a surgical setting to hospitals in the United States, the Netherlands and Norway. Methods This survey included 575 surgical personnel in Haukeland University Hospital in Bergen, an 1100-bed tertiary hospital in western Norway: surgeons, operating theatre nurses, anaesthesiologists, nurse anaesthetists and ancillary personnel. Of these, 358 returned the HSOPS, resulting in a 62% response rate. We used factor analysis to examine the applicability of the HSOPS factor structure in operating theatre settings. We also performed psychometric analysis for internal consistency and construct validity. In addition, we compared the percent of average positive responds of the patient safety climate factors with results of the US HSOPS 2010 comparative data base report. Results The professions differed in their perception of patient safety climate, with anaesthesia personnel having the highest mean scores. Factor analysis using the original 12-factor model of the HSOPS resulted in low reliability scores (r = 0.6 for two factors: "adequate staffing" and "organizational learning and continuous improvement". For the remaining factors, reliability was ≥ 0.7. Reliability scores improved to r = 0.8 by combining the factors "organizational learning and continuous improvement" and "feedback and communication about error" into one six-item factor, supporting an 11-factor model. The inter-item correlations were found satisfactory. Conclusions The psychometric properties of the questionnaire need further investigations to be regarded as reliable in surgical environments. The operating

Technology, safety and costs of decommissioning a reference boiling water reactor power station. Volume 2. Appendices. Technical report, September 1977-October 1979

International Nuclear Information System (INIS)

Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

1980-06-01

Technology, safety and cost information is given for the conceptual decommissioning of a large (1100MWe) boiling water reactor (BWR) power station. Three approaches to decommissioning, immediate dismantlement, safe storage with deferred dismantlement and entombment, were studied to obtain comparisons between costs, occupational radiation doses, potential dose to the public and other safety impacts. It also shows the sensitivity of decommissioning safety and costs to the power rating of a BWR in the range of 200 to 1100 MWE. This volume contains the appendices

Technology, safety and costs of decommissioning a reference boiling water reactor power station. Volume 2. Appendices. Technical report, September 1977-October 1979

Energy Technology Data Exchange (ETDEWEB)

Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

1980-06-01

Technology, safety and cost information is given for the conceptual decommissioning of a large (1100MWe) boiling water reactor (BWR) power station. Three approaches to decommissioning, immediate dismantlement, safe storage with deferred dismantlement and entombment, were studied to obtain comparisons between costs, occupational radiation doses, potential dose to the public and other safety impacts. It also shows the sensitivity of decommissioning safety and costs to the power rating of a BWR in the range of 200 to 1100 MWE. This volume contains the appendices.

Efficacy and safety of tolvaptan in heart failure patients with sustained volume overload despite the use of conventional diuretics: a phase III open-label study.

Science.gov (United States)

Fukunami, Masatake; Matsuzaki, Masunori; Hori, Masatsugu; Izumi, Tohru

2011-12-01

Volume overload is a common complication associated with heart failure (HF) and is recommended to be treated with loop or thiazide diuretics. However, use of diuretics can cause serum electrolyte imbalances and diuretic resistance. Tolvaptan, a selective, oral, non-peptide vasopressin V2-receptor antagonist, offers a new option for treating volume overload in HF patients. The aim of this study was to investigate the efficacy and safety of tolvaptan in Japanese HF patients with volume overload. Fifty-one HF patients with volume overload, despite using conventional diuretics, were treated with 15 mg/day tolvaptan for 7 days. If the response was insufficient at Day 7, tolvaptan was continued for a further 7 days at either 15 mg/day or 30 mg/day. Outcomes included changes in body weight, symptoms and safety parameters. Thirty-six patients discontinued treatment within 7 days, therefore 15 patients entered the second phase of treatment. In two patients, tolvaptan was increased to 30 mg/day after 7 days. Body weight was reduced on Day 7 (-1.95 ± 1.98 kg; n = 41) and Day 14 (-2.35 ± 1.44 kg; n = 11, 15 mg/day). Symptoms of volume overload, including lower limb edema, pulmonary congestion, jugular venous distention and hepatomegaly, were improved by tolvaptan treatment for 7 or 14 days. Neither tolvaptan increased the incidence of severe or serious adverse events when administered for 7-14 days. This study confirms the efficacy and safety of 15 mg/day tolvaptan for 7-14 days in Japanese HF patients with volume overload despite conventional diuretics.

Patient safety in primary care: a survey of general practitioners in the Netherlands

Directory of Open Access Journals (Sweden)

Wensing Michel

2010-01-01

Full Text Available Abstract Background Primary care encompasses many different clinical domains and patient groups, which means that patient safety in primary care may be equally broad. Previous research on safety in primary care has focused on medication safety and incident reporting. In this study, the views of general practitioners (GPs on patient safety were examined. Methods A web-based survey of a sample of GPs was undertaken. The items were derived from aspects of patient safety issues identified in a prior interview study. The questionnaire used 10 clinical cases and 15 potential risk factors to explore GPs' views on patient safety. Results A total of 68 GPs responded (51.5% response rate. None of the clinical cases was uniformly judged as particularly safe or unsafe by the GPs. Cases judged to be unsafe by a majority of the GPs concerned either the maintenance of medical records or prescription and monitoring of medication. Cases which only a few GPs judged as unsafe concerned hygiene, the diagnostic process, prevention and communication. The risk factors most frequently judged to constitute a threat to patient safety were a poor doctor-patient relationship, insufficient continuing education on the part of the GP and a patient age over 75 years. Language barriers and polypharmacy also scored high. Deviation from evidence-based guidelines and patient privacy in the reception/waiting room were not perceived as risk factors by most of the GPs. Conclusion The views of GPs on safety and risk in primary care did not completely match those presented in published papers and policy documents. The GPs in the present study judged a broader range of factors than in previously published research on patient safety in primary care, including a poor doctor-patient relationship, to pose a potential threat to patient safety. Other risk factors such as infection prevention, deviation from guidelines and incident reporting were judged to be less relevant than by policy

Patient safety in primary care: a survey of general practitioners in The Netherlands.

Science.gov (United States)

Gaal, Sander; Verstappen, Wim; Wensing, Michel

2010-01-21

Primary care encompasses many different clinical domains and patient groups, which means that patient safety in primary care may be equally broad. Previous research on safety in primary care has focused on medication safety and incident reporting. In this study, the views of general practitioners (GPs) on patient safety were examined. A web-based survey of a sample of GPs was undertaken. The items were derived from aspects of patient safety issues identified in a prior interview study. The questionnaire used 10 clinical cases and 15 potential risk factors to explore GPs' views on patient safety. A total of 68 GPs responded (51.5% response rate). None of the clinical cases was uniformly judged as particularly safe or unsafe by the GPs. Cases judged to be unsafe by a majority of the GPs concerned either the maintenance of medical records or prescription and monitoring of medication. Cases which only a few GPs judged as unsafe concerned hygiene, the diagnostic process, prevention and communication. The risk factors most frequently judged to constitute a threat to patient safety were a poor doctor-patient relationship, insufficient continuing education on the part of the GP and a patient age over 75 years. Language barriers and polypharmacy also scored high. Deviation from evidence-based guidelines and patient privacy in the reception/waiting room were not perceived as risk factors by most of the GPs. The views of GPs on safety and risk in primary care did not completely match those presented in published papers and policy documents. The GPs in the present study judged a broader range of factors than in previously published research on patient safety in primary care, including a poor doctor-patient relationship, to pose a potential threat to patient safety. Other risk factors such as infection prevention, deviation from guidelines and incident reporting were judged to be less relevant than by policy makers.

Safety report concerning the reactor Pegase - volume 1 - Description of the installation - volume 2 - Safety of the installations; Rapport de surete du reacteur pegase - tome 1 - Description des installations - tome 2 - Surete des installations

Energy Technology Data Exchange (ETDEWEB)

Lacour, J. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Legoin, P. [S.E.M. Hispano-Suiza, 92 - Colombes (France)

1964-07-01

In the first volume: This report is a description of the reactor Pegase, given with a view to examine the safety of the installations. The Cadarache site at which they are situated is briefly described, in particular because of the consequences on the techniques employed for building Pegase. A description is also given of the original aspects of the reactor. The independent loops which are designed for full-scale testing of fuel elements used in natural uranium-gas-graphite reactor systems are described in this report, together with their operational and control equipment. In the second volume: In the present report are examined the accidents which could cause damage to the Pegase reactor installation. Among possible causes of accidents considered are the seismicity of the region, an excessive power excursion of the reactor and a fracture in the sealing of an independent loop. Although all possible precautions have been taken to offset the effects of such accidents, their ultimate consequences are considered here. The importance is stressed of the security action and regulations which, added to the precautions taken for the construction, ensure the safety of the installations. (authors) [French] Dans le volume 1: Ce rapport est une description du reacteur Pegase, afin d'examiner la surete des installations. Le site de CADARACHE ou elles sont situees, a ete sommairement decrit, en particulier, a cause des consequences sur les techniques mises en oeuvre pour la realisation de Pegase. Nous nous sommes egalement attache a decrire les aspects originaux du reacteur. Les boucles autonomes destinees a tester en vraie grandeur des elements combustibles de la filiere uranium naturel graphite-gaz, ainsi que leurs dispositifs de controle et d'exploitation, figurent egalement dans ce rapport. Dans le volume 2: Dans le present rapport, nous examinons des accidents pouvant endommager des installations du reacteur Pegase. Les origines d'accidents examines

Safety report concerning the reactor Pegase - volume 1 - Description of the installation - volume 2 - Safety of the installations; Rapport de surete du reacteur pegase - tome 1 - Description des installations - tome 2 - Surete des installations

Energy Technology Data Exchange (ETDEWEB)

Lacour, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Legoin, P [S.E.M. Hispano-Suiza, 92 - Colombes (France)

1964-07-01

In the first volume: This report is a description of the reactor Pegase, given with a view to examine the safety of the installations. The Cadarache site at which they are situated is briefly described, in particular because of the consequences on the techniques employed for building Pegase. A description is also given of the original aspects of the reactor. The independent loops which are designed for full-scale testing of fuel elements used in natural uranium-gas-graphite reactor systems are described in this report, together with their operational and control equipment. In the second volume: In the present report are examined the accidents which could cause damage to the Pegase reactor installation. Among possible causes of accidents considered are the seismicity of the region, an excessive power excursion of the reactor and a fracture in the sealing of an independent loop. Although all possible precautions have been taken to offset the effects of such accidents, their ultimate consequences are considered here. The importance is stressed of the security action and regulations which, added to the precautions taken for the construction, ensure the safety of the installations. (authors) [French] Dans le volume 1: Ce rapport est une description du reacteur Pegase, afin d'examiner la surete des installations. Le site de CADARACHE ou elles sont situees, a ete sommairement decrit, en particulier, a cause des consequences sur les techniques mises en oeuvre pour la realisation de Pegase. Nous nous sommes egalement attache a decrire les aspects originaux du reacteur. Les boucles autonomes destinees a tester en vraie grandeur des elements combustibles de la filiere uranium naturel graphite-gaz, ainsi que leurs dispositifs de controle et d'exploitation, figurent egalement dans ce rapport. Dans le volume 2: Dans le present rapport, nous examinons des accidents pouvant endommager des installations du reacteur Pegase. Les origines d'accidents examines comprennent la seismicite

Trainee Knowledge of Imaging Appropriateness and Safety: Results of a Series of Surveys From a Large Academic Medical Center.

Science.gov (United States)

Hollingsworth, Thaddeus D; Duszak, Richard; Vijayasarathi, Arvind; Gelbard, Rondi B; Mullins, Mark E

2017-10-31

In order to provide high quality care to their patients and utilize imaging most judiciously, physician trainees should possess a working knowledge of appropriate use, radiation dose, and safety. Prior work has suggested knowledge gaps in similar areas. We aimed to evaluate the knowledge of imaging appropriateness, radiation dose, and MRI and contrast safety of physician trainees across a variety of specialties. Between May 2016 and January 2017, three online surveys were distributed to all interns, residents, and fellows in ACGME accredited training programs at a large academic institution over two academic years. Response rates to three surveys ranged from 17.2% (218 of 1266) for MRI and contrast material safety, 19.1% (242 of 1266) for imaging appropriateness, to19.9% (246 of 1238) for radiation dose. Overall 72% (509 of 706) of survey respondents reported regularly ordering diagnostic imaging examinations, but fewer than half (47.8%; 470 of 984) could correctly estimate radiation dose across four commonly performed imaging studies. Only one third (34%; 167 of 488) of trainees chose appropriate imaging in scenarios involving pregnant patients. Trainee post-graduate year was not significantly correlated with overall radiation safety scores, and no significant difference was found between radiation safety or appropriate imaging scores of those who participated in a medical school radiology elective vs. those who did not. A total of 84% (57 of 68) of radiology trainees and 43% (269 of 630) of non-radiology trainees considered their knowledge adequate but that correlated only weakly correlated to actual knowledge scores (pimaging safety exist among many trainees. In order to enhance the value of imaging at the population level, further work is needed to assess the most appropriate method and stage of training to address these knowledge gaps. Copyright © 2017 Elsevier Inc. All rights reserved.

Survey and analysis of radiation safety management systems at medical institutions. Initial report. Radiation protection supervisor, radiation safety organization, and education and training

International Nuclear Information System (INIS)

Ohba, Hisateru; Ogasawara, Katsuhiko; Aburano, Tamio

2005-01-01

In this study, a questionnaire survey was carried out to determine the actual situation of radiation safety management systems in Japanese medical institutions with nuclear medicine facilities. The questionnaire consisted of questions concerning the Radiation Protection Supervisor license, safety management organizations, and problems related to education and training in safety management. Analysis was conducted according to region, type of establishment, and number of beds. The overall response rate was 60%, and no significant difference in response rate was found among regions. Medical institutions that performed nuclear medicine practices without a radiologist participating accounted for 10% of the total. Medical institutions where nurses gave patients intravenous injections of radiopharmaceuticals as part of the nuclear medicine practices accounted for 28% of the total. Of these medical institutions, 59% provided education and training in safety management for nurses. The rate of acquisition of Radiation Protection Supervisor licenses was approximately 70% for radiological technologists and approximately 20% for physicians (regional difference, p=0.02). The rate of medical institutions with safety management organizations was 71% of the total. Among the medical institutions (n=208) without safety management organizations, approximately 56% had 300 beds or fewer. In addition, it became clear that 35% of quasi-public organizations and 44% of private organizations did not provide education and training in safety management (p<0.001, according to establishment). (author)

Status of safety issues at licensed power plants: TMI Action Plan requirements; unresolved safety issues; generic safety issues; other multiplant action issues

International Nuclear Information System (INIS)

1993-12-01

As part of ongoing US Nuclear Regulatory Commission (NRC) efforts to ensure the quality and accountability of safety issue information, the NRC established a program for publishing an annual report on the status of licensee implementation and NRC verification of safety issues in major NRC requirements areas. This information was initially compiled and reported in three NUREG-series volumes. Volume 1, published in March 1991, addressed the status of Three Mile Island (TMI) Action Plan Requirements. Volume 2, published in May 1991, addressed the status of unresolved safety issues (USIs). Volume 3, published in June 1991, addressed the implementation and verification status of generic safety issues (GSIs). The first annual supplement, which combined these volumes into a single report and presented updated information as of September 30, 1991, was published in December 1991. The second annual supplement, which provided updated information as of September 30, 1992, was published in December 1992. Supplement 2 also provided the status of licensee implementation and NRC verification of other multiplant action (MPA) issues not related to TMI Action Plan requirements, USIs, or GSIs. This third annual NUREG report, Supplement 3, presents updated information as of September 30, 1993. This report gives a comprehensive description of the implementation and verification status of TMI Action Plan requirements, safety issues designated as USIs, GSIs, and other MPAs that have been resolved and involve implementation of an action or actions by licensees. This report makes the information available to other interested parties, including the public. Additionally, this report serves as a follow-on to NUREG-0933, ''A Prioritization of Generic Safety Issues,'' which tracks safety issues until requirements are approved for imposition at licensed plants or until the NRC issues a request for action by licensees

Safeguarding the User - Developing a Multimodal Design for Surveying and Raising Internet Safety and Security Awareness

DEFF Research Database (Denmark)

Gjedde, Lisa; Sharp, Robin; Andersen, Preben

2009-01-01

Internet safety and security for the user is an issue of great importance for the successful implementation of ICT, but since it is a complex field, with a specialist vocabulary that cannot immediately be understood by the common user, it is difficult to survey the field. The user may not underst......Internet safety and security for the user is an issue of great importance for the successful implementation of ICT, but since it is a complex field, with a specialist vocabulary that cannot immediately be understood by the common user, it is difficult to survey the field. The user may...... describes an ICT-based research method that combines a verbal mode of inquiry with a visual mode employing illustrations, animations and simulations to provide the user with a multimodal media experience. The rationale for this is that we are working in a complex technical field with a specialist vocabulary...

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

A survey of dynamic methodologies for probabilistic safety assessment of nuclear power plants

International Nuclear Information System (INIS)

Aldemir, Tunc

2013-01-01

Highlights: ► Dynamic methodologies for probabilistic safety assessment (PSA) are surveyed. ► These methodologies overcome the limitations of the traditional approach to PSA. ► They are suitable for PSA using a best estimate plus uncertainty approach. ► They are highly computation intensive and produce very large number of scenarios. ► Use of scenario clustering can assist the analysis of the results. -- Abstract: Dynamic methodologies for probabilistic safety assessment (PSA) are defined as those which use a time-dependent phenomenological model of system evolution along with its stochastic behavior to account for possible dependencies between failure events. Over the past 30 years, numerous concerns have been raised in the literature regarding the capability of the traditional static modeling approaches such as the event-tree/fault-tree methodology to adequately account for the impact of process/hardware/software/firmware/human interactions on the stochastic system behavior. A survey of the types of dynamic PSA methodologies proposed to date is presented, as well as a brief summary of an example application for the PSA modeling of a digital feedwater control system of an operating pressurized water reactor. The use of dynamic methodologies for PSA modeling of passive components and phenomenological uncertainties are also discussed.

Perception of risks and safety. Results of the October 2000 survey

International Nuclear Information System (INIS)

2000-01-01

After having recalled the themes present in the survey on the perception of risks and safety as far as nuclear energy is concerned, this report proposes an analysis of the obtained results. It discusses the current general concerns, the perception of risks (confidence, truth), the opinions on the scientific expertise, the perception of technological and natural risks for the environment (hazardous installations, demand for environmental acceptability of installations, disasters), the opinions on nuclear activities (image, actors, information, control of these activities), the possibility of a nuclear accident and the implemented countermeasures, and finally the risks associated with radon

Perception of risks and safety. Results of the October 1999 survey

International Nuclear Information System (INIS)

1999-01-01

After having recalled the themes present in the survey on the perception of risks and safety as far as nuclear energy is concerned, this report proposes an analysis of the obtained results. It discusses the current general concerns, the perception of risks (demand, confidence, truth), the opinions on scientific expertise, the opinions on nuclear activities (image, actors, information, control of these activities), the issue of radioactive wastes and mining residues (perceived risk depending on the site vicinity, time scale, site management), the possibility of a nuclear accident and the implemented countermeasures, and finally the risks concerning food

Proceedings of the twenty-fourth water reactor safety information meeting. Volume 3: PRA and HRA; Probabilistic seismic hazard assessment and seismic siting criteria

Energy Technology Data Exchange (ETDEWEB)

Monteleone, S. [comp.] [Brookhaven National Lab., Upton, NY (United States)

1997-02-01

This three-volume report contains papers presented at the Twenty-Fourth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, October 21--23, 1996. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from Czech Republic, Finland, France, Japan, Norway, Russia and United Kingdom. This volume is divided into the following sections: PRA and HRA and probabilistic seismic hazard assessment and seismic siting criteria. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

Proceedings of the twenty-fourth water reactor safety information meeting. Volume 3: PRA and HRA; Probabilistic seismic hazard assessment and seismic siting criteria

International Nuclear Information System (INIS)

Monteleone, S.

1997-02-01

This three-volume report contains papers presented at the Twenty-Fourth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, October 21--23, 1996. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from Czech Republic, Finland, France, Japan, Norway, Russia and United Kingdom. This volume is divided into the following sections: PRA and HRA and probabilistic seismic hazard assessment and seismic siting criteria. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database

NASA System Safety Handbook. Volume 1; System Safety Framework and Concepts for Implementation

Science.gov (United States)

Dezfuli, Homayoon; Benjamin, Allan; Everett, Christopher; Smith, Curtis; Stamatelatos, Michael; Youngblood, Robert

2011-01-01

System safety assessment is defined in NPR 8715.3C, NASA General Safety Program Requirements as a disciplined, systematic approach to the analysis of risks resulting from hazards that can affect humans, the environment, and mission assets. Achievement of the highest practicable degree of system safety is one of NASA's highest priorities. Traditionally, system safety assessment at NASA and elsewhere has focused on the application of a set of safety analysis tools to identify safety risks and formulate effective controls.1 Familiar tools used for this purpose include various forms of hazard analyses, failure modes and effects analyses, and probabilistic safety assessment (commonly also referred to as probabilistic risk assessment (PRA)). In the past, it has been assumed that to show that a system is safe, it is sufficient to provide assurance that the process for identifying the hazards has been as comprehensive as possible and that each identified hazard has one or more associated controls. The NASA Aerospace Safety Advisory Panel (ASAP) has made several statements in its annual reports supporting a more holistic approach. In 2006, it recommended that "... a comprehensive risk assessment, communication and acceptance process be implemented to ensure that overall launch risk is considered in an integrated and consistent manner." In 2009, it advocated for "... a process for using a risk-informed design approach to produce a design that is optimally and sufficiently safe." As a rationale for the latter advocacy, it stated that "... the ASAP applauds switching to a performance-based approach because it emphasizes early risk identification to guide designs, thus enabling creative design approaches that might be more efficient, safer, or both." For purposes of this preface, it is worth mentioning three areas where the handbook emphasizes a more holistic type of thinking. First, the handbook takes the position that it is important to not just focus on risk on an individual

The role of informal dimensions of safety in high-volume organisational routines: an ethnographic study of test results handling in UK general practice.

Science.gov (United States)

Grant, Suzanne; Checkland, Katherine; Bowie, Paul; Guthrie, Bruce

2017-04-27

The handling of laboratory, imaging and other test results in UK general practice is a high-volume organisational routine that is both complex and high risk. Previous research in this area has focused on errors and harm, but a complementary approach is to better understand how safety is achieved in everyday practice. This paper ethnographically examines the role of informal dimensions of test results handling routines in the achievement of safety in UK general practice and how these findings can best be developed for wider application by policymakers and practitioners. Non-participant observation was conducted of high-volume organisational routines across eight UK general practices with diverse organisational characteristics. Sixty-two semi-structured interviews were also conducted with the key practice staff alongside the analysis of relevant documents. While formal results handling routines were described similarly across the eight study practices, the everyday structure of how the routine should be enacted in practice was informally understood. Results handling safety took a range of local forms depending on how different aspects of safety were prioritised, with practices varying in terms of how they balanced thoroughness (i.e. ensuring the high-quality management of results by the most appropriate clinician) and efficiency (i.e. timely management of results) depending on a range of factors (e.g. practice history, team composition). Each approach adopted created its own potential risks, with demands for thoroughness reducing productivity and demands for efficiency reducing handling quality. Irrespective of the practice-level approach adopted, staff also regularly varied what they did for individual patients depending on the specific context (e.g. type of result, patient circumstances). General practices variably prioritised a legitimate range of results handling safety processes and outcomes, each with differing strengths and trade-offs. Future safety

Efficacy and safety of tolvaptan in heart failure patients with volume overload despite the standard treatment with conventional diuretics: a phase III, randomized, double-blind, placebo-controlled study (QUEST study).

Science.gov (United States)

Matsuzaki, Masunori; Hori, Masatsugu; Izumi, Tohru; Fukunami, Masatake

2011-12-01

Diuretics are recommended to treat volume overload with heart failure (HF), however, they may cause serum electrolyte imbalance, limiting their use. Moreover, patients with advanced HF could poorly respond to these diuretics. In this study, we evaluated the efficacy and safety of Tolvaptan, a competitive vasopressin V2-receptor antagonist developed as a new drug to treat volume overload in HF patients. A phase III, multicenter, randomized, double-blind, placebo-controlled parallel study was performed to assess the efficacy and safety of tolvaptan in treating HF patients with volume overload despite the use of conventional diuretics. One hundred and ten patients were randomly assigned to receive either placebo or 15 mg/day tolvaptan for 7 consecutive days. Compared with placebo, tolvaptan administered for 7 days significantly reduced body weight and improved symptoms associated with volume overload. The safety profile of tolvaptan was considered acceptable for clinical use with minimal adverse effects. Tolvaptan reduced volume overload and improved congestive symptoms associated with HF by a potent water diuresis (aquaresis).

Proceedings of the US Nuclear Regulatory Commission twentieth water reactor safety information meeting; Volume 2, Severe accident research, Thermal hydraulics

Energy Technology Data Exchange (ETDEWEB)

Weiss, A.J. [comp.] [Brookhaven National Lab., Upton, NY (United States)

1993-03-01

This three-volume report contains papers presented at the Twentieth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 21--23, 1992. The papers describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included 10 different papers presented by researchersfrom CEC, China, Finland, France, Germany, Japan, Spain and Taiwan. Selected papers have been processed separately for inclusion in the Energy Science and Technology Database.

Hospital survey on patient safety culture: psychometric analysis on a Scottish sample.

Science.gov (United States)

Sarac, Cakil; Flin, Rhona; Mearns, Kathryn; Jackson, Jeanette

2011-10-01

To investigate the psychometric properties of the Hospital Survey on Patient Safety Culture on a Scottish NHS data set. The data were collected from 1969 clinical staff (estimated 22% response rate) from one acute hospital from each of seven Scottish Health boards. Using a split-half validation technique, the data were randomly split; an exploratory factor analysis was conducted on the calibration data set, and confirmatory factor analyses were conducted on the validation data set to investigate and check the original US model fit in a Scottish sample. Following the split-half validation technique, exploratory factor analysis results showed a 10-factor optimal measurement model. The confirmatory factor analyses were then performed to compare the model fit of two competing models (10-factor alternative model vs 12-factor original model). An S-B scaled χ(2) square difference test demonstrated that the original 12-factor model performed significantly better in a Scottish sample. Furthermore, reliability analyses of each component yielded satisfactory results. The mean scores on the climate dimensions in the Scottish sample were comparable with those found in other European countries. This study provided evidence that the original 12-factor structure of the Hospital Survey on Patient Safety Culture scale has been replicated in this Scottish sample. Therefore, no modifications are required to the original 12-factor model, which is suggested for use, since it would allow researchers the possibility of cross-national comparisons.

Evaluation of patient safety culture among Malaysian retail pharmacists: results of a self-reported survey

Directory of Open Access Journals (Sweden)

Sivanandy P

2016-07-01

Full Text Available Palanisamy Sivanandy,1 Mari Kannan Maharajan,1 Kingston Rajiah,1 Tan Tyng Wei,2 Tan Wee Loon,2 Lim Chong Yee2 1Department of Pharmacy Practice, School of Pharmacy, 2School of Pharmacy, International Medical University, Wilayah Persekutuan Kuala Lumpur, Malaysia Background: Patient safety is a major public health issue, and the knowledge, skills, and experience of health professionals are very much essential for improving patient safety. Patient safety and medication error are very much associated. Pharmacists play a significant role in patient safety. The function of pharmacists in the medication use process is very different from medical and nursing colleagues. Medication dispensing accuracy is a vital element to ensure the safety and quality of medication use.Objective: To evaluate the attitude and perception of the pharmacist toward patient safety in retail pharmacies setup in Malaysia.Methods: A Pharmacy Survey on Patient Safety Culture questionnaire was used to assess patient safety culture, developed by the Agency for Healthcare Research and Quality, and the convenience sampling method was adopted.Results: The overall positive response rate ranged from 31.20% to 87.43%, and the average positive response rate was found to be 67%. Among all the eleven domains pertaining to patient safety culture, the scores of “staff training and skills” were less. Communication openness, and patient counseling are common, but not practiced regularly in the Malaysian retail pharmacy setup compared with those in USA. The overall perception of patient safety of an acceptable level in the current retail pharmacy setup.Conclusion: The study revealed that staff training, skills, communication in patient counseling, and communication across shifts and about mistakes are less in current retail pharmacy setup. The overall perception of patient safety should be improved by educating the pharmacists about the significance and essential of patient safety. Keywords

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

International Nuclear Information System (INIS)

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

2016-01-01

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

Survey of fish impingement at power plants in the United States. Volume III. Estuaries and coastal waters

International Nuclear Information System (INIS)

Stupka, R.C.; Sharma, R.K.

1977-03-01

Impingement of fish at cooling-water intakes of 32 power plants, located on estuaries and coastal waters has been surveyed and data are presented. Descriptions of site, plant, and intake design and operation are provided. Reports in this volume summarize impingement data for individual plants in tabular and histogram formats. Information was available from differing sources such as the utilities themselves, public documents, regulatory agencies, and others. Thus, the extent of detail in the reports varies greatly from plant to plant. Histogram preparation involved an extrapolation procedure that has inadequacies. The reader is cautioned in the use of information presented in this volume to determine intake-design acceptability or intensity of impacts on ecosystems. No conclusions are presented herein; data comparisons are made in Volume IV

Survey of fish impingement at power plants in the United States. Volume III. Estuaries and coastal waters

Energy Technology Data Exchange (ETDEWEB)

Stupka, Richard C.; Sharma, Rajendra K.

1977-03-01

Impingement of fish at cooling-water intakes of 32 power plants, located on estuaries and coastal waters has been surveyed and data are presented. Descriptions of site, plant, and intake design and operation are provided. Reports in this volume summarize impingement data for individual plants in tabular and histogram formats. Information was available from differing sources such as the utilities themselves, public documents, regulatory agencies, and others. Thus, the extent of detail in the reports varies greatly from plant to plant. Histogram preparation involved an extrapolation procedure that has inadequacies. The reader is cautioned in the use of information presented in this volume to determine intake-design acceptability or intensity of impacts on ecosystems. No conclusions are presented herein; data comparisons are made in Volume IV.

Safety and reliability. V. 1. Proceedings

International Nuclear Information System (INIS)

Soares, C.G.

1997-01-01

Proceedings of a 1997 conference on industrial safety and reliability are reported. The first volume looks at risk management, probabilistic safety assessment and management styles in various industrial settings, including nuclear power plants. The second volume addresses safety and reliability in the offshore and transport industries, focusing on the role of staff training and appropriate maintenance routines to effectively reduce accidents and outages. (UK)

Organisational and extraorganisational determinants of volume of service delivery by English community pharmacies: a cross-sectional survey and secondary data analysis

Science.gov (United States)

Hann, Mark; Schafheutle, Ellen I; Bradley, Fay; Elvey, Rebecca; Wagner, Andrew; Halsall, Devina; Hassell, Karen

2017-01-01

Objectives This study aimed to identify the organisational and extraorganisational factors associated with existing variation in the volume of services delivered by community pharmacies. Design and setting Linear and ordered logistic regression of linked national data from secondary sources—community pharmacy activity, socioeconomic and health need datasets—and primary data from a questionnaire survey of community pharmacies in nine diverse geographical areas in England. Outcome measures Annual dispensing volume; annual volume of medicines use reviews (MURs). Results National dataset (n=10 454 pharmacies): greater dispensing volume was significantly associated with pharmacy ownership type (large chains>independents>supermarkets), greater deprivation, higher local prevalence of cardiovascular disease and depression, older people (aged >75 years) and infants (aged 0–4 years) but lower prevalence of mental health conditions. Greater volume of MURs was significantly associated with pharmacy ownership type (large chains/supermarkets>>independents), greater dispensing volume, and lower disease prevalence. Survey dataset (n=285 pharmacies; response=34.6%): greater dispensing volume was significantly associated with staffing, skill-mix, organisational culture, years open and greater deprivation. Greater MUR volume was significantly associated with pharmacy ownership type (large chains/supermarkets>>independents), greater dispensing volume, weekly opening hours and lower asthma prevalence. Conclusions Organisational and extraorganisational factors were found to impact differently on dispensing volume and MUR activity, the latter being driven more by corporate ownership than population need. While levels of staffing and skill-mix were associated with dispensing volume, they did not influence MUR activity. Despite recent changes to the contractual framework, the existing fee-for-service reimbursement may therefore not be the most appropriate for the delivery of

Does Employee Safety Matter for Patients Too? Employee Safety Climate and Patient Safety Culture in Health Care.

Science.gov (United States)

Mohr, David C; Eaton, Jennifer Lipkowitz; McPhaul, Kathleen M; Hodgson, Michael J

2015-04-22

We examined relationships between employee safety climate and patient safety culture. Because employee safety may be a precondition for the development of patient safety, we hypothesized that employee safety culture would be strongly and positively related to patient safety culture. An employee safety climate survey was administered in 2010 and assessed employees' views and experiences of safety for employees. The patient safety survey administered in 2011 assessed the safety culture for patients. We performed Pearson correlations and multiple regression analysis to examine the relationships between a composite measure of employee safety with subdimensions of patient safety culture. The regression models controlled for size, geographic characteristics, and teaching affiliation. Analyses were conducted at the group level using data from 132 medical centers. Higher employee safety climate composite scores were positively associated with all 9 patient safety culture measures examined. Standardized multivariate regression coefficients ranged from 0.44 to 0.64. Medical facilities where staff have more positive perceptions of health care workplace safety climate tended to have more positive assessments of patient safety culture. This suggests that patient safety culture and employee safety climate could be mutually reinforcing, such that investments and improvements in one domain positively impacts the other. Further research is needed to better understand the nexus between health care employee and patient safety to generalize and act upon findings.

Impact of the Global Food Safety Initiative on Food Safety Worldwide: Statistical Analysis of a Survey of International Food Processors.

Science.gov (United States)

Crandall, Philip G; Mauromoustakos, Andy; O'Bryan, Corliss A; Thompson, Kevin C; Yiannas, Frank; Bridges, Kerry; Francois, Catherine

2017-10-01

In 2000, the Consumer Goods Forum established the Global Food Safety Initiative (GFSI) to increase the safety of the world's food supply and to harmonize food safety regulations worldwide. In 2013, a university research team in conjunction with Diversey Consulting (Sealed Air), the Consumer Goods Forum, and officers of GFSI solicited input from more than 15,000 GFSI-certified food producers worldwide to determine whether GFSI certification had lived up to these expectations. A total of 828 usable questionnaires were analyzed, representing about 2,300 food manufacturing facilities and food suppliers in 21 countries, mainly across Western Europe, Australia, New Zealand, and North America. Nearly 90% of these certified suppliers perceived GFSI as being beneficial for addressing their food safety concerns, and respondents were eight times more likely to repeat the certification process knowing what it entailed. Nearly three-quarters (74%) of these food manufacturers would choose to go through the certification process again even if certification were not required by one of their current retail customers. Important drivers for becoming GFSI certified included continuing to do business with an existing customer, starting to do business with new customer, reducing the number of third-party food safety audits, and continuing improvement of their food safety program. Although 50% or fewer respondents stated that they saw actual increases in sales, customers, suppliers, or employees, significantly more companies agreed than disagreed that there was an increase in these key performance indicators in the year following GFSI certification. A majority of respondents (81%) agreed that there was a substantial investment in staff time since certification, and 50% agreed there was a significant capital investment. This survey is the largest and most representative of global food manufacturers conducted to date.

Development of computerized stocktaking system in mine surveying for ore mineral volume calculation in covered storehouses

Science.gov (United States)

Valdman, V. V.; Gridnev, S. O.

2017-10-01

The article examines into the vital issues of measuring and calculating the raw stock volumes in covered storehouses at mining and processing plants. The authors bring out two state-of-the-art high-technology solutions: 1 - to use the ground-based laser scanning system (the method is reasonably accurate and dependable, but costly and time consuming; it also requires the stoppage of works in the storehouse); 2 - to use the fundamentally new computerized stocktaking system in mine surveying for the ore mineral volume calculation, based on the profile digital images. These images are obtained via vertical projection of the laser plane onto the surface of the stored raw materials.

Status of safety issues at licensed power plants: TMI Action Plan requirements, unresolved safety issues, generic safety issues, other multiplant action issues. Supplement 4

International Nuclear Information System (INIS)

1994-12-01

As part of ongoing US Nuclear Regulatory Commission (NRC) efforts to ensure the quality and accountability of safety issue information, the NRC established a program for publishing an annual report on the status of licensee implementation and NRC verification of safety issues in major NRC requirements areas. This information was initially compiled and reported in three NUREG-series volumes. Volume 1, published in March 1991, addressed the status of Three Mile Island (TMI) Action Plan Requirements. Volume 2, published in May 1991, addressed the status of unresolved safety issues (USIs). Volume 3, published in June 1991, addressed the implementation and verification status of generic safety issues (GSIs). The first annual supplement, which combined these volumes into a single report and presented updated information as of September 30, 1991, was published in December 1991. The second annual supplement, which provided updated information as of September 30, 1992, was published in December 1992. Supplement 2 also provided the status of licensee implementation and NRC verification of other multiplant action (MPA) issues not related to TMI Action Plan requirements, USIs, or GSIs. Supplement 3 gives status as of September 30, 1993. This annual report, Supplement 4, presents updated information as of September 30, 1994. This report gives a comprehensive description of the implementation and verification status of TMI Action Plan requirements, safety issues designated as USIs, GSIs, and other MPAs that have been resolved and involve implementation of an action or actions by licensees. This report makes the information available to other interested parties, including the public. Additionally, this report serves as a follow-on to NUREG-0933, ''A Prioritization of Generic Safety Issues,'' which tracks safety issues until requirements are approved for imposition at licensed plants or until the NRC issues a request for action by licensees

School Survey on Crime and Safety (SSOCS): 2015-16. Public-Use Data File User's Manual. NCES 2018-107

Science.gov (United States)

Jackson, Michael; Diliberti, Melissa; Kemp, Jana; Hummel, Steven; Cox, Christina; Gbondo-Tugbawa, Komba; Simon, Dillon

2018-01-01

The School Survey on Crime and Safety (SSOCS) is managed by the National Center for Education Statistics (NCES) within the Institute of Education Sciences of the U.S. Department of Education. SSOCS collects extensive crime and safety data from principals and administrators of public schools in the United States. Data from this collection can be…

The impact of nurse working hours on patient safety culture: a cross-national survey including Japan, the United States and Chinese Taiwan using the Hospital Survey on Patient Safety Culture.

Science.gov (United States)

Wu, Yinghui; Fujita, Shigeru; Seto, Kanako; Ito, Shinya; Matsumoto, Kunichika; Huang, Chiu-Chin; Hasegawa, Tomonori

2013-10-07

A positive patient safety culture (PSC) is one of the most critical components to improve healthcare quality and safety. The Hospital Survey on Patient Safety Culture (HSOPS), developed by the US Agency for Healthcare Research and Quality, has been used to assess PSC in 31 countries. However, little is known about the impact of nurse working hours on PSC. We hypothesized that long nurse working hours would deteriorate PSC, and that the deterioration patterns would vary between countries. Moreover, the common trends observed in Japan, the US and Chinese Taiwan may be useful to improve PSC in other countries. The purpose of this study was to clarify the impact of long nurse working hours on PSC in Japan, the US, and Chinese Taiwan using HSOPS. The HSOPS questionnaire measures 12 sub-dimensions of PSC, with higher scores indicating a more positive PSC. Odds ratios (ORs) were calculated using a generalized linear mixed model to evaluate the impact of working hours on PSC outcome measures (patient safety grade and number of events reported). Tukey's test and Cohen's d values were used to verify the relationships between nurse working hours and the 12 sub-dimensions of PSC. Nurses working ≥60 h/week in Japan and the US had a significantly lower OR for patient safety grade than those working working ≥40 h/week had a significantly higher OR for the number of events reported. The mean score on 'staffing' was significantly lower in the ≥60-h group than in the Japan and Chinese Taiwan. Patient safety grade deteriorated and the number of events reported increased with long working hours. Among the 12 sub-dimensions of PSC, long working hours had an impact on 'staffing' and 'teamwork within units' in Japan, the US and Chinese Taiwan.

Perception of risks and safety. Results of the November 2002 survey

International Nuclear Information System (INIS)

2002-01-01

After having recalled the themes present in the survey on the perception of risks and safety as far as nuclear energy is concerned, this report proposes an analysis of the obtained results. It discusses the current general concerns, the perception of risks (risks for the society, confidence in authorities, spoken truth), the opinions on the scientific expertise (role, opinion, confidence), the perception of technological and natural risks for the environment (hazardous installations, demand for environmental acceptability of installations, participation to information session, industrial and natural disasters), the opinions on nuclear activities (image, actors, information, control of these activities), and finally the possibility of a nuclear accident and the implemented countermeasures

Safety and environmental health handbook

Science.gov (United States)

,

1989-01-01

This Safety Handbook (445-1-H.) supplements the Geological Survey Safety Management Program objectives set forth in Survey Manual 445.1. Specifically, it provides a compact source of basic information to assist management and employees in preventing motor vehicle accidents, personal injuries, occupational diseases, fire, and other property damage or loss. All work situations incidental to the Geological Survey cannot be discussed in a handbook, and such complete coverage is not intended in this document. However, a wide range of subjects are covered in which a "common sense" approach to safety has been expressed. These subjects have been organized such that Chapters 1-5 address administrative issues, Chapters 6-12 address activities usually conducted within a facility, and Chapters 13-20 address field activities. No information contained in the Handbook is intended to alter any provision of any Federal law or executive order, Department of the Interior or Survey directive, or collective bargaining agreement. Questions or suggestions regarding the content of the Safety Handbook may be directed to the Survey Safety Manager, Administrative Division, Office of Facilities and Management Services, National Center, Reston, Virginia, Mail Stop 246. The previous edition of the Safety Handbook is superseded.

Viability Assessment Volume 2

International Nuclear Information System (INIS)

1998-01-01

This volume describes the major design features of the Monitored Geologic Repository. This document is not intended to provide an exhaustive, detailed description of the repository design. Rather, this document summarizes the major systems and primary elements of the design that are radiologically significant, and references the specific technical documents and design analyses wherein the details can be found. Not all portions of the design are at the same level of completeness. Highest priority has been given to assigning resources to advance the design of the Monitored Geologic Repository features that are important to radiological safety and/or waste isolation and for which there is no NRC licensing precedent. Those features that are important to radiological safety and/or waste isolation, but for which there is an NRC precedent, receive second priority. Systems and features that have no impact on radiological safety or waste isolation receive the lowest priority. This prioritization process, referred to as binning, is discussed in more detail in Section 2.3. Not every subject discussed in this volume is given equal treatment with regard to the level of detail provided. For example, less detail is provided for the surface facility design than for the subsurface and waste package designs. This different level of detail is intentional. Greater detail is provided for those functions, structures, systems, and components that play key roles with regard to protecting radiological health and safety and that are not common to existing nuclear facilities already licensed by NRC. A number of radiological subjects are not addressed in the VA, (e.g., environmental qualification of equipment). Environmental qualification of equipment and other radiological safety considerations will be addressed in the LA. Non-radiological safety considerations such as silica dust control and other occupational safety considerations are considered equally important but are not addressed in

Disease Risk Perception and Safety Practices: A Survey of Australian Flying Fox Rehabilitators.

Directory of Open Access Journals (Sweden)

Cecilia A Sánchez

2016-02-01

Full Text Available Interactions with flying foxes pose disease transmission risks to volunteer rehabilitators (carers who treat injured, ill, and orphaned bats. In particular, Australian bat lyssavirus (ABLV can be transmitted directly from flying foxes to humans in Australia. Personal protective equipment (PPE and rabies vaccination can be used to protect against lyssavirus infection. During May and June 2014, active Australian flying fox carers participated in an online survey (SOAR: Survey Of Australian flying fox Rehabilitators designed to gather demographic data, assess perceptions of disease risk, and explore safety practices. Responses to open-ended questions were analysed thematically. A logistic regression was performed to assess whether rehabilitators' gender, use of PPE, threat perception, and years of experience predicted variation in their odds of being bitten or scratched. Eligible responses were received from 122 rehabilitators located predominantly on the eastern coast of Australia. Eighty-four percent of respondents were female. Years of experience ranged from <1 to 30 years (median 5 years. Respondents were highly educated. All rehabilitators were vaccinated against rabies and 94% received a rabies titre check at least every two years. Sixty-three percent of carers did not perceive viruses in flying foxes as a potential threat to their health, yet 74% of carers reported using PPE when handling flying foxes. Eighty-three percent of rehabilitators had received a flying fox bite or scratch at some point during their career. Carers provide an important community service by rescuing and rehabilitating flying foxes. While rehabilitators in this study have many excellent safety practices, including a 100% vaccination rate against rabies, there is room for improvement in PPE use. We recommend 1 the establishment of an Australia-wide set of guidelines for safety when caring for bats and 2 that the responsible government agencies in Australia support

Survey and evaluation of inherent safety characteristics and passive safety systems for use in probabilistic safety analyses

International Nuclear Information System (INIS)

Wetzel, N.; Scharfe, A.

1998-01-01

The present report examines the possibilities and limits of a probabilistic safety analysis to evaluate passive safety systems and inherent safety characteristics. The inherent safety characteristics are based on physical principles, that together with the safety system lead to no damage. A probabilistic evaluation of the inherent safety characteristic is not made. An inventory of passive safety systems of accomplished nuclear power plant types in the Federal Republic of Germany was drawn up. The evaluation of the passive safety system in the analysis of the accomplished nuclear power plant types was examined. The analysis showed that the passive manner of working was always assumed to be successful. A probabilistic evaluation was not performed. The unavailability of the passive safety system was determined by the failure of active components which are necessary in order to activate the passive safety system. To evaluate the passive safety features in new concepts of nuclear power plants the AP600 from Westinghouse, the SBWR from General Electric and the SWR 600 from Siemens, were selected. Under these three reactor concepts, the SWR 600 is specially attractive because the safety features need no energy sources and instrumentation in this concept. First approaches for the assessment of the reliability of passively operating systems are summarized. Generally it can be established that the core melt frequency for the passive concepts AP600 and SBWR is advantageous in comparison to the probabilistic objectives from the European Pressurized Water Reactor (EPR). Under the passive concepts is the SWR 600 particularly interesting. In this concept the passive systems need no energy sources and instrumentation, and has active operational systems and active safety equipment. Siemens argues that with this concept the frequency of a core melt will be two orders of magnitude lower than for the conventional reactors. (orig.) [de

Nuclear power performance and safety. V.3. Safety and international co-operation

International Nuclear Information System (INIS)

1988-01-01

The International Conference on Nuclear Power Performance and Safety, organized by the International Atomic Energy Agency, was held at the Austria Centre Vienna (ACV) in Vienna, Austria, from 28 September to 2 October 1987. The objective of the Conference was to promote an exchange of worldwide information on the current trends in the performance and safety of nuclear power and its fuel cycle, and to take a forward look at the expectations and objectives for the 1990s. This objective was accomplished through presentation and discussion of about 200 papers at the Conference. Almost 500 participants and observers from 40 countries and 12 organizations discussed three major questions which were posed as the focus of this Conference: (1) What are the current trends and major issues with regard to performance and safety of nuclear power, the nuclear fuel cycle and radioactive waste management? (2) What steps are being taken or need to be taken to resolve outstanding issues in order to improve the performance of nuclear power with assured safety? (3) What performance objectives and achievements can be anticipated for the 1990s? All presentations of this Conference were divided into six volumes. This is Volume 3 which is devoted to the problems of safety and international cooperation. All presentations of Volume 3 were divided into four sessions as follows: the need for safety in nuclear power programmes (4 papers); international cooperation in nuclear safety (6 papers); technical aspects in plant safety (7 papers); approaches to safety (3 papers). A separate abstract was prepared for each of these 20 papers. Refs, figs and tabs

Practice gaps in patient safety among dermatology residents and their teachers: a survey study of dermatology residents.

Science.gov (United States)

Swary, Jillian Havey; Stratman, Erik J

2014-07-01

Curriculum and role modeling adjustments are necessary to address patient safety gaps occurring during dermatology residency. To identify the source of clinical practices among dermatology residents that affect patient safety and determine the best approach for overcoming gaps in knowledge and practice patterns that contribute to these practices. A survey-based study, performed at a national medical dermatology meeting in Itasca, Illinois, in 2012, included 142 dermatology residents from 44 residency programs in the United States and Canada. Self-reported rates of dermatology residents committing errors, identifying local systems errors, and identifying poor patient safety role modeling. Of surveyed dermatology residents, 45.2% have failed to report needle-stick injuries incurred during procedures, 82.8% reported cutting and pasting a previous author's patient history information into a medical record without confirming its validity, 96.7% reported right-left body part mislabeling during examination or biopsy, and 29.4% reported not incorporating clinical photographs of lesions sampled for biopsy in the medical record at their institution. Residents variably perform a purposeful pause ("time-out") when indicated to confirm patient, procedure, and site before biopsy, with 20.0% always doing so. In addition, 59.7% of residents work with at least 1 attending physician who intimidates the residents, reducing the likelihood of reporting safety issues they witness. Finally, 78.3% have witnessed attending physicians purposefully disregarding required safety steps. Our data reinforce the need for modified curricula, systems, and teacher development to reduce injuries, improve communication with patients and between physicians, residents, and other members of the health care team, and create an environment free of intimidation.

High School and Beyond. 1980 Senior Coort. Third-Follow-Up (1986). Data File User's Manual. Volume II: Survey Instruments. Contractor Report.

Science.gov (United States)

Sebring, Penny; And Others

Survey instruments used in the collection of data for the High School and Beyond base year (1980) through the third follow-up surveys (1986) are provided as Volume II of a user's manual for the senior cohort data file. The complete user's manual is designed to provide the extensive documentation necessary for using the cohort data files. Copies of…

A survey of food safety training in small food manufacturers.

Science.gov (United States)

Worsfold, Denise

2005-08-01

A survey of food safety training was conducted in small food manufacturing firms in South Wales. Structured interviews with managers were used to collect information on the extent and level of food hygiene and HACCP training and the manager's perceptions of and attitude towards training. All the businesses surveyed had undertaken some hygiene training. Hygiene induction programmes were often unstructured and generally unrecorded. Low-risk production workers were usually trained on the job whilst high-care production staff were trained in hygiene to Level 1. Part-time and temporary staff received less training than full-timers. Regular refresher training was undertaken by less than half of the sample. None of the businesses made use of National Vocational Qualification (NVQ) qualifications. Over half of the managers/senior staff had undertaken higher levels of hygiene training and half had attended a HACCP course. Managers trained the workforce to operate the HACCP system. Formal training-related activities were generally only found in the larger businesses. Few of the manufacturers had made use of training consultants. Managers held positive attitudes towards training but most regarded it as operating expense rather than an investment. Resource poverty, in terms of time and money was perceived to be a major inhibiting factor to continual, systematic training.

Leadership Actions to Improve Nuclear Safety Culture

International Nuclear Information System (INIS)

Clewett, L.K.

2016-01-01

The challenge many leaders face is how to effectively implement and then utilise the results of Safety Culture surveys. Bruce Power has recently successfully implemented changes to the Safety Culture survey process including how corrective actions were identified and implemented. The actions taken in response to the latest survey have proven effective with step change performance noted. Nuclear Safety is a core value for Bruce Power. Nuclear Safety at Bruce Power is based on the following four pillars: reactor safety, industrial safety, radiological safety and environmental safety. Processes and practices are in place to achieve a healthy Nuclear Safety Culture within Bruce Power such that nuclear safety is the overriding priority. This governance is based on industry leading practices which monitor, asses and take action to drive continual improvements in the Nuclear Safety Culture within Bruce Power.

SU-D-201-07: A Survey of Radiation Oncology Residents’ Training and Preparedness to Lead Patient Safety Programs in Clinics

International Nuclear Information System (INIS)

Spraker, M; Nyflot, M; Ford, E; Kane, G; Zeng, J; Hendrickson, K

2016-01-01

Purpose: Safety and quality has garnered increased attention in radiation oncology, and physicians and physicists are ideal leaders of clinical patient safety programs. However, it is not clear whether residency programs incorporate formal patient safety training and adequately equip residents to assume this leadership role. A national survey was conducted to evaluate medical and physics residents’ exposure to safety topics and their confidence with the skills required to lead clinical safety programs. Methods: Radiation oncology residents were identified in collaboration with ARRO and AAPM. The survey was released in February 2016 via email using REDCap. This included questions about exposure to safety topics, confidence leading safety programs, and interest in training opportunities (i.e. workshops). Residents rated their exposure, skills, and confidence on 4 or 5-point scales. Medical and physics residents responses were compared using chi-square tests. Results: Responses were collected from 56 of 248 (22%) physics and 139 of 690 (20%) medical residents. More than two thirds of all residents had no or only informal exposure to incident learning systems (ILS), root cause analysis (RCA), failure mode and effects analysis (FMEA), and the concept of human factors engineering (HFE). Likewise, 63% of residents had not heard of RO-ILS. Response distributions were similar, however more physics residents had formal exposure to FMEA (p<0.0001) and felt they were adequately trained to lead FMEAs in clinic (p<0.001) than medical residents. Only 36% of residents felt their patient safety training was adequate, and 58% felt more training would benefit their education. Conclusion: These results demonstrate that, despite increasing desire for patient safety training, medical and physics residents’ exposure to relevant concepts is low. Physics residents had more exposure to FMEA than medical residents, and were more confident in leading FMEA. This suggests that increasing

SU-D-201-07: A Survey of Radiation Oncology Residents’ Training and Preparedness to Lead Patient Safety Programs in Clinics

Energy Technology Data Exchange (ETDEWEB)

Spraker, M; Nyflot, M; Ford, E; Kane, G; Zeng, J; Hendrickson, K [University of Washington, Seattle, WA (United States)

2016-06-15

Purpose: Safety and quality has garnered increased attention in radiation oncology, and physicians and physicists are ideal leaders of clinical patient safety programs. However, it is not clear whether residency programs incorporate formal patient safety training and adequately equip residents to assume this leadership role. A national survey was conducted to evaluate medical and physics residents’ exposure to safety topics and their confidence with the skills required to lead clinical safety programs. Methods: Radiation oncology residents were identified in collaboration with ARRO and AAPM. The survey was released in February 2016 via email using REDCap. This included questions about exposure to safety topics, confidence leading safety programs, and interest in training opportunities (i.e. workshops). Residents rated their exposure, skills, and confidence on 4 or 5-point scales. Medical and physics residents responses were compared using chi-square tests. Results: Responses were collected from 56 of 248 (22%) physics and 139 of 690 (20%) medical residents. More than two thirds of all residents had no or only informal exposure to incident learning systems (ILS), root cause analysis (RCA), failure mode and effects analysis (FMEA), and the concept of human factors engineering (HFE). Likewise, 63% of residents had not heard of RO-ILS. Response distributions were similar, however more physics residents had formal exposure to FMEA (p<0.0001) and felt they were adequately trained to lead FMEAs in clinic (p<0.001) than medical residents. Only 36% of residents felt their patient safety training was adequate, and 58% felt more training would benefit their education. Conclusion: These results demonstrate that, despite increasing desire for patient safety training, medical and physics residents’ exposure to relevant concepts is low. Physics residents had more exposure to FMEA than medical residents, and were more confident in leading FMEA. This suggests that increasing

Organisational and extraorganisational determinants of volume of service delivery by English community pharmacies: a cross-sectional survey and secondary data analysis.

Science.gov (United States)

Hann, Mark; Schafheutle, Ellen I; Bradley, Fay; Elvey, Rebecca; Wagner, Andrew; Halsall, Devina; Hassell, Karen; Jacobs, Sally

2017-10-10

This study aimed to identify the organisational and extraorganisational factors associated with existing variation in the volume of services delivered by community pharmacies. Linear and ordered logistic regression of linked national data from secondary sources-community pharmacy activity, socioeconomic and health need datasets-and primary data from a questionnaire survey of community pharmacies in nine diverse geographical areas in England. Annual dispensing volume; annual volume of medicines use reviews (MURs). National dataset (n=10 454 pharmacies): greater dispensing volume was significantly associated with pharmacy ownership type (large chains>independents>supermarkets), greater deprivation, higher local prevalence of cardiovascular disease and depression, older people (aged >75 years) and infants (aged 0-4 years) but lower prevalence of mental health conditions. Greater volume of MURs was significantly associated with pharmacy ownership type (large chains/supermarkets>independents), greater dispensing volume, and lower disease prevalence.Survey dataset (n=285 pharmacies; response=34.6%): greater dispensing volume was significantly associated with staffing, skill-mix, organisational culture, years open and greater deprivation. Greater MUR volume was significantly associated with pharmacy ownership type (large chains/supermarkets>independents), greater dispensing volume, weekly opening hours and lower asthma prevalence. Organisational and extraorganisational factors were found to impact differently on dispensing volume and MUR activity, the latter being driven more by corporate ownership than population need. While levels of staffing and skill-mix were associated with dispensing volume, they did not influence MUR activity. Despite recent changes to the contractual framework, the existing fee-for-service reimbursement may therefore not be the most appropriate for the delivery of cognitive (rather than supply) services, still appearing to incentivise quantity

Inventory of Federal energy-related environment and safety research for FY 1979. Volume II. Project listings and indexes

Energy Technology Data Exchange (ETDEWEB)

None

1980-12-01

This volume contains summaries of FY 1979 government-sponsored environment and safety research related to energy arranged by log number, which groups the projects by reporting agency. The log number is a unique number assigned to each project from a block of numbers set aside for each contributing agency. Information elements included in the summary listings are project title, principal investigators, research organization, project number, contract number, supporting organization, funding level, related energy sources with numbers indicating percentages of effort devoted to each, and R and D categories. A brief description of each project is given, and this is followed by subject index terms that were assigned for computer searching and for generating the printed subject index in the back of this volume.

Inventory of Federal energy-related environment and safety research for FY 1979. Volume II. Project listings and indexes

International Nuclear Information System (INIS)

1980-12-01

This volume contains summaries of FY 1979 government-sponsored environment and safety research related to energy arranged by log number, which groups the projects by reporting agency. The log number is a unique number assigned to each project from a block of numbers set aside for each contributing agency. Information elements included in the summary listings are project title, principal investigators, research organization, project number, contract number, supporting organization, funding level, related energy sources with numbers indicating percentages of effort devoted to each, and R and D categories. A brief description of each project is given, and this is followed by subject index terms that were assigned for computer searching and for generating the printed subject index in the back of this volume

Patient safety and nursing implication: Survey in Catalan hospitals.

Science.gov (United States)

Freixas Sala, Núria; Monistrol Ruano, Olga; Espuñes Vendrell, Jordi; Sallés Creus, Montserrat; Gallardo González, Mónica; Ramón Cantón, Carme; Bueno Domínguez, María José; Llinas Vidal, Montserrat; Campo Osaba, María Antonia

This study aims to describe the implementation of the patient safety (PS) programs in catalan hospitals and to analyze the level of nursing involvement. Multicenter cross-sectional study. To obtain the data two questionnaires were developed; one addressed to the hospital direction and another to the nurse executive in PS. The survey was distributed during 2013 to the 65 acute care hospitals in Catalonia. The questionnaire was answered by 43 nursing directors and 40 nurse executive in PS. 93% of the hospitals responded that they had a PS Program and 81.4% used a specific scoreboard with PS indicators. The referent of the hospital in PS was a nurse in 55.8% of the centres. 92.5% had a system of notification of adverse effects with an annual average of 190.3 notifications. In 86% of the centres had a nurse involved in the PS program but only in the 16% of the centres the nurse dedication was at full-time. The nurse respondents evaluate the degree of implementation of the PBS program with a note of approved and they propound as improvement increase the staff dedicated to the PS and specific academic training in PS. The degree of implementation of programs for patient safety is high in Catalan acute hospitals, while the organizational structure is highly diverse. In more than half of the hospitals the PS referent was a nurse, confirming the nurse involvement in the PS programs. Copyright © 2016 Elsevier España, S.L.U. All rights reserved.

Nuclear Safety: Volume 29, No. 3: Technical progress review

Energy Technology Data Exchange (ETDEWEB)

Silver, E G [ed.

1988-07-01

Nuclear Safety is a review journal that covers significant development in the field of nuclear safety. Its scope included the analysis and control of hazards associated with nuclear energy, operations involving fissionable materials and the products of nuclear fission and their effects on the environment. Primary emphasis is on safety in reactor design, construction, and operation; however, the safety aspects of the entire fuel cycle, including fuel fabrication, spent-fuel processing, nuclear waste disposal, handling of radioisotopes, and environmental effects of these operations, are also treated. Individual papers have been cataloged separately.

Survey about pedestrian safety and attitudes toward automated traffic enforcement in Washington, D.C.

Science.gov (United States)

Cicchino, Jessica B; Wells, Joann K; McCartt, Anne T

2014-01-01

Pedestrians represent more than one third of all traffic deaths in Washington, D.C. The District plans to expand its long-standing automated traffic enforcement program in 2013 from speed and red light cameras to cameras to enforce pedestrian right-of-way laws at crosswalks and stop sign laws. This study collected information on the opinions, behaviors, and knowledge of D.C. residents related to camera enforcement and pedestrian safety issues. A telephone survey of 801 adult D.C. residents was conducted in November 2012 with approximately equal numbers of respondents in each of D.C.'s eight wards. Quotas were used to ensure that the sample was representative of the demographic characteristics of adults in each ward. For analyses combining responses across the wards, data were weighted to correspond with the demographic characteristics of adults in the city. Most respondents believed that drivers speeding, running red lights, running stop signs, and not stopping for pedestrians are serious threats to their safety. Respondents strongly supported the speed and red light camera programs, with 76 percent of respondents favoring speed cameras and 87 percent favoring red light cameras. Support was more limited for the camera enforcement that was not yet in place at the time of the survey, with 50 percent of respondents favoring stop sign cameras and 47 percent of respondents favoring crosswalk cameras. Twenty-four percent of respondents had not driven a car in D.C. in the past month, and higher proportions of these nondrivers favored speed cameras (90%), stop sign cameras (67%), and crosswalk cameras (59%) than respondents who drove in D.C. in the past month. Respondents who supported camera enforcement cited safety as their main reason. More than 9 in 10 respondents knew that D.C. law requires drivers to stop for pedestrians crossing the street in marked crosswalks at intersections without traffic signals and midblock, but only 54 percent knew that drivers must stop for

Patient safety culture in out-of-hours primary care services in the Netherlands: a cross-sectional survey.

Science.gov (United States)

Smits, Marleen; Keizer, Ellen; Giesen, Paul; Deilkås, Ellen Catharina Tveter; Hofoss, Dag; Bondevik, Gunnar Tschudi

2018-03-01

To examine patient safety culture in Dutch out-of-hours primary care using the safety attitudes questionnaire (SAQ) which includes five factors: teamwork climate, safety climate, job satisfaction, perceptions of management and communication openness. Cross-sectional observational study using an anonymous web-survey. Setting Sixteen out-of-hours general practitioner (GP) cooperatives and two call centers in the Netherlands. Subjects Primary healthcare providers in out-of-hours services. Main outcome measures Mean scores on patient safety culture factors; association between patient safety culture and profession, gender, age, and working experience. Overall response rate was 43%. A total of 784 respondents were included; mainly GPs (N = 470) and triage nurses (N = 189). The healthcare providers were most positive about teamwork climate and job satisfaction, and less about communication openness and safety climate. The largest variation between clinics was found on safety climate; the lowest on teamwork climate. Triage nurses scored significantly higher than GPs on each of the five patient safety factors. Older healthcare providers scored significantly higher than younger on safety climate and perceptions of management. More working experience was positively related to higher teamwork climate and communication openness. Gender was not associated with any of the patient safety factors. Our study showed that healthcare providers perceive patient safety culture in Dutch GP cooperatives positively, but there are differences related to the respondents' profession, age and working experience. Recommendations for future studies are to examine reasons for these differences, to examine the effects of interventions to improve safety culture and to make international comparisons of safety culture. Key Points Creating a positive patient safety culture is assumed to be a prerequisite for quality and safety. We found that: • healthcare providers in Dutch GP cooperatives

Status of safety issues at licensed power plants

International Nuclear Information System (INIS)

1991-06-01

As part of ongoing US Nuclear Regulatory Commission (NRC) efforts to ensure the quality and accountability of safety issue information, a program has been established whereby an annual NUREG report will be published on the status of licensee implementation and NRC verification of safety issues in major NRC requirement areas. This report, the third volume of a three-volume series, addresses the status of generic safety issues (GSIs) at licensed plants. Volume 1 addressed the status of Three Mile Island Action Plan requirements and was published in March 1991. Volume 2 addressed the status of implementation and verification of unresolved safety issues and was published in May 1991. The annual NUREG report will combine these three areas in a single volume to be published in late 1991. The data contained in these NUREG reports are a product of the NRC's Safety Issues Management System (SIMS) database, which is maintained by the Project Management Staff in the Office of Nuclear Reactor Regulation and by NRC regional personnel. The purpose of this report is to provide a comprehensive description of the status of implementation and verification of the 34 GSIs and sub-issues that have been resolved by the NRC and involve implementation of an action or actions by licensees. This NUREG report also serves as a follow-on to NUREG-0933, ''A Prioritization of Generic Safety Issues,'' which tracks safety issues up until a request for action by licensees is issued by NRC. 3 figs., 6 tabs

Appalachian States Compact Low-Level Radioactive Waste management survey, 1987

International Nuclear Information System (INIS)

Singh, K.N.

1989-03-01

Since the enactment of the Low-Level Radioactive Waste Disposal Act in February 1988, the Commonwealth of Pennsylvania has undertaken major steps to develop a Low-Level Radioactive Waste (LLRW) Disposal Facility within its borders for the exclusive use of radioactive material licensees in the Appalachian States Compact. In order to adequately plan for the design and development of that facility, it is essential to obtain accurate data on LLRW being generated in the Compact. To that end, the Division of Nuclear Safety of the Pennsylvania Bureau of Radiation Protection (BRP) conducted a survey to determine volume and activity of LLRW shipped and stored in 1987 by the licensees in the Appalachian States Compact. The 1986 LLRW survey included licensees in Pennsylvania and Maryland, while surveys conducted prior to 1986 involved only Pennsylvania licensees. So this is the first survey conducted by BRP that has included all four states of the Compact

Twenty-fifth water reactor safety information meeting: Proceedings. Volume 3: Thermal hydraulic research and codes; Digital instrumentation and control; Structural performance

International Nuclear Information System (INIS)

Monteleone, S.

1998-04-01

This three-volume report contains papers presented at the conference. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Japan, Norway, and Russia. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. This volume contains the following: (1) thermal hydraulic research and codes; (2) digital instrumentation and control; (3) structural performance

Twenty-third water reactor safety information meeting. Volume 3, structural and seismic engineering, primary systems integrity, equipment operability and aging, ECCS strainer blockage research and regulatory issues

Energy Technology Data Exchange (ETDEWEB)

Monteleone, S. [comp.] [Brookhaven National Lab., Upton, NY (United States)

1996-03-01

This three-volume report contains papers presented at the Twenty- Third Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, October 23-25, 1995. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Italy, Japan, Norway, Russia, Sweden, and Switzerland. This document, Volume 3, presents topics in Structural & Seismic Engineering, Primary Systems Integrity, Equipment Operability and Aging, and ECCS Strainer Blockage Research & Regulatory Issues. Individual papers have been cataloged separately.

Twenty-third water reactor safety information meeting. Volume 3, structural and seismic engineering, primary systems integrity, equipment operability and aging, ECCS strainer blockage research and regulatory issues

International Nuclear Information System (INIS)

Monteleone, S.

1996-03-01

This three-volume report contains papers presented at the Twenty- Third Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, October 23-25, 1995. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Italy, Japan, Norway, Russia, Sweden, and Switzerland. This document, Volume 3, presents topics in Structural ampersand Seismic Engineering, Primary Systems Integrity, Equipment Operability and Aging, and ECCS Strainer Blockage Research ampersand Regulatory Issues. Individual papers have been cataloged separately

Safety culture in the maternity unit of hospitals in Ilam province, Iran: a census survey using HSOPSC tool.

Science.gov (United States)

Akbari, Nahid; Malek, Marzieh; Ebrahimi, Parvin; Haghani, Hamid; Aazami, Sanaz

2017-01-01

Improving quality of maternal care as well as patients' safety are two important issues in health-care service. Therefore, this study aimed to assess the culture of patient safety at maternity units. This cross-sectional study was conducted among staffs working at maternity units in seven hospitals of Ilam city, Iran. The staffs included in this study were gynecologists and midwifes working in different positions including matron, supervisors, head of departments and staffs. Data were collected using the Hospital Survey on Patient Safety Culture (HSOPSC). This study indicated that 59.1% of participants reported fair level of overall perceptions of safety and 67.1% declared that no event was reported during the past 12 months. The most positively perceived dimension of safety culture was teamwork within departments in view of managers (79.41) and personnel (81.10). However, the least positively perceived dimensions of safety culture was staffing levels. The current study revealed areas of strength (teamwork within departments) and weakness (staffing, punitive responses to error) among managers and personnel. In addition, we found that staffs in Ilam's hospitals accept the patient safety culture in maternity units, but, still are far away from excellent culture of patient safety. Therefore, it is necessary to promote culture of patient's safety among professions working in the maternity units of Ilam's hospitals.

Internet safety education for youth: stakeholder perspectives.

Science.gov (United States)

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

2013-06-05

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

Intensive care unit nurses' perceptions of safety after a highly specific safety intervention.

Science.gov (United States)

Elder, N C; Brungs, S M; Nagy, M; Kudel, I; Render, M L

2008-02-01

It is unknown if successful changes in specific safety practices in the intensive care unit (ICU) generalize to broader concepts of patient safety by staff nurses. To explore perceptions of patient safety among nursing staff in ICUs following participation in a safety project that decreased hospital acquired infections. After implementation of practices that reduced catheter-related bloodstream infections in ICUs at four community hospitals, ICU nurses participated in focus groups to discuss patient safety. Audiotapes from the focus groups were transcribed, and two independent reviewers categorised the data which were triangulated with responses from selected questions of safety climate surveys and with the safety checklists used by management leadership on walk rounds. Thirty-three nurses attended eight focus groups; 92 nurses and managers completed safety climate surveys, and three separate leadership checklists were reviewed. In focus groups, nurses predominantly related patient safety to dangers in the physical environment (eg, bed rails, alarms, restraints, equipment, etc.) and to medication administration. These areas also represented 47% of checklist items from leadership walk rounds. Nurses most frequently mentioned self-initiated "double checking" as their main safety task. Focus-group participants and survey responses both noted inconsistency between management's verbal and written commitment compared with their day-to-day support of patient safety issues. ICU nurses who participated in a project to decrease hospital acquired infections did not generalize their experience to other aspects of patient safety or relate it to management's interest in patient safety. These findings are consistent with many adult learning theories, where self-initiated tasks, combined with immediate, but temporary problem-solving, are stronger learning forces than management-led activities with delayed feedback.

Management response plan for the Chemical Safety Vulnerability Working Group report. Volume 2

International Nuclear Information System (INIS)

1994-09-01

The Chemical Safety Vulnerability (CSV) Working Group was established to identify adverse conditions involving hazardous chemicals at DOE facilities that might result in fires or explosions, release of hazardous chemicals to the environment, or exposure of workers or the public to chemicals. A CSV Review was conducted in 146 facilities at 29 sites. Eight generic vulnerabilities were documented related to: abandoned chemicals and chemical residuals; past chemical spills and ground releases; characterization of legacy chemicals and wastes; disposition of legacy chemicals; storage facilities and conditions; condition of facilities and support systems; unanalyzed and unaddressed hazards; and inventory control and tracking. Weaknesses in five programmatic areas were also identified related to: management commitment and planning; chemical safety management programs; aging facilities that continue to operate; nonoperating facilities awaiting deactivation; and resource allocations. To address the facility-specific and site-specific vulnerabilities, responsible DOE and site-contractor line organizations have developed initial site response plans. These plans, presented as Volume 2 of this Management Response Plan, describe the actions needed to mitigate or eliminate the facility- and site-specific vulnerabilities identified by the CSV Working Group field verification teams. Initial site response plans are described for: Brookhaven National Lab., Hanford Site, Idaho National Engineering Lab., Lawrence Livermore National Lab., Los Alamos National Lab., Oak Ridge Reservation, Rocky Flats Plant, Sandia National Laboratories, and Savannah River Site

Survey by senior NRC management to obtain veiwpoints on the safety impact of regulatory activities from representative utilities operating and constructing nuclear power plants

International Nuclear Information System (INIS)

1981-08-01

A survey of licensee staff members representing the several organizational elements in different licensee corporate and plant staffs was conducted by senior NRC management to obtain licensee views on the potential safety consequences and impact of NRC regulatory activities. The comments received addressed the full scope of NRC activities and the negative impact of agency actions on licensee resources, staff performance, planning and scheduling, and organizational effectiveness. The findings of the survey is that the pace and nature of regulatory actions have created a potential safety problem which deserves further evaluation by the agency

Patient Safety Activity Under the Social Insurance Medical Fee Schedule in Japan: An Overview of the 2010 Nationwide Survey.

Science.gov (United States)

Hirose, Masahiro; Kawamura, Toshihiko; Igawa, Mikio; Imanaka, Yuichi

2017-11-16

Little is known about patient safety performance under the social insurance medical fee schedule in Japan. The Health Ministry in Japan introduced the preferential patient safety countermeasure fee (PPSCF) to promote patient safety in 2006 and revised the PPSCF system in 2010. This study aims to address the patient safety performance status at hospitals implementing the PPSCF. A nationwide questionnaire survey targeting 2674 hospitals with the PPSCF was performed in 2010 to 2011. The 627 participant hospitals were divided into the following three groups: 178 hospitals implementing PPSCF 1 with 400 beds or more (group A), 286 hospitals implementing PPSCF 1 with 399 beds or fewer (group B), and 163 hospitals implementing PPSCF 2 (group C). The mean numbers (standard errors) of patient safety managers were 1.45 (0.07) in group A, 1.12 (0.04) in group B, and 0.37 (0.12) in group C (P fee schedule in Japan.

Impact of resident duty hour limits on safety in the intensive care unit: a national survey of pediatric and neonatal intensivists.

Science.gov (United States)

Typpo, Katri V; Tcharmtchi, M Hossein; Thomas, Eric J; Kelly, P Adam; Castillo, Leticia D; Singh, Hardeep

2012-09-01

Resident duty-hour regulations potentially shift the workload from resident to attending physicians. We sought to understand how current or future regulatory changes might impact safety in academic pediatric and neonatal intensive care units. Web-based survey. U.S. academic pediatric and neonatal intensive care units. Attending pediatric and neonatal intensivists. We evaluated perceptions on four intensive care unit safety-related risk measures potentially affected by current duty-hour regulations: 1) attending physician and resident fatigue; 2) attending physician workload; 3) errors (self-reported rates by attending physicians or perceived resident error rates); and 4) safety culture. We also evaluated perceptions of how these risks would change with further duty-hour restrictions. We administered our survey between February and April 2010 to 688 eligible physicians, of whom 360 (52.3%) responded. Most believed that resident error rates were unchanged or worse (91.9%) and safety culture was unchanged or worse (84.4%) with current duty-hour regulations. Of respondents, 61.9% believed their own work-hours providing direct patient care increased and 55.8% believed they were more fatigued while providing direct patient care. Most (85.3%) perceived no increase in their own error rates currently, but in the scenario of further reduction in resident duty-hours, over half (53.3%) believed that safety culture would worsen and a significant proportion (40.3%) believed that their own error rates would increase. Pediatric intensivists do not perceive improved patient safety from current resident duty-hour restrictions. Policies to further restrict resident duty-hours should consider unintended consequences of worsening certain aspects of intensive care unit safety.

Comparing safety climate in naval aviation and hospitals: implications for improving patient safety.

Science.gov (United States)

Singer, Sara J; Rosen, Amy; Zhao, Shibei; Ciavarelli, Anthony P; Gaba, David M

2010-01-01

Evidence of variation in safety climate suggests the need for improvement among at least some hospitals. However, comparisons only among hospitals may underestimate the improvement required. Comparison of hospitals with analogous industries may provide a broader perspective on the safety status of our nation's hospitals. The purpose of this study was to compare safety climate among hospital workers with personnel from naval aviation, an organization that operates with high reliability despite intrinsically hazardous conditions. We surveyed a random sample of health care workers in 67 U.S. hospitals and, for generalizability, 30 veterans affairs hospitals using questions comparable with those posed at approximately the same time (2007) to a census of personnel from 35 squadrons of U.S. naval aviators. We received 13,841 (41%) completed surveys in U.S. hospitals, 5,511 (50%) in veterans affairs hospitals, and 14,854 (82%) among naval aviators. We examined differences in respondents' perceptions of safety climate at their institution overall and for 16 individual items. Safety climate was three times better on average among naval aviators than among hospital personnel. Naval aviators perceived a safer climate (up to seven times safer) than hospital personnel with respect to each of the 16 survey items. Compared with hospital managers, naval commanders perceived climate more like frontline personnel did. When contrasting naval aviators with hospital personnel working in comparably hazardous areas, safety climate discrepancies increased rather than decreased. One individual hospital performed as well as naval aviation on average, and at least one hospital outperformed the Navy benchmark for all but three individual survey items. Results suggest that hospitals have not sufficiently created a uniform priority of safety. However, if each hospital performed as well as the top-performing hospital in each area measured, hospitals could achieve safety climate levels comparable

Safety culture: a survey of the state-of-the-art

International Nuclear Information System (INIS)

Sorensen, J.N.

2002-01-01

This paper discusses the evolution of the term 'safety culture' and the perceived relationship between safety culture and safety of operations in nuclear power generation and other hazardous technologies. There is a widespread belief that safety culture is an important contributor to safety of operations. Empirical evidence that safety culture and other management and organizational factors influence operational safety is more readily available for the chemical process industry than for nuclear power plant operations. The commonly accepted attributes of safety culture include good organizational communications, good organizational learning, and senior management commitment to safety. Safety culture may be particularly important in reducing latent errors in complex, well-defended systems. The role of regulatory bodies in fostering strong safety cultures remains unclear, and additional work is required to define the essential attributes of safety culture and to identify reliable performance indicators

Twenty-fifth water reactor safety information meeting: Proceedings. Volume 1: Plenary sessions; Pressure vessel research; BWR strainer blockage and other generic safety issues; Environmentally assisted degradation of LWR components; Update on severe accident code improvements and applications

Energy Technology Data Exchange (ETDEWEB)

Monteleone, S. [comp.] [Brookhaven National Lab., Upton, NY (United States)

1998-03-01

This three-volume report contains papers presented at the conference. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Japan, Norway, and Russia. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. This volume contains the following information: (1) plenary sessions; (2) pressure vessel research; (3) BWR strainer blockage and other generic safety issues; (4) environmentally assisted degradation of LWR components; and (5) update on severe accident code improvements and applications. Selected papers have been indexed separately for inclusion in the Energy Science and Technology Database.

Twenty-fifth water reactor safety information meeting: Proceedings. Volume 1: Plenary sessions; Pressure vessel research; BWR strainer blockage and other generic safety issues; Environmentally assisted degradation of LWR components; Update on severe accident code improvements and applications

International Nuclear Information System (INIS)

Monteleone, S.

1998-03-01

This three-volume report contains papers presented at the conference. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Japan, Norway, and Russia. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. This volume contains the following information: (1) plenary sessions; (2) pressure vessel research; (3) BWR strainer blockage and other generic safety issues; (4) environmentally assisted degradation of LWR components; and (5) update on severe accident code improvements and applications. Selected papers have been indexed separately for inclusion in the Energy Science and Technology Database

The extent and influence of Asbestos Safety Awareness training among managers who had previously commissioned an asbestos survey in their workplace buildings

OpenAIRE

HICKEY, Jane; SAUNDERS, Jean; DAVERN, Peter

2015-01-01

A telephone survey was conducted among a sample of managers (n=30) in Ireland who had previously commissioned an asbestos survey in their workplace buildings. The aims of the telephone survey were to examine the extent to which managers had completed Asbestos Safety Awareness (ASA) training, and to assess how such training might influence (i) their instinctive thoughts on asbestos, and (ii) their approach to aspects of asbestos management within their buildings. Managers’ motivations for comm...

Report on transparency and nuclear safety - Saclay - 2012

International Nuclear Information System (INIS)

2013-01-01

This report presents the different nuclear base installations (INB) of the Saclay CEA centre, gives an overview of measures regarding safety within these installations (organisation, technical general arrangements, technical arrangements related to different risks, management of emergency situations, inspections, audits and second-level controls, arrangements and main events specific to the different installations and buildings) and of measures related to radiation protection (organisation and dosimetry results, internal dosimetry). It reports the significant events related to safety and radiation protection which occurred in 2012 and were declared to the ASN. It reports and comments the results of measurements of gaseous and liquid effluents, of their impact on the environment, and of surveys of the environment. The next part addresses the management of radioactive wastes which are warehoused on this site: arrangements aimed at limiting their volume, and at limiting their impact on health and on the environment, nature and quantities of warehoused wastes. Remarks and recommendations of the CHSCT are given

Civilian use transport of radioactive substances on public road. Volume 1: Shipment accreditation and approval requests. Guide Nr 7, Revision 2 of 15 February 2016. Volume 2: safety file of package models, European guide 'Package Design Safety Report'. Civilian use transport of radioactive packages or substances on public road. Volume 3: Compliance of package models not subject to accreditation. Guide Nr 7, Revision 7 of the 2015/11/13

International Nuclear Information System (INIS)

2016-01-01

After having recalled the regulatory context and sanctions susceptible to be applied, the first volume presents the accreditation process for a package model: file content, tests programme, safety file, certification studies, documents to be produced, accreditation prorogation request, accreditation extension or package model modifications, instruction delays. Some peculiar cases are described. Models of accreditation certificate are provided, and obligations concerning packaging design, fabrication, use and maintenance are briefly discussed. The second volume is a European technical guide which is intended to assist in the preparation of the Package Design Safety Report (PDSR) to demonstrate compliance of a package design for the transport of radioactive material with the regulatory requirements. It covers package designs requiring competent authority approval, and also covers package designs not requiring competent authority approval. In its first two chapters, this document provides a generic structure and contents of a PDSR which applies to all package types. The contents are described in a comprehensive way to cover all important aspects. Some of these aspects may not be applicable to specific package type and details can be found in the annexes which provide further guidance for the scope of the contents of a PDSR, specifically for each package type. The third volume presents recommendations made by the ASN for all stakeholders to guarantee the compliance to regulation of package models which are 'not submitted to competent authority approval'. After an indication and a comment of the regulatory context, it presents requirements to be applied for the design of those package models, and then describes and comments the structure and content of a safety file for such package models (generalities, authorised contents, packaging description, safety demonstration, receipt, use and maintenance instruction, management system). The last part presents the

Identifying organizational cultures that promote patient safety.

Science.gov (United States)

Singer, Sara J; Falwell, Alyson; Gaba, David M; Meterko, Mark; Rosen, Amy; Hartmann, Christine W; Baker, Laurence

2009-01-01

Safety climate refers to shared perceptions of what an organization is like with regard to safety, whereas safety culture refers to employees' fundamental ideology and orientation and explains why safety is pursued in the manner exhibited within a particular organization. Although research has sought to identify opportunities for improving safety outcomes by studying patterns of variation in safety climate, few empirical studies have examined the impact of organizational characteristics such as culture on hospital safety climate. This study explored how aspects of general organizational culture relate to hospital patient safety climate. In a stratified sample of 92 U.S. hospitals, we sampled 100% of senior managers and physicians and 10% of other hospital workers. The Patient Safety Climate in Healthcare Organizations and the Zammuto and Krakower organizational culture surveys measured safety climate and group, entrepreneurial, hierarchical, and production orientation of hospitals' culture, respectively. We administered safety climate surveys to 18,361 personnel and organizational culture surveys to a 5,894 random subsample between March 2004 and May 2005. Secondary data came from the 2004 American Hospital Association Annual Hospital Survey and Dun & Bradstreet. Hierarchical linear regressions assessed relationships between organizational culture and safety climate measures. Aspects of general organizational culture were strongly related to safety climate. A higher level of group culture correlated with a higher level of safety climate, but more hierarchical culture was associated with lower safety climate. Aspects of organizational culture accounted for more than threefold improvement in measures of model fit compared with models with controls alone. A mix of culture types, emphasizing group culture, seemed optimal for safety climate. Safety climate and organizational culture are positively related. Results support strategies that promote group orientation and

Tank Farms Technical Safety Requirements. Volume 1 and 2

International Nuclear Information System (INIS)

CASH, R.J.

2000-01-01

The Technical Safety Requirements (TSRs) define the acceptable conditions, safe boundaries, basis thereof, and controls to ensure safe operation during authorized activities, for facilities within the scope of the Tank Waste Remediation System (TWRS) Final Safety Analysis Report (FSAR)

Galaxy redshift surveys with sparse sampling

International Nuclear Information System (INIS)

Chiang, Chi-Ting; Wullstein, Philipp; Komatsu, Eiichiro; Jee, Inh; Jeong, Donghui; Blanc, Guillermo A.; Ciardullo, Robin; Gronwall, Caryl; Hagen, Alex; Schneider, Donald P.; Drory, Niv; Fabricius, Maximilian; Landriau, Martin; Finkelstein, Steven; Jogee, Shardha; Cooper, Erin Mentuch; Tuttle, Sarah; Gebhardt, Karl; Hill, Gary J.

2013-01-01

Survey observations of the three-dimensional locations of galaxies are a powerful approach to measure the distribution of matter in the universe, which can be used to learn about the nature of dark energy, physics of inflation, neutrino masses, etc. A competitive survey, however, requires a large volume (e.g., V survey ∼ 10Gpc 3 ) to be covered, and thus tends to be expensive. A ''sparse sampling'' method offers a more affordable solution to this problem: within a survey footprint covering a given survey volume, V survey , we observe only a fraction of the volume. The distribution of observed regions should be chosen such that their separation is smaller than the length scale corresponding to the wavenumber of interest. Then one can recover the power spectrum of galaxies with precision expected for a survey covering a volume of V survey (rather than the volume of the sum of observed regions) with the number density of galaxies given by the total number of observed galaxies divided by V survey (rather than the number density of galaxies within an observed region). We find that regularly-spaced sampling yields an unbiased power spectrum with no window function effect, and deviations from regularly-spaced sampling, which are unavoidable in realistic surveys, introduce calculable window function effects and increase the uncertainties of the recovered power spectrum. On the other hand, we show that the two-point correlation function (pair counting) is not affected by sparse sampling. While we discuss the sparse sampling method within the context of the forthcoming Hobby-Eberly Telescope Dark Energy Experiment, the method is general and can be applied to other galaxy surveys

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...

Abnormal condition and events analysis for instrumentation and control systems. Volume 2: Survey and evaluation of industry practices. Final report

International Nuclear Information System (INIS)

McKemy, S.; Marcelli, M.; Boehmer, N.; Crandall, D.

1996-01-01

The ACES Project was initiated to identify a cost-effective methodology for addressing abnormal conditions and events (ACES) in digital upgrades to nuclear power plant systems, as introduced by IEEE Standard 7-4.3.2-1993. Several methodologies and techniques currently in use in the defense, aerospace, and other communities for the assurance of digital safety systems were surveyed, and although several were shown to possess desirable qualities, none sufficiently met the needs of the nuclear power industry. This report describes a tailorable methodology for performing ACES analysis that is based on the more desirable aspects of the reviewed methodologies and techniques. The methodology is applicable to both safety- and non-safety-grade systems, addresses hardware, software, and system-level concerns, and can be applied in either a lifecycle or post-design timeframe. Employing this methodology for safety systems should facilitate the digital upgrade licensing process

Power plants and safety 1982

International Nuclear Information System (INIS)

1982-01-01

The papers of this volume deal with the whole range of safety issues from planning and construction to the operation of power plants, and discuss also issues like availability and safety of power plants, protective clothes and their incommodating effect, alternatives for rendering hot-water generators safe and the safety philosophy in steam turbine engineering. (HAG) [de

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.

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.

Speaking up about traditional and professionalism-related patient safety threats: a national survey of interns and residents.

Science.gov (United States)

Martinez, William; Lehmann, Lisa Soleymani; Thomas, Eric J; Etchegaray, Jason M; Shelburne, Julia T; Hickson, Gerald B; Brady, Donald W; Schleyer, Anneliese M; Best, Jennifer A; May, Natalie B; Bell, Sigall K

2017-11-01

Open communication between healthcare professionals about care concerns, also known as 'speaking up', is essential to patient safety. Compare interns' and residents' experiences, attitudes and factors associated with speaking up about traditional versus professionalism-related safety threats. Anonymous, cross-sectional survey. Six US academic medical centres, 2013-2014. 1800 medical and surgical interns and residents (47% responded). Attitudes about, barriers and facilitators for, and self-reported experience with speaking up. Likelihood of speaking up and the potential for patient harm in two vignettes. Safety Attitude Questionnaire (SAQ) teamwork and safety scales; and Speaking Up Climate for Patient Safety (SUC-Safe) and Speaking Up Climate for Professionalism (SUC-Prof) scales. Respondents more commonly observed unprofessional behaviour (75%, 628/837) than traditional safety threats (49%, 410/837); pbarrier to speaking up about unprofessional behaviour compared with traditional safety threats (58%, 482/837 vs 42%, 348/837; psafety vignette, even when they perceived high potential patient harm (20%, 49/251 vs 71%, 179/251; psafety vignette (OR 1.90, 99% CI 1.36 to 2.66 and 1.46, 1.02 to 2.09, respectively), while only a positive perception of SUC-Prof was associated with speaking up in the professionalism vignette (1.76, 1.23 to 2.50). Interns and residents commonly observed unprofessional behaviour yet were less likely to speak up about it compared with traditional safety threats even when they perceived high potential patient harm. Measuring SUC-Safe, and particularly SUC-Prof, may fill an existing gap in safety culture assessment. Published by the BMJ Publishing Group Limited. For permission to use (where not already granted under a licence) please go to http://www.bmj.com/company/products-services/rights-and-licensing/.

A Mandatory Uniform Policy in Urban Schools: Findings from the School Survey on Crime and Safety: 2003-04

Directory of Open Access Journals (Sweden)

Seunghee Han

2010-01-01

Full Text Available The main purpose of the study is to examine the relations between a mandatory school uniform policy and student problem behavior. The study is based on the School Survey on Crime and Safety (SSOCS 2003-04 data. Analyzing data from 421 urban schools, the study found that schools adopting a mandatory uniform policy are negatively associated with rates of student problem behaviors except at the high school level. As with other school safety initiatives, parental involvement at the elementary school level, and teacher training and community efforts at the high school level were revealed as negative predictors of student problem behavior.

Efficacy and safety of 10,600-nm carbon dioxide fractional laser on facial skin with previous volume injections

Directory of Open Access Journals (Sweden)

Josiane Hélou

2013-01-01

Full Text Available Background: Fractionated carbon dioxide (CO 2 lasers are a new treatment modality for skin resurfacing. The cosmetic rejuvenation market abounds with various injectable devices (poly-L-lactic acid, polymethyl-methacrylate, collagens, hyaluronic acids, silicone. The objective of this study is to examine the efficacy and safety of 10,600-nm CO 2 fractional laser on facial skin with previous volume injections. Materials and Methods: This is a retrospective study including 14 patients treated with fractional CO 2 laser and who have had previous facial volume restoration. The indication for the laser therapy, the age of the patients, previous facial volume restoration, and side effects were all recorded from their medical files. Objective assessments were made through clinical physician global assessment records and improvement scores records. Patients′ satisfaction rates were also recorded. Results: Review of medical records of the 14 patients show that five patients had polylactic acid injection prior to the laser session. Eight patients had hyaluronic acid injection prior to the laser session. Two patients had fat injection, two had silicone injection and one patient had facial thread lift. Side effects included pain during the laser treatment, post-treatment scaling, post-treatment erythema, hyperpigmentation which spontaneously resolved within a month. Concerning the previous facial volume restoration, no granulomatous reactions were noted, no facial shape deformation and no asymmetry were encountered whatever the facial volume product was. Conclusion: CO 2 fractional laser treatments do not seem to affect facial skin which had previous facial volume restoration with polylactic acid for more than 6 years, hyaluronic acid for more than 0.5 year, silicone for more than 6 years, or fat for more than 1.4 year. Prospective larger studies focusing on many other variables (skin phototype, injected device type are required to achieve better

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.

Patterns of electronic cigarette use and user beliefs about their safety and benefits: an internet survey.

Science.gov (United States)

Goniewicz, Maciej L; Lingas, Elena O; Hajek, Peter

2013-03-01

As the popularity of electronic cigarettes (e-cigarettes) increases, it is becoming important to find out more about the characteristics of e-cigarette users, why and how they use the product and whether e-cigarettes are used exclusively or in combination with conventional cigarettes. The objective of this study was to investigate patterns and effects of e-cigarette use and user beliefs about e-cigarette safety and benefits. E-cigarette users in Poland were recruited online and asked to participate in a web-based survey. The participants provided information on their smoking history, patterns of e-cigarette use, beliefs and attitudes regarding the product and information on concurrent use of conventional cigarettes. The survey was completed by 179 e-cigarette users. Almost all participants used e-cigarettes daily. E-cigarettes were primarily used to quit smoking or to reduce the harm associated with smoking (both 41%), and were successful in helping the surveyed users to achieve these goals with 66% not smoking conventional cigarettes at all and 25% smoking under five cigarettes a day. Most participants (82%) did not think that e-cigarettes were completely safe, but thought that they were less dangerous than conventional cigarettes. Sixty percent believed that e-cigarettes were addictive, but less so than conventional cigarettes. The participants primarily used e-cigarettes as a stop-smoking aid or as an alternative to conventional cigarettes, and the majority reported that they successfully stopped smoking. More data on e-cigarette safety and its efficacy in harm-reduction and smoking cessation are needed. © 2012 Australasian Professional Society on Alcohol and other Drugs.

A health and safety survey of Irish funeral industry workers.

LENUS (Irish Health Repository)

Kelly, N

2012-02-01

BACKGROUND: Those handling deceased individuals, including the funeral industry, face a variety of health and safety hazards including occupationally acquired infectious disease. AIMS: To identify the knowledge, attitudes and beliefs of Irish funeral industry workers towards occupational hazards and infectious disease in 2009. METHODS: The sample analysed consisted of all listed member premises of the Irish Association of Funeral Directors as at 1 July 2009. A postal survey was sent to each premises in July 2009, with two rounds of follow-up reviews sent to non-responders. Four main areas were covered--occupational hazards, embalming, industry expertise and demographics. The quantitative and qualitative results were analysed to assess knowledge, attitudes and beliefs. Data collection was completed on 31 December 2009. RESULTS: Two hundred and thirty listed member premises were contacted. Twenty-two were unsuitable for the survey. One hundred and thirty-eight valid replies were received from 130 premises, representing a premises response rate of 63% (130\\/208). Seventy-three premises (56%) identified themselves as embalmers. Embalmers had variable vaccine uptake and variable knowledge, attitude and beliefs towards embalming those with blood-borne viruses. Fifteen per cent of respondents reported a work-related injury, back injury being the most common. Splash and sharps injuries were reported as a work-related injury, and infections believed to be work related were also reported. CONCLUSIONS: This study demonstrates widespread occupational health concerns among this professional group. It confirms the need for occupational health advice and services. There is also a strong desire for regulation of this profession in Ireland.

Mid-Face Volumization With Hyaluronic Acid: Injection Technique and Safety Aspects from a Controlled, Randomized, Double-Blind Clinical Study.

Science.gov (United States)

Prager, Welf; Agsten, Karla; Kravtsov, Maria; Kerscher, Prof Martina

2017-04-01

BACKGROUND: Injection of hyaluronic acid (HA) volumizing fillers in the malar area is intended for rejuvenation of the mid-face. The choice of products, depth, and technique of injection depends on the desired level of volume enhancement and practitioners' preferences. OBJECTIVE: To describe a volumizing injection technique in the scope of a controlled, randomized, double-blind, single-center, split-face clinical study. A total of 45 subjects with bilateral symmetrical moderate to severe volume loss in the malar area received a single 2 mL injection of CPM®-26 (Cohesive Polydensified Matrix®) on one side and VYC®-20 (VYCROSS®) on the contralateral side of the face. The same injection technique was applied for both sides of the face. Use of anesthetics, overcorrection, and touch-ups were not permitted. The investigator completed a product satisfaction questionnaire. Adverse events (AE) and injection-site reactions (ISRs) were reported during the study. RESULTS: The products were placed at the epiperiosteal depth in 88.9% (n=40), at the subdermal depth in 8.9% (n=4) and at both levels in 2.2% (n=1) of subjects. Fanning technique using cannulae was applied in most cases (97.8%, n=44). Results of the investigator satisfaction questionnaire allowed to characterize CPM-26 in comparison to other volumizing gels. Both study products were generally well tolerated. Local reactions were transient and of mild to moderate intensity, with the most frequent ones being redness, pain, and swelling. CONCLUSION: Adequate injection technique in volumizing treatments is essential to create a natural aesthetic rejuvenation while respecting the safety aspect of the procedures. A 22G blunt cannula used with CPM-26 was preferred due to an easier and a more homogeneous distribution of the product. The investigator also appreciated CPM-26 for its ease of injection, positioning, lifting, and volumizing capacity. J Drugs Dermatol. 2017;16(4):351-357..

Report on transparency and nuclear safety - 2015. Nuclear facilities exploited by CEA Marcoule

International Nuclear Information System (INIS)

Guiberteau, Philippe

2016-01-01

This report presents the different basic nuclear installations (INB) of the Marcoule CEA centre, gives an overview of measures regarding safety within these installations (organisation, general arrangements, arrangements related to different risks, management of emergency situations, inspections, audits and second-level controls, arrangements and main events specific to the different installations and buildings) and of measures related to radiation protection (organisation and results, main events). It reports the significant events related to safety and radiation protection which occurred in 2015 and which were declared to the nuclear safety authority (ASN), and discusses how experience feedback has been used. It reports and comments the results of measurements of gaseous and liquid effluents, of their impact on the environment, and of surveys of the environment. It also presents the environmental management approach. The next part addresses the management of radioactive wastes which are warehoused on this site: arrangements aimed at limiting their volume, and at limiting their impact on health and on the environment, nature and quantities of warehoused wastes. Remarks and recommendations of the health, safety and work conditions committee (CHSCT) are given

The safety of domestic robotics: A survey of various safety-related publications

OpenAIRE

Tadele, T.S.; de Vries, Theodorus J.A.; Stramigioli, Stefano

2014-01-01

Different branches of technology are striving to come up with new advancements that will enhance civilization and ultimately improve the quality of life. In the robotics community, strides have been made to bring the use of personal robots in office and home environments on the horizon. Safety is one of the critical issues that must be guaranteed for the successful acceptance, deployment, and utilization of domestic robots. Unlike the barrier-based operational safety guarantee that is widely ...

Software safety analysis techniques for developing safety critical software in the digital protection system of the LMR

Energy Technology Data Exchange (ETDEWEB)

Lee, Jang Soo; Cheon, Se Woo; Kim, Chang Hoi; Sim, Yun Sub

2001-02-01

This report has described the software safety analysis techniques and the engineering guidelines for developing safety critical software to identify the state of the art in this field and to give the software safety engineer a trail map between the code and standards layer and the design methodology and documents layer. We have surveyed the management aspects of software safety activities during the software lifecycle in order to improve the safety. After identifying the conventional safety analysis techniques for systems, we have surveyed in details the software safety analysis techniques, software FMEA(Failure Mode and Effects Analysis), software HAZOP(Hazard and Operability Analysis), and software FTA(Fault Tree Analysis). We have also surveyed the state of the art in the software reliability assessment techniques. The most important results from the reliability techniques are not the specific probability numbers generated, but the insights into the risk importance of software features. To defend against potential common-mode failures, high quality, defense-in-depth, and diversity are considered to be key elements in digital I and C system design. To minimize the possibility of CMFs and thus increase the plant reliability, we have provided D-in-D and D analysis guidelines.

Software safety analysis techniques for developing safety critical software in the digital protection system of the LMR

International Nuclear Information System (INIS)

Lee, Jang Soo; Cheon, Se Woo; Kim, Chang Hoi; Sim, Yun Sub

2001-02-01

This report has described the software safety analysis techniques and the engineering guidelines for developing safety critical software to identify the state of the art in this field and to give the software safety engineer a trail map between the code and standards layer and the design methodology and documents layer. We have surveyed the management aspects of software safety activities during the software lifecycle in order to improve the safety. After identifying the conventional safety analysis techniques for systems, we have surveyed in details the software safety analysis techniques, software FMEA(Failure Mode and Effects Analysis), software HAZOP(Hazard and Operability Analysis), and software FTA(Fault Tree Analysis). We have also surveyed the state of the art in the software reliability assessment techniques. The most important results from the reliability techniques are not the specific probability numbers generated, but the insights into the risk importance of software features. To defend against potential common-mode failures, high quality, defense-in-depth, and diversity are considered to be key elements in digital I and C system design. To minimize the possibility of CMFs and thus increase the plant reliability, we have provided D-in-D and D analysis guidelines

A methodological study to compare survey-based and observation-based evaluations of organisational and safety cultures and then compare both approaches with markers of the quality of care.

Science.gov (United States)

Freeth, D; Sandall, J; Allan, T; Warburton, F; Berridge, E J; Mackintosh, N; Rogers, M; Abbott, S

2012-05-01

Patient safety concerns have focused attention on organisational and safety cultures, in turn directing attention to the measurement of organisational and safety climates. First, to compare levels of agreement between survey- and observation-based measures of organisational and safety climates/cultures and to compare both measures with criterion-based audits of the quality of care, using evidence-based markers drawn from national care standards relating to six common clinical conditions. (This required development of an observation-based instrument.) Second, to examine whether observation-based evaluations could replace or augment survey measurements to mitigate concerns about declining response rates and increasing social desirability bias. Third, to examine mediating factors in safety and organisational climate scores. The study had three strands: (A) a postal questionnaire survey to elicit staff perceptions of organisational and safety climates, using six prevalidated scales; (B) semistructured non-participant observation of clinical teams; and (C) a retrospective criterion-based audit carried out by non-clinical auditors to minimise hindsight bias. Standardised summary scores were created for each strand, and pairs of measurements were compared (strand A with strand B, strand A with strand C, and strand B with strand C) using Bland-Altman plots to evaluate agreement. Correlations were also examined. Multilevel modelling of Strand A scores explored mediating factors. Eight emergency departments and eight maternity units in England, UK. None. Examination of feasibility, correlation and agreement. Strand A: the overall response rate was 27.6%, whereas site-specific rates ranged from 9% to 47%. We identified more mediating factors than previous studies; variable response rates had little effect on the results. Organisational and safety climate scores were strongly correlated (r = 0.845) and exhibited good agreement [standard deviation (SD) differences 0.449; 14 (88

PATRAM '80. Proceedings. Volume 1

International Nuclear Information System (INIS)

Huebner, H.W.

1980-01-01

Volume 1 contains papers from the following sessions: Plenary Session; Regulations, Licensing and Standards; LMFBR Systems Concepts; Risk/Safety Assessment I; Systems and Package Design; US Institutional Issues; Risk/Safety Assessment II; Leakage, Leak Rate and Seals; Poster Session A; Operations and Systems Experience I; Manufacturing Processes and Materials; and Quality Assurance and Maintenance. Individual papers were processed. (LM)

Survey of Safety Climate in a Petrochemical Industry in Mahshahr

Directory of Open Access Journals (Sweden)

Y. Shokoohi

2012-07-01

Results and Discussion: Average score of the industry's safety climate was obtained 5.9. Of 17 studied dimensions, 9 dimensions were weak (score less than 6. Lowest score were related to Event & Accident and Change management dimensions. Highest score were related to Individual priorities and need for safety (8.65. Generally relationship between individual variables (ages, work experience, education and safety climate were not significant (P>0.05. Conclusion: Generally one can conclude that individual variables such as age, education and experience have not significant effect on safety climate. It seems that top management forms the organizational climate and consequently safety climate. It reaffirms the basic principle of senior management commitment to safety and its role in preventing accidents. Thus safety climate can be used as a good method for assessing Occupational Health and Safety Management Performance.

Inventory of Federal energy-related environment and safety research for FY 1978. Volume II. Project listings and indexes

Energy Technology Data Exchange (ETDEWEB)

None

1979-12-01

This volume contains summaries of FY-1978 government-sponsored environment and safety research related to energy. Project summaries were collected by Aerospace Corporation under contract with the Department of Energy, Office of Program Coordination, under the Assistant Secretary for Environment. Summaries are arranged by log number, which groups the projects by reporting agency. The log number is a unique number assigned to each project from a block of numbers set aside for each agency. Information about the projects is included in the summary listings. This includes the project title, principal investigators, research organization, project number, contract number, supporting organization, funding level if known, related energy sources with numbers indicating percentages of effort devoted to each, and R and D categories. A brief description of each project is given, and this is followed by subject index terms that were assigned for computer searching and for generating the printed subject index in Volume IV.

Inventory of Federal energy-related environment and safety research for FY 1978. Volume II. Project listings and indexes

International Nuclear Information System (INIS)

1979-12-01

This volume contains summaries of FY-1978 government-sponsored environment and safety research related to energy. Project summaries were collected by Aerospace Corporation under contract with the Department of Energy, Office of Program Coordination, under the Assistant Secretary for Environment. Summaries are arranged by log number, which groups the projects by reporting agency. The log number is a unique number assigned to each project from a block of numbers set aside for each agency. Information about the projects is included in the summary listings. This includes the project title, principal investigators, research organization, project number, contract number, supporting organization, funding level if known, related energy sources with numbers indicating percentages of effort devoted to each, and R and D categories. A brief description of each project is given, and this is followed by subject index terms that were assigned for computer searching and for generating the printed subject index in Volume IV

Twenty-third water reactor safety information meeting: Volume 2, Human factors research; Advanced I and C hardware and software; Severe accident research; Probabilistic risk assessment topics; Individual plant examination: Proceedings

Energy Technology Data Exchange (ETDEWEB)

Monteleone, S. [comp.] [Brookhaven National Lab., Upton, NY (United States)

1996-03-01

This three-volume report contains papers presented at the Twenty- Third Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, October 23-25, 1995. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Italy, Japan, Norway, Russia, Sweden, and Switzerland. This document, Volume 2, present topics in human factors research, advanced instrumentation and control hardware and software, severe accident research, probabilistic risk assessment, and individual plant examination. Individual papers have been cataloged separately.

Investigations of possibilities to dispose of spent nuclear fuel in Lithuania: a model case. Volume 3, Generic Safety Assessment of Repository in Crystalline Rocks

International Nuclear Information System (INIS)

Motiejunas, S.; Poskas, P.

2005-01-01

In this Volume a generic safety assessment of the repository for spent nuclear fuel in crystalline rock in Lithuania is presented. Modeling of safety relevant radionuclide release from the defected canister and their transport through the near field and far field was performed. Doses to humans due to released radionuclides in the well water were calculated and compared with the dose restrictions existing in Lithuania. For this stage of generic safety assessment only two scenarios were chosen: base scenario and canister defect scenario. KBS-3 concept developed by SKB for disposal of spent nuclear fuel in Sweden was chosen as prototype for repository in crystalline basement in Lithuania. The KBS-3H design with horizontal canister emplacement is proposed as a reference design for Lithuania

Site survey for nuclear power plants

International Nuclear Information System (INIS)

1984-01-01

This Safety Guide describes the first stage of the siting process for nuclear power plants - the site survey to select one or more preferred candidate sites. Its purpose is to recommend procedures and provide information for use in implementing a part of the Code of Practice on Safety in Nuclear Power Plant Siting (IAEA Safety Series No.50-C-S). The organization, procedures, methodologies, guidance for documenting the site survey process and examples of detailed procedures on some safety-related site characteristics are given in the Guide

A SUCCESSFUL BROADBAND SURVEY FOR GIANT Lyα NEBULAE. I. SURVEY DESIGN AND CANDIDATE SELECTION

International Nuclear Information System (INIS)

Prescott, Moire K. M.; Dey, Arjun; Jannuzi, Buell T.

2012-01-01

Giant Lyα nebulae (or Lyα 'blobs') are likely sites of ongoing massive galaxy formation, but the rarity of these powerful sources has made it difficult to form a coherent picture of their properties, ionization mechanisms, and space density. Systematic narrowband Lyα nebula surveys are ongoing, but the small redshift range covered and the observational expense limit the comoving volume that can be probed by even the largest of these surveys and pose a significant problem when searching for such rare sources. We have developed a systematic search technique designed to find large Lyα nebulae at 2 ∼ 2 NOAO Deep Wide-Field Survey Boötes field. With a total survey comoving volume of ≈10 8 h –3 70 Mpc 3 , this is the largest volume survey for Lyα nebulae ever undertaken. In this first paper in the series, we present the details of the survey design and a systematically selected sample of 79 candidates, which includes one previously discovered Lyα nebula.

Radiation safety among cardiology fellows.

Science.gov (United States)

Kim, Candice; Vasaiwala, Samip; Haque, Faizul; Pratap, Kiran; Vidovich, Mladen I

2010-07-01

Cardiology fellows can be exposed to high radiation levels during procedures. Proper radiation training and implementation of safety procedures is of critical importance in lowering physician health risks associated with radiation exposure. Participants were cardiology fellows in the United States (n = 2,545) who were contacted by e-mail to complete an anonymous survey regarding the knowledge and practice of radiation protection during catheterization laboratory procedures. An on-line survey engine, SurveyMonkey, was used to distribute and collect the results of the 10-question survey. The response rate was 10.5%. Of the 267 respondents, 82% had undergone formal radiation safety training. Only 58% of the fellows were aware of their hospital's pregnancy radiation policy and 60% knew how to contact the hospital's radiation safety officer. Although 52% of the fellows always wore a dosimeter, 81% did not know their level of radiation exposure in the previous year and only 74% of fellows knew the safe levels of radiation exposure. The fellows who had received formal training were more likely to be aware of their pregnancy policy, to know the contact information of their radiation safety officer, to be aware of the safe levels of radiation exposure, to use dosimeters and RadPad consistently, and to know their own level of radiation exposure in the previous year. In conclusion, cardiology fellows have not been adequately educated about radiation safety. A concerted effort directed at physician safety in the workplace from the regulatory committees overseeing cardiology fellowships should be encouraged. Published by Elsevier Inc.

Nuclear safety. Volume 36, Number 2, July--December 1995

Energy Technology Data Exchange (ETDEWEB)

None

1995-12-01

The primary scope of the journal is safety in the design, construction, operation, and decommissioning of nuclear power reactors worldwide and the research and analysis activities that promote this goal, but it also encompasses the safety aspects of the entire nuclear fuel cycle, including fuel fabrication, spent-fuel processing and handling, and nuclear waste disposal, the handling of fissionable materials and radioisotopes, and the environmental effects of all these activities. The following subjects are covered here: (1) the Chernobyl accident; (2) general safety considerations; (3) accident analysis; (4) design features; (5) environmental effects; (6) operating experiences; (7) US NRC information and analyses; and (8) recent developments. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

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

Directory of Open Access Journals (Sweden)

Mária FRANEKOVÁ

2008-01-01

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

Survey of strong motion earthquake effects on thermal power plants in California with emphasis on piping systems. Volume 2, Appendices

International Nuclear Information System (INIS)

Stevenson, J.D.

1995-11-01

Volume 2 of the ''Survey of Strong Motion Earthquake Effects on Thermal Power Plants in California with Emphasis on Piping Systems'' contains Appendices which detail the detail design and seismic response of several power plants subjected to strong motion earthquakes. The particular plants considered include the Ormond Beach, Long Beach and Seal Beach, Burbank, El Centro, Glendale, Humboldt Bay, Kem Valley, Pasadena and Valley power plants. Included is a typical power plant piping specification and photographs of typical power plant piping specification and photographs of typical piping and support installations for the plants surveyed. Detailed piping support spacing data are also included

A NEARLY VOLUME-COMPLETE SPECTROSCOPIC SURVEY OF THE CLOSESTMID-TO-LATE M DWARFS

Science.gov (United States)

Winters, Jennifer; Irwin, Jonathan; Newton, Elisabeth; Charbonneau, David; Latham, David W.; Mink, Jessica; Esquerdo, Gil; Berlind, Perry; Calkins, Mike

2018-01-01

Recent results from Kepler estimate that M dwarfs harbor 2.5 planets per star. Yet, we will understand our exoplanet discoveries only as well as we understand their host stars, and much remains unknown about our low-mass stellar neighbors, such as their kinematics, ages, and multiplicity. A nearly volume-complete sample of M dwarfs lies within 15 pc of the Sun, and it is only for planets orbiting these nearest and smallest stars that thorough follow-up work for characterization will be possible. Unfortunately, more than half of this sample have only low-resolution (R SMARTS) 1.5m. We present here results from year one of our TRES survey. We have measured radial velocities, rotational broadening, and H-alpha equivalent widths for 305 mid-to-late M dwarfs. We have discovered five new spectroscopic binaries, one of which is a rare M dwarf - (likely) brown dwarf binary within 10 pc, for which we have determined the orbit.Our survey more than doubles the number of mid-M dwarfs within 15 pc with complete high-resolution spectroscopic and trigonometric characterization. We hope to provide a legacy dataset for the use of future generations of astronomers.This work is being supported by grants from the National Science Foundation and the John Templeton Foundation.

Nuclear health and safety

International Nuclear Information System (INIS)

1990-04-01

This report summarizes the responsiveness of DOE and contractors to findings contained in DOE technical safety appraisals and environmental surveys. These appraisals and surveys have been done at DOE facilities and sites to find out the extent of the environmental, safety, and health problems and to prioritize them for corrective action. As of January 1990, DOE computer data showed over 1,700 safety and health problems and almost 1,300 environmental problems. The majority of these problems, however, have not yet been corrected. GAO also looked at the extent to which DOE has developed a computerized tracking system to monitor the status of its environmental, safety, and health problems. GAO found that the computer system lacks important information, such as various field office and independent appraisals. Inclusion of this information would provide a more complete picture of the problems at the site

2016 Traffic Safety Culture Index

Science.gov (United States)

... Newsroom SEARCH Driver Behavior & Performance 2016 Traffic Safety Culture Index This report presents the results of our annual Traffic Safety Culture Index survey, providing data on the attitudes and ...

Measuring the safety culture in a hospital setting: a concept whose time has come?

Science.gov (United States)

Robb, Gillian; Seddon, Mary

2010-05-14

Getting the right 'patient safety culture' is thought to be an important component in improving patient safety in hospitals, however there is a lack of clarity in how best to measure and improve it, and whether such improvement actually translates to better patient outcomes. This paper reflects on the Counties Manukau District Health Board (CMDHB) experience with a patient safety survey and attempts to answer questions other organisations may ask when deciding whether to invest in such survey. A literature search was undertaken to identify valid and reliable patient safety culture survey tools. These were reviewed with respect to how best to interpret and use the results. If hospitals decide to undertake a patient safety culture survey, the recommended survey tools are the Safety Attitudes Questionnaire (SAQ) and the Hospital Survey on Patient Safety (HSOPS). Both have been widely used and have sound and comprehensive psychometrics. Only the SAQ has established links with patient safety outcomes such as reduced healthcare associated infections. Surveys can provide some insights into the patient safety culture within an organisation, but the opportunity costs of undertaking a survey should be carefully considered. Much of their value lies in raising the profile of patient safety and promoting conversations; making patient safety 'the way we do business around here'.

Choice of teenagers' vehicles and views on vehicle safety: survey of parents of novice teenage drivers.

Science.gov (United States)

Hellinga, Laurie A; McCartt, Anne T; Haire, Emily R

2007-01-01

To examine parental decisions about vehicles driven by teenagers and parental knowledge of vehicle safety. About 300 parents were interviewed during spring 2006 in Minnesota, North Carolina, and Rhode Island while teenagers took their first on-road driving tests. Fewer than half of parents surveyed said teenagers would be the primary drivers of the chosen vehicles. Parents most often cited safety, existing family vehicle, and reliability when explaining the choices for their teenagers' vehicles. About half of the vehicles intended for teenagers were small/mini/sports cars, pickups, or SUVs - vehicles considered less safe for teenagers than midsize/large cars or minivans. A large majority of vehicles were 2001 models or earlier. Vehicles purchased in anticipation of adding a new driver to the family were more likely to be the sizes/types considered less safe than vehicles already owned. Few parents insisted on side airbags or electronic stability control, despite strong evidence of their safety benefits. Even when asked to identify ideal vehicles for their teenagers to drive, about half of parents identified less safe vehicle sizes/types. Most parents knew that midsize/large vehicles are safer than small vehicles, and at least half of parents said SUVs and pickups are not safe for teenage drivers, citing instability. The majority of parents understood some of the important criteria for choosing safe vehicles for their teenagers. However, parents actually selected many vehicles for teenagers that provide inferior crash protection. Vehicle safety varies substantially by vehicle size, type, and safety features. Many teenagers are driving inferior vehicles in terms of crashworthiness and crash avoidance.

Linguistic Validation and Cultural Adaptation of Bulgarian Version of Hospital Survey on Patient Safety Culture (HSOPSC).

Science.gov (United States)

Stoyanova, Rumyana; Dimova, Rositsa; Tarnovska, Miglena; Boeva, Tatyana

2018-05-20

Patient safety (PS) is one of the essential elements of health care quality and a priority of healthcare systems in most countries. Thus the creation of validated instruments and the implementation of systems that measure patient safety are considered to be of great importance worldwide. The present paper aims to illustrate the process of linguistic validation, cross-cultural verification and adaptation of the Bulgarian version of the Hospital Survey on Patient Safety Culture (B-HSOPSC) and its test-retest reliability. The study design is cross-sectional. The HSOPSC questionnaire consists of 42 questions, grouped in 12 different subscales that measure patient safety culture. Internal con-sistency was assessed using Cronbach's alpha. The Wilcoxon signed-rank test and the split-half method were used; the Spear-man-Brown coefficient was calculated. The overall Cronbach's alpha for B-HSOPSC is 0.918. Subscales 7 Staffing and 12 Overall perceptions of safety had the lowest coefficients. The high reliability of the instrument was confirmed by the Split-half method (0.97) and ICC-coefficient (0.95). The lowest values of Spearmen-Broun coefficients were found in items A13 and A14. The study offers an analysis of the results of the linguistic validation of the B-HSOPSC and its test-retest reliability. The psychometric characteristics of the questions revealed good validity and reliability, except two questions. In the future, the instrument will be administered to the target population in the main study so that the psychometric properties of the instrument can be verified.

A SUCCESSFUL BROADBAND SURVEY FOR GIANT Ly{alpha} NEBULAE. I. SURVEY DESIGN AND CANDIDATE SELECTION

Energy Technology Data Exchange (ETDEWEB)

Prescott, Moire K. M. [Department of Physics, Broida Hall, Mail Code 9530, University of California, Santa Barbara, CA 93106 (United States); Dey, Arjun; Jannuzi, Buell T., E-mail: mkpresco@physics.ucsb.edu [National Optical Astronomy Observatory, 950 North Cherry Avenue, Tucson, AZ 85719 (United States)

2012-04-01

Giant Ly{alpha} nebulae (or Ly{alpha} 'blobs') are likely sites of ongoing massive galaxy formation, but the rarity of these powerful sources has made it difficult to form a coherent picture of their properties, ionization mechanisms, and space density. Systematic narrowband Ly{alpha} nebula surveys are ongoing, but the small redshift range covered and the observational expense limit the comoving volume that can be probed by even the largest of these surveys and pose a significant problem when searching for such rare sources. We have developed a systematic search technique designed to find large Ly{alpha} nebulae at 2 {approx}< z {approx}< 3 within deep broadband imaging and have carried out a survey of the 9.4 deg{sup 2} NOAO Deep Wide-Field Survey Booetes field. With a total survey comoving volume of Almost-Equal-To 10{sup 8} h{sup -3}{sub 70} Mpc{sup 3}, this is the largest volume survey for Ly{alpha} nebulae ever undertaken. In this first paper in the series, we present the details of the survey design and a systematically selected sample of 79 candidates, which includes one previously discovered Ly{alpha} nebula.

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)

Report on transparency and nuclear safety - Fontenay-aux-Roses CEA centre - 2012

International Nuclear Information System (INIS)

2013-01-01

This report presents the different nuclear base installations (INB) of the Fontenay-aux-Roses CEA centre, gives an overview of measures regarding safety within these installations (organisation, general arrangements, arrangements related to different risks, defence in-depth, management of emergency situations, inspections, audits and second-level controls, arrangements and main events specific to the different installations and buildings, issues related to transports, soil radiological assessment) and measures related to radiation protection (organisation and results). It reports the significant events related to safety and radiation protection which occurred in 2012 and were declared to the ASN, and discusses how the return-on-experience has been used. It reports and comments the results of measurements of radiological and chemical gaseous and liquid effluents, of surveys of the environment. It also evokes important events related to these measurement and survey processes, presents the environmental management approach. The next part addresses the management of radioactive wastes: arrangements aimed at limiting the volume of warehoused wastes, and at limiting their impact on health and on the environment, nature and quantities of warehoused wastes. The different arrangements regarding transparency and information are reviewed (TSN report, newsletter, and so on)

Perceived safety management practices in the logistics sector.

Science.gov (United States)

Auyong, Hui-Nee; Zailani, Suhaiza; Surienty, Lilis

2016-03-09

Malaysia's progress on logistics has been slowed to keep pace with its growth in trade. The Government has been pressing companies to improve the safety of their activities in order to reduce society's loss due to occupational accidents and illnesses. Occupational safety and health is a crucial part of a workplace because every worker has to take care of his/her own safety and health. The main occupational safety and health (OSH) national policy in Malaysia is the enactment of the Occupational Safety and Health Act (OSHA) 1994. Only those companies which have excellent health and safety care have good quality and productive employees. This study investigated safety management practices in the logistics sector. The present study is concerned with the human factors to safety in the logistics industry. The authors examined the perceived safety management practices of workers in the logistics sector. The purpose was to identify the perception of safety management practices of Malaysian logistics personnel. Survey questionnaires were distributed to assess logistics personnel about management commitment. The quantitative method using the availability sampling method was applied. The data gathered from the survey were analysed using SPSS software. The responses to the survey were rated according to the Likert scale type, with '1' indicating strongly disagree and '5' indicating strongly agree. One hundred and three employees of logistics functions completed the survey. The highest mean scores were found for fire apparatus, prioritisation of safety, and safety policy. The results from this study also emphasise the importance of the management's commitment in enhancing workplace safety. Specifically, companies should maintain good relations between the employer and the employee to help reduce workplace injuries.

Implementing Patient Safety Initiatives in Rural Hospitals

Science.gov (United States)

Klingner, Jill; Moscovice, Ira; Tupper, Judith; Coburn, Andrew; Wakefield, Mary

2009-01-01

Implementation of patient safety initiatives can be costly in time and energy. Because of small volumes and limited resources, rural hospitals often are not included in nationally driven patient safety initiatives. This article describes the Tennessee Rural Hospital Patient Safety Demonstration project, whose goal was to strengthen capacity for…

Twenty-second water reactor safety information meeting. Volume 2: Severe accident research, thermal hydraulic research for advanced passive LWRs, high-burnup fuel behavior

Energy Technology Data Exchange (ETDEWEB)

Monteleone, S. [comp.

1995-04-01

This three-volume report contains papers presented at the Twenty-Second Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 24-26, 1994. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from Finland, France, Italy, Japan, Russia, and United Kingdom. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting.

Twenty-second water reactor safety information meeting. Volume 2: Severe accident research, thermal hydraulic research for advanced passive LWRs, high-burnup fuel behavior

International Nuclear Information System (INIS)

Monteleone, S.

1995-04-01

This three-volume report contains papers presented at the Twenty-Second Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 24-26, 1994. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from Finland, France, Italy, Japan, Russia, and United Kingdom. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting

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

Liquefied Gaseous Fuels Safety and Environmental Control Assessment Program: second status report

Energy Technology Data Exchange (ETDEWEB)

1980-10-01

The Assistant Secretary for Environment has responsibility for identifying, characterizing, and ameliorating the environmental, health, and safety issues and public concerns associated with commercial operation of specific energy systems. The need for developing a safety and environmental control assessment for liquefied gaseous fuels was identified by the Environmental and Safety Engineering Division as a result of discussions with various governmental, industry, and academic persons having expertise with respect to the particular materials involved: liquefied natural gas, liquefied petroleum gas, hydrogen, and anhydrous ammonia. This document is arranged in three volumes and reports on progress in the Liquefied Gaseous Fuels (LGF) Safety and Environmental Control Assessment Program made in Fiscal Year (FY)-1979 and early FY-1980. Volume 1 (Executive Summary) describes the background, purpose and organization of the LGF Program and contains summaries of the 25 reports presented in Volumes 2 and 3. Annotated bibliographies on Liquefied Natural Gas (LNG) Safety and Environmental Control Research and on Fire Safety and Hazards of Liquefied Petroleum Gas (LPG) are included in Volume 1.

Subjective perception of safety in healthy individuals working with 7 T MRI scanners: a retrospective multicenter survey.

Science.gov (United States)

Fatahi, Mahsa; Demenescu, Liliana Ramona; Speck, Oliver

2016-06-01

To retrospectively assess perception of safety of healthy individuals working with human 7 Tesla (T) magnetic resonance imaging (MRI) scanners. A total of 66 healthy individuals with a mean age of 31 ± 7 years participated in this retrospective multicentre survey study. Nonparametric correlation analysis was conducted to evaluate the relation between self-reported perception of safety and prevalence of sensory effects while working with 7 T MRI scanners for an average 47 months. The results indicated that 98.5 % of the study participants had a neutral or positive feeling about safety aspects at 7 T MRI scanners. 45.5 % reported that they feel very safe and none of the participants stated that they feel moderately or very unsafe while working with 7 T MRI scanners. Perception of safety was not affected by the number of hours per week spent in the vicinity of the 7 T MRI scanner or the duration of experience with 7 T MRI. More than 50 % of individuals experienced vertigo and metallic taste while working with 7 T MRI scanners. However, participants' perceptions of safety were not affected by the prevalence of MR-related symptoms. The overall data indicated an average perception of a moderately safe work environment. To our knowledge, this study delineates the first attempt to assess the subjective safety perception among 7 T MRI workers and suggests further investigations are indicated.

Potential Theory Surveys and Problems

CERN Document Server

Lukeš, Jaroslav; Netuka, Ivan; Veselý, Jiří

1988-01-01

The volume comprises eleven survey papers based on survey lectures delivered at the Conference in Prague in July 1987, which covered various facets of potential theory, including its applications in other areas. The survey papers deal with both classical and abstract potential theory and its relations to partial differential equations, stochastic processes and other branches such as numerical analysis and topology. A collection of problems from potential theory, compiled on the occasion of the conference, is included, with additional commentaries, in the second part of this volume.

Does lean management improve patient safety culture? An extensive evaluation of safety culture in a radiotherapy institute.

Science.gov (United States)

Simons, Pascale A M; Houben, Ruud; Vlayen, Annemie; Hellings, Johan; Pijls-Johannesma, Madelon; Marneffe, Wim; Vandijck, Dominique

2015-02-01

The importance of a safety culture to maximize safety is no longer questioned. However, achieving sustainable culture improvements are less evident. Evidence is growing for a multifaceted approach, where multiple safety interventions are combined. Lean management is such an integral approach to improve safety, quality and efficiency and therefore, could be expected to improve the safety culture. This paper presents the effects of lean management activities on the patient safety culture in a radiotherapy institute. Patient safety culture was evaluated over a three year period using triangulation of methodologies. Two surveys were distributed three times, workshops were performed twice, data from an incident reporting system (IRS) was monitored and results were explored using structured interviews with professionals. Averages, chi-square, logistical and multi-level regression were used for analysis. The workshops showed no changes in safety culture, whereas the surveys showed improvements on six out of twelve dimensions of safety climate. The intention to report incidents not reaching patient-level decreased in accordance with the decreasing number of reports in the IRS. However, the intention to take action in order to prevent future incidents improved (factorial survey presented β: 1.19 with p: 0.01). Due to increased problem solving and improvements in equipment, the number of incidents decreased. Although the intention to report incidents not reaching patient-level decreased, employees experienced sustained safety awareness and an increased intention to structurally improve. The patient safety culture improved due to the lean activities combined with an organizational restructure, and actual patient safety outcomes might have improved as well. Copyright © 2014 Elsevier Ltd. All rights reserved.

Measuring enterprise proactiveness in managing occupational safety

DEFF Research Database (Denmark)

Sønderstrup-Andersen, Hans H. K.; Fløcke, Thomas; Mikkelsen, Kim Lyngby

2010-01-01

The aim of this paper is to communicate results, and lessons learned, from developing and applying a national questionnaire based survey for measuring the initiation of occupational safety activities in Danish enterprises and public institutions1. The survey is cross-sectional and it is part...... on the safety attitude index....

Assessing the culture of safety in cardiovascular perfusion: attitudes and perceptions.

Science.gov (United States)

Lawson, Chad; Predella, Megan; Rowden, Allison; Goldstein, Jamie; Sistino, Joseph J; Fitzgerald, David C

2017-10-01

The Hospital Survey on Patient Safety Culture was developed by the Agency for Healthcare Research and Quality (AHRQ) to assess the culture of safety in hospitals. The purpose of this study was to identify specific domains of perfusion that are indicators of a high quality culture of safety. Perfusionists were recruited to participate in the survey through email invitation through Perflist, Perfmail and LinkedIn. The survey consisted of 37 questions across six safety domains. Questions were developed using the AHRQ Hospital Survey on Patient Safety Culture. 'Positive scores' were defined as a response that either agreed or strongly agreed with a safety standard. Survey responses that resulted in a 75 percent or higher positive response rate were identified as vital components of a high culture of safety. Logistic regression analysis was used to determine importance components of perceived safety. Four responses were found to have a significant predictive level of a positive safety environment in the work unit: (1) in this unit, we discuss ways to prevent errors from happening again; OR=3.09, (2) in this unit, we treat others with respect; OR=1.09 (3) my supervisor/manager seriously considers staff suggestions for improving patient safety; OR=1.89 and (4) there is good cooperation among hospital units that need to work together; OR=1.77. There were two predictors of a negative work unit safety environment: (1) staff are afraid to ask questions when something does not seem right; OR=0.62 and (2) it is just by chance that more serious mistakes don't happen around here; OR=0.55. The results from this survey indicate that effective communication secondary to both incident and near-miss reporting is associated with a higher perceived culture of safety. A positive safety environment is associated with being able to speak up regarding safety issues without fear of negative repercussions.

Safety climate and safety behaviors in the construction industry: The importance of co-workers commitment to safety.

Science.gov (United States)

Schwatka, Natalie V; Rosecrance, John C

2016-06-16

There is growing empirical evidence that as safety climate improves work site safety practice improve. Safety climate is often measured by asking workers about their perceptions of management commitment to safety. However, it is less common to include perceptions of their co-workers commitment to safety. While the involvement of management in safety is essential, working with co-workers who value and prioritize safety may be just as important. To evaluate a concept of safety climate that focuses on top management, supervisors and co-workers commitment to safety, which is relatively new and untested in the United States construction industry. Survey data was collected from a cohort of 300 unionized construction workers in the United States. The significance of direct and indirect (mediation) effects among safety climate and safety behavior factors were evaluated via structural equation modeling. Results indicated that safety climate was associated with safety behaviors on the job. More specifically, perceptions of co-workers commitment to safety was a mediator between both management commitment to safety climate factors and safety behaviors. These results support workplace health and safety interventions that build and sustain safety climate and a commitment to safety amongst work teams.

Evaluation of safety climate and employee injury rates in healthcare.

Science.gov (United States)

Cook, Jacqueline M; Slade, Martin D; Cantley, Linda F; Sakr, Carine J

2016-09-01

Safety climates that support safety-related behaviour are associated with fewer work-related injuries, and prior research in industry suggests that safety knowledge and motivation are strongly related to safety performance behaviours; this relationship is not well studied in healthcare settings. We performed analyses of survey results from a Veterans Health Administration (VHA) Safety Barometer employee perception survey, conducted among VHA employees in 2012. The employee perception survey assessed 6 safety programme categories, including management participation, supervisor participation, employee participation, safety support activities, safety support climate and organisational climate. We examined the relationship between safety climate from the survey results on VHA employee injury and illness rates. Among VHA facilities in the VA New England Healthcare System, work-related injury rate was significantly and inversely related to overall employee perception of safety climate, and all 6 safety programme categories, including employee perception of employee participation, management participation, organisational climate, supervisor participation, safety support activities and safety support climate. Positive employee perceptions of safety climate in VHA facilities are associated with lower work-related injury and illness rates. Employee perception of employee participation, management participation, organisational climate, supervisor participation, safety support activities and safety support climate were all associated with lower work-related injury rates. Future implications include fostering a robust safety climate for patients and healthcare workers to reduce healthcare worker injuries. Published by the BMJ Publishing Group Limited. For permission to use (where not already granted under a licence) please go to http://www.bmj.com/company/products-services/rights-and-licensing/

Fast reactor safety and related physics. Volume I. Invited papers; panels; summary

Energy Technology Data Exchange (ETDEWEB)

1976-01-01

Separate abstracts were prepared for each of the twenty invited papers included. The papers covered sessions on licensing aspects of safety design bases, safety of demonstration plants, safety aspects of large commercial fast breeders, and safety test facilities.

School Survey on Crime and Safety (SSOCS) 2000 Public-Use Data Files, User's Manual, and Detailed Data Documentation. [CD-ROM].

Science.gov (United States)

National Center for Education Statistics (ED), Washington, DC.

This CD-ROM contains the raw, public-use data from the 2000 School Survey on Crime and Safety (SSOCS) along with a User's Manual and Detailed Data Documentation. The data are provided in SAS, SPSS, STATA, and ASCII formats. The User's Manual and the Detailed Data Documentation are provided as .pdf files. (Author)

Laser safety tools and training

CERN Document Server

Barat, Ken

2008-01-01

Lasers perform many unique functions in a plethora of applications, but there are many inherent risks with this continually burgeoning technology. Laser Safety: Tools and Training presents simple, effective ways for users in a variety of facilities to evaluate the hazards of any laser procedure and ensure they are following documented laser safety standards.Designed for use as either a stand-alone volume or a supplement to Laser Safety Management, this text includes fundamental laser and laser safety information and critical laser use information rarely found in a single source. The first lase

Leading Edge. Volume 7, Number 3. Systems Safety Engineering

Science.gov (United States)

2010-01-01

foods were not always safe to eat given the sanitary conditions of the day. In 1943, the psychologist Abraham Maslow proposed a five-level... hierarchy of basic human needs, and safety was number two on this list. System safety is a specialized and formalized extension of our in- herent drive for...factors, hazards, mishaps, and ef- fects. The following is an example of each element within the hierarchy : An exposed sharp edge in a relay cabi- net

Results of an aging-related failure survey of light water safety systems and components

International Nuclear Information System (INIS)

Meale, B.M.; Satterwhite, D.G.; MacDonald, P.E.

1988-01-01

The collection and evaluation of operating experience data are necessary in determining the effects of aging on the safety of operating nuclear plants. This paper presents the final results of a two-year research effort evaluating aging impacts on components in light water reactor systems. This research was performed as a part of the Nuclear Plant Aging Research program, sponsored by the US Nuclear Regulatory Commission. Two unique types of data analyses were performed. In the first, an aging-survey study, aging-related failure data for fifteen light water reactor systems were obtained from the Nuclear Plant Reliability Data System (NPRDS). These included safety, support, and power conversion systems. A computerized sort of these records classified each record into one of five generic categories, based on the utility's choice of the failure's NPRDS cause category. Systems and components within the systems that were most affected by aging were identified. In the second analysis, information on aging-related reported causes of failures was evaluated for component failures reported to NPRDS for auxiliary feedwater, high pressure injection, service water, and Class 1E electrical power distribution systems. 3 refs., 13 figs., 4 tabs

Twenty-second water reactor safety information meeting: Proceedings. Volume 3: Primary systems integrity; Structural and seismic engineering; Aging research, products and applications

Energy Technology Data Exchange (ETDEWEB)

Monteleone, S. [comp.] [Brookhaven National Lab., Upton, NY (United States)

1995-04-01

This three-volume report contains papers presented at the Twenty-Second Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 24--26, 1994. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from Finland, France, Italy, Japan, Russia, and United Kingdom. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

Twenty-second water reactor safety information meeting: Proceedings. Volume 3: Primary systems integrity; Structural and seismic engineering; Aging research, products and applications

International Nuclear Information System (INIS)

Monteleone, S.

1995-04-01

This three-volume report contains papers presented at the Twenty-Second Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 24--26, 1994. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from Finland, France, Italy, Japan, Russia, and United Kingdom. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database

An Analysis of Laboratory Safety in Texas.

Science.gov (United States)

Fuller, Edward J.; Picucci, Ali Callicoatte; Collins, James W.; Swann, Philip

This paper reports on a survey to discover the types of laboratory accidents that occur in Texas public schools, the factors associated with such accidents, and the practices of schools with regard to current laboratory safety requirements. The purpose of the survey is to better understand safety conditions in Texas public schools and to help…

Statistical analysis applied to safety culture self-assessment

International Nuclear Information System (INIS)

Macedo Soares, P.P.

2002-01-01

Interviews and opinion surveys are instruments used to assess the safety culture in an organization as part of the Safety Culture Enhancement Programme. Specific statistical tools are used to analyse the survey results. This paper presents an example of an opinion survey with the corresponding application of the statistical analysis and the conclusions obtained. Survey validation, Frequency statistics, Kolmogorov-Smirnov non-parametric test, Student (T-test) and ANOVA means comparison tests and LSD post-hoc multiple comparison test, are discussed. (author)

Building a safety culture in global health: lessons from Guatemala.

Science.gov (United States)

Rice, Henry E; Lou-Meda, Randall; Saxton, Anthony T; Johnston, Bria E; Ramirez, Carla C; Mendez, Sindy; Rice, Eli N; Aidar, Bernardo; Taicher, Brad; Baumgartner, Joy Noel; Milne, Judy; Frankel, Allan S; Sexton, J Bryan

2018-01-01

Programmes to modify the safety culture have led to lasting improvements in patient safety and quality of care in high-income settings around the world, although their use in low-income and middle-income countries (LMICs) has been limited. This analysis explores (1) how to measure the safety culture using a health culture survey in an LMIC and (2) how to use survey data to develop targeted safety initiatives using a paediatric nephrology unit in Guatemala as a field test case. We used the Safety, Communication, Operational Reliability, and Engagement survey to assess staff views towards 13 health climate and engagement domains. Domains with low scores included personal burnout, local leadership, teamwork and work-life balance. We held a series of debriefings to implement interventions targeted towards areas of need as defined by the survey. Programmes included the use of morning briefings, expansion of staff break resources and use of teamwork tools. Implementation challenges included the need for education of leadership, limited resources and hierarchical work relationships. This report can serve as an operational guide for providers in LMICs for use of a health culture survey to promote a strong safety culture and to guide their quality improvement and safety programmes.

Adaptação transcultural da versão brasileira do Hospital Survey on Patient Safety Culture: etapa inicial Translation and cross-cultural adaptation of the Brazilian version of the Hospital Survey on Patient Safety Culture: initial stage

Directory of Open Access Journals (Sweden)

Claudia Tartaglia Reis

2012-11-01

Full Text Available A avaliação da cultura de segurança do paciente permite aos hospitais identificar e gerir prospectivamente questões relevantes de segurança em suas rotinas de trabalho. Este artigo descreve a adaptação transcultural do Hospital Survey on Patient Safety Culture (HSOPSC para a Língua Portuguesa e contexto brasileiro. Adotou-se abordagem universalista para avaliar a equivalência conceitual, de itens e semântica. A metodologia incluiu os seguintes estágios: (1 tradução do questionário para o Português; (2 retradução para o Inglês; (3 painel de especialistas para elaboração da versão preliminar; (4 avaliação da compreensão verbal pela população-alvo. O questionário foi traduzido para o Português e sua versão final incluiu 42 itens. A população-alvo avaliou todos os itens como de fácil compreensão. O questionário encontra-se traduzido para o Português e adaptado para o contexto brasileiro, entretanto, faz-se necessário avaliar sua equivalência de mensuração, validade externa e reprodutibilidade.Patient safety culture assessment allows hospitals to identify and prospectively manage safety issues in work routines. This article aimed to describe the cross-cultural adaptation of the Hospital Survey on Patient Safety Culture (HSOPSC into Brazilian Portuguese. A universalist approach was adopted to assess conceptual, item, and semantic equivalence. The methodology involved the following stages: (1 translation of the questionnaire into Portuguese; (2 back-translation into English; (3 an expert panel to prepare a draft version; and (4 assessment of verbal understanding of the draft by a sample of the target population. The questionnaire was translated into Portuguese, and the scale's final version included 42 items. The target population sample assessed all the items as easy to understand. The questionnaire has been translated into Portuguese and adapted to the Brazilian hospital context, but it is necessary to assess

25. MPA-seminar: safety and reliability of plant technology with special emphasis on safety and reliability - integrity proofs, qualification of components, damage prevention. Vol. 1. Papers 1-29

International Nuclear Information System (INIS)

1999-01-01

The proceedings of the 25th MPA Seminar on 'Safety and Reliability of Plant Technology' were issued in two volumes. The main topics of the first volume are: 1. Structural and safety analysis, 2. Reliability analysis, 3. Fracture mechanics, and 4. Nondestructive Testing. s

CONTAMINATED SOIL VOLUME ESTIMATE TRACKING METHODOLOGY

International Nuclear Information System (INIS)

Durham, L.A.; Johnson, R.L.; Rieman, C.; Kenna, T.; Pilon, R.

2003-01-01

The U.S. Army Corps of Engineers (USACE) is conducting a cleanup of radiologically contaminated properties under the Formerly Utilized Sites Remedial Action Program (FUSRAP). The largest cost element for most of the FUSRAP sites is the transportation and disposal of contaminated soil. Project managers and engineers need an estimate of the volume of contaminated soil to determine project costs and schedule. Once excavation activities begin and additional remedial action data are collected, the actual quantity of contaminated soil often deviates from the original estimate, resulting in cost and schedule impacts to the project. The project costs and schedule need to be frequently updated by tracking the actual quantities of excavated soil and contaminated soil remaining during the life of a remedial action project. A soil volume estimate tracking methodology was developed to provide a mechanism for project managers and engineers to create better project controls of costs and schedule. For the FUSRAP Linde site, an estimate of the initial volume of in situ soil above the specified cleanup guidelines was calculated on the basis of discrete soil sample data and other relevant data using indicator geostatistical techniques combined with Bayesian analysis. During the remedial action, updated volume estimates of remaining in situ soils requiring excavation were calculated on a periodic basis. In addition to taking into account the volume of soil that had been excavated, the updated volume estimates incorporated both new gamma walkover surveys and discrete sample data collected as part of the remedial action. A civil survey company provided periodic estimates of actual in situ excavated soil volumes. By using the results from the civil survey of actual in situ volumes excavated and the updated estimate of the remaining volume of contaminated soil requiring excavation, the USACE Buffalo District was able to forecast and update project costs and schedule. The soil volume

Safety Assessment in Installation of Precast Concrete

Directory of Open Access Journals (Sweden)

Yashrri S.N.

2014-03-01

Full Text Available This study was carried out to identify the safety aspects and the level of safety during the installation process in construction sites. A questionnaire survey and interviews were done to provide data on safety requirements in precast concrete construction. All of the interviews and the research questionnaire survey were conducted among contractors that are registered as class 1 to class 7 with the Construction Industry Development Board (CIDB and class A to class G with Pusat Khidmat Kontraktor (PKK in Penang. Returned questionnaires were analysed with the use of simple percentages and the Likert Scale analysis method to identify safety aspects of precast construction. The results indicate that the safety aspect implemented by companies involved in the precast construction process is at a good level in the safety aspect during bracing, propping, welding and grouting processes and at a very good level of safety in general aspects and safety aspects during lifting processes.

The Oak Ridge Research Reactor: safety analysis: Volume 2, supplement 2

International Nuclear Information System (INIS)

Hurt, S.S.

1986-11-01

The Oak Ridge Research Reactor Safety Analysis was last updated via ORNL-4169, Vol. 2, Supplement 1, in May of 1978. Since that date, several changes have been effected through the change-memo system described below. While these changes have involved the cooling system, the electrical system, and the reactor instrumentation and controls, they have not, for the most part, presented new or unreviewed safety questions. However, some of the changes have been based on questions or recommendations stemming from safety reviews or from reactor events at other sites. This paper discusses those changes which were judged to be safety related and which include revisions to the syphon-break system and changes related to seismic considerations which were very recently completed. The maximum hypothetical accident postulated in the original safety analysis requires dynamic containment and filtered flow for compliance with 10CFR100 limits at the site boundary

NURE aerial gamma-ray and magnetic reconnaissance survey of portions of New Mexico, Arizona and Texas. Volume II. New Mexico-Carlsbad NI 31-11 Quadrangle. Final report

International Nuclear Information System (INIS)

1981-09-01

As part of the Department of Energy (DOE) Nation Uranium Resource Evaluation Program, a rotary-wing high sensitivity radiometric and magnetic survey was flown covering the Carlsbad Quadrangle of the State of New Mexico. The area surveyed consisted of approximately 1732 line miles. The survey was flown with a Sikorsky S58T helicopter equipped with a high sensitivity gamma ray spectrometer which was calibrated at the DOE calibration facilities at Walker Field in Grand Junction, Colorado, and the Dynamic Test Range at Lake Mead, Arizona. Instrumentation and data reduction methods are presented in Volume I of this report. The reduced data is presented in the form of stacked profiles, standard deviation anomaly plots, histogram plots and microfiche listings. The results of the geologic interpretation of the radiometric data together with the profiles, anomaly maps and histograms are presented in this Volume II final report

A GALEX ULTRAVIOLET IMAGING SURVEY OF GALAXIES IN THE LOCAL VOLUME

International Nuclear Information System (INIS)

Lee, Janice C.; Gil de Paz, Armando; Kennicutt, Robert C. Jr; Bothwell, Matthew; Johnson, Benjamin D.; Dalcanton, Julianne; Funes S. J., Jose G.; Sakai, Shoko; Skillman, Evan; Tremonti, Christy; Van Zee, Liese

2011-01-01

We present results from a GALEX ultraviolet (UV) survey of a complete sample of 390 galaxies within ∼11 Mpc of the Milky Way. The UV data are a key component of the composite Local Volume Legacy, an ultraviolet-to-infrared imaging program designed to provide an inventory of dust and star formation in nearby spiral and irregular galaxies. The ensemble data set is an especially valuable resource for studying star formation in dwarf galaxies, which comprise over 80% of the sample. We describe the GALEX survey programs that obtained the data and provide a catalog of far-UV (∼1500 A) and near-UV (∼2200 A) integrated photometry. General UV properties of the sample are briefly discussed. We compute two measures of the global star formation efficiency, the star formation rate (SFR) per unit H I gas mass, and the SFR per unit stellar mass, to illustrate the significant differences that can arise in our understanding of dwarf galaxies when the FUV is used to measure the SFR instead of Hα. We find that dwarf galaxies may not be as drastically inefficient in converting gas into stars as suggested by prior Hα studies. In this context, we also examine the UV properties of late-type dwarf galaxies that appear to be devoid of star formation because they were not detected in previous Hα narrowband observations. Nearly all such galaxies in our sample are detected in the FUV and have FUV SFRs that fall below the limit where the Hα flux is robust to Poisson fluctuations in the formation of massive stars. Otherwise, the UV colors and star formation efficiencies of Hα-undetected, UV-bright dwarf irregulars appear to be relatively unremarkable with respect to those exhibited by the general population of star-forming galaxies.

Self-reported patient safety competence among Canadian medical students and postgraduate trainees: a cross-sectional survey.

Science.gov (United States)

Doyle, Patricia; VanDenKerkhof, Elizabeth G; Edge, Dana S; Ginsburg, Liane; Goldstein, David H

2015-02-01

Quality and patient safety (PS) are critical components of medical education. This study reports on the self-reported PS competence of medical students and postgraduate trainees. The Health Professional Education in Patient Safety Survey was administered to medical students and postgraduate trainees in January 2012. PS dimension scores were compared across learning settings (classroom and clinical) and year in programme. Sixty-three percent (255/406) of medical students and 32% (141/436) of postgraduate trainees responded. In general, both groups were most confident in their learning of clinical safety skills (eg, hand hygiene) and least confident in learning about sociocultural aspects of safety (eg, understanding human factors). Medical students' confidence in most aspects of safety improved with years of training. For some of the more intangible dimensions (teamwork and culture), medical students in their final year had lower scores than students in earlier years. Thirty-eight percent of medical students felt they could approach someone engaging in unsafe practice, and the majority of medical students (85%) and postgraduate trainees (78%) agreed it was difficult to question authority. Our results suggest the need to improve the overall content, structure and integration of PS concepts in both classroom and clinical learning environments. Decreased confidence in sociocultural aspects of PS among medical students in the final year of training may indicate that culture in clinical settings negatively affects students' perceived PS competence. Alternatively, as medical students spend more time in the clinical setting, they may develop a clearer sense of what they do not know. Published by the BMJ Publishing Group Limited. For permission to use (where not already granted under a licence) please go to http://group.bmj.com/group/rights-licensing/permissions.

Volume 1: Survey of Available Information in Support of the Energy-Water Bandwidth Study of Desalination Systems

Energy Technology Data Exchange (ETDEWEB)

Rao, Prakash [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Aghajanzadeh, Arian [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Sheaffer, Paul [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Morrow, William R. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Brueske, Sabine [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Dollinger, Caroline [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Price, Kevin [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Sarker, Prateeti [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Ward, Nicholas [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Cresko, Joe [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States)

2016-10-01

The U.S. Department of Energy (DOE) has set a goal to reduce the cost of seawater desalination systems to $0.50/ cubic meter (m³) through the development of technology pathways to reduce energy, capital, operating, soft, and system integration costs.1 In support of this goal and to evaluate the technology pathways to lower the energy and carbon intensity of desalination while also reducing the total water cost, DOE is undertaking a comprehensive study of the energy consumption and carbon dioxide (CO₂) emissions for desalination technologies and systems. This study is being undertaken in two phases. Phase 1, Survey of Available Information in Support of the Energy-Water Bandwidth Study of Desalination Systems, collected the background information that will underpin Phase 2, the Energy Water Bandwidth Study for Desalination Systems. This report (Volume 1) summarizes the results from Phase 1. The results from Phase 2 will be summarized in Volume 2: Energy Water Bandwidth Study for Desalination Systems (Volume 2). The analysis effort for Phase 2 will utilize similar methods as other industry-specific Energy Bandwidth Studies developed by DOE,2 which has provided a framework to evaluate and compare energy savings potentials within and across manufacturing sectors at the macroscale. Volume 2 will assess the current state of desalination energy intensity and reduction potential through the use of advanced and emerging technologies. For the purpose of both phases of study, energy intensity is defined as the amount of energy required per unit of product water output (for example, kilowatt-hours per cubic meter of water produced). These studies will expand the scope of previous sectorial bandwidth studies by also evaluating CO₂ intensity and reduction opportunities and informing a techno-economic analysis of desalination systems. Volume 2 is expected to be completed in 2017.

Federal Funds for Research and Development: Fiscal Years 1980, 1981, and 1982. Volume XXX. Detailed Statistical Tables. Surveys of Science Resources Series.

Science.gov (United States)

National Science Foundation, Washington, DC.

During the March through July 1981 period a total of 36 Federal agencies and their subdivisions (95 individual respondents) submitted data in response to the Annual Survey of Federal Funds for Research and Development, Volume XXX, conducted by the National Science Foundation. The detailed statistical tables presented in this report were derived…

Survey of numerical safety targets for nuclear power plants

International Nuclear Information System (INIS)

Kelley, A.P. Jr.; Buttemer, D.R.

1981-04-01

The construction of a nuclear power plant implies, as does the construction of any major public work, the acceptance of a finite degree of risk. This risk can be reduced by an increased investment in engineered safeguards. However, at some level of risk, overinvestment in safety can render the project uneconomical. Because of the desirability of fixing safety standards on an absolute basis, there has long been an interest in establishing numerical risk criteria for the design, construction, and operation of nuclear power plants. Interest in the subject of numerical safety goals has recently been intensified by the Three Mile Island Action Plan. The USNRC has been directed by Congress to develop a national safety goal for reactor regulation. This report summarizes actions which have been historically, and are currently, taking place toward establishing national numerical risk targets for reactor regulation. Emphasis is placed upon actions taken, or currently being taken, by federal regulatory agencies and directly associated advisory bodies

What do healthcare workers in elderly care know about occupational health and safety? An explorative survey.

Science.gov (United States)

Schönrock, Stefanie; Schablon, Anja; Nienhaus, Albert; Peters, Claudia

2015-01-01

Demographic changes will lead to a growing demand for healthy, motivated healthcare workers (HCW) in the years ahead. Along with well-targeted prevention, knowledge of occupational health and safety and infection precaution is essential for a healthy working life. In this context back-friendly working methods and protection from infectious diseases are necessary in elderly care. In 2012, a survey was conducted in nine residential and two semi-residential nursing homes, as well as in one home care service in the Schwerin area of northeast Germany. Four hundred and seventy three HCWs were asked to fill in a questionnaire on what they knew about aspects of occupational health and safety such as vaccinations and preventative measures administered by occupational physicians, hygiene, back-friendly working methods and infection prevention. The statistical evaluation was descriptive, with a comparison between job title. Differences were examined with chi square or Fisher's exact test. The response rate was 28 % (n = 132). The largest group of respondents (36 %) were qualified geriatric HCWs. More than 74 % of employees felt well informed about opportunities for precautionary checks and vaccination by occupational physician, and 93 % utilized these opportunities. When it came to assigning modes of transmission to specific infectious diseases, only 23 % of participants were well informed, and one in three (31 %) care assistants was inadequately informed. Fewer than half of participants could correctly name the indications for hand disinfection. Only 66 % of the HCWs said they were aware of training offers for the management of multidrug-resistant organisms in their institution. They did know about possible aids to back-friendly working, although gaps in knowledge were apparent. Only 59 % of respondents knew that care utensils should preferably be stored at working height so as to reduce awkward body postures. Employees in elderly care are well informed about the

Do doctors benefit from their profession?--A survey of medical practitioners' health promotion and health safety practices.

LENUS (Irish Health Repository)

O'Connor, M

1998-12-01

Three hundred Irish Medical Organisation members were surveyed on health promotion and health and safety issues. 64.7% responded (65.3 males; 33.7% < thirty-five years). Over half (54.9%) were aware of the safety legislation and very few reported available occupational health services. A majority wanted more such services. Nearly all believed health promotion was important yet only 35.2% always availed of opportunities to give such advice. 36.3% were often stressed, particularly at work. Alcohol was sometimes or frequently used to cope by around half of respondents. Although less than half (47.7%) used whole milk, one third usually or always added salt to their food. 15.5% took no weekly aerobic exercise but 42.0% claimed to do so three times weekly. 11.4 were current smokers. A third of women had never had a cervical smear. We conclude doctors require adequate occupational health services.

New IAEA guidance on safety culture

International Nuclear Information System (INIS)

Haage, Monica; )

2012-01-01

Monica Haage described a project for Kozloduy Nuclear Power Plant in Bulgaria which was also funded by the Norwegian government. This project included the development of guidance documents and training on self-assessment and continuous improvement of safety culture. A draft IAEA safety culture survey was also developed as part of this project in collaboration with St Mary's University, Canada. This project was conducted in parallel with an IAEA project to develop new safety reports on safety culture self-assessment and continuous improvement. A safety report on safety culture during the pre-operational phases of NPPs has also been drafted. The IAEA approach to safety culture assessment was outlined and core principles of the approach were discussed. These include the use of several assessment methods (survey, interview, observation, focus groups, document review), and two distinct levels of analysis. The first is a descriptive analysis of the observed cultural characteristics from each assessment method and overarching themes. This is followed by a 'normative' analysis comparing what has been observed with the desirable characteristics of a strong, positive, safety culture, as defined by the IAEA safety culture framework. The application of this approach during recent Operational Safety Assessment Review Team (OSART) missions was described along with key learning points

Engaging Employees: The Importance of High-Performance Work Systems for Patient Safety.

Science.gov (United States)

Etchegaray, Jason M; Thomas, Eric J

2015-12-01

To develop and test survey items that measure high-performance work systems (HPWSs), report psychometric characteristics of the survey, and examine associations between HPWSs and teamwork culture, safety culture, and overall patient safety grade. We reviewed literature to determine dimensions of HPWSs and then asked executives to tell us which dimensions they viewed as most important for safety and quality. We then created a HPWSs survey to measure the most important HPWSs dimensions. We administered an anonymous, electronic survey to employees with direct patient care working at a large hospital system in the Southern United States and looked for linkages between HPWSs, culture, and outcomes. Similarities existed for the HPWS practices viewed as most important by previous researchers and health-care executives. The HPWSs survey was found to be reliable, distinct from safety culture and teamwork culture based on a confirmatory factor analysis, and was the strongest predictor of the extent to which employees felt comfortable speaking up about patient safety problems as well as patient safety grade. We used information from a literature review and executive input to create a reliable and valid HPWSs survey. Future research needs to examine whether HPWSs is associated with additional safety and quality outcomes.

Probabilistic safety assessment for instrumentation and control systems in nuclear power plants. A literature survey

International Nuclear Information System (INIS)

Lu, Lixuan; Jiang, Jin

2003-01-01

Deregulation in electricity market will create a great deal of challenges for Nuclear Power Plants (NPP). To stay competitive, NPP will need to find new ways to reduce their operation costs. In NPP, Instrumentation and Control (I and C) systems play an important role in reducing the cost of producing electricity while maintaining and/or enhancing safety. Therefore, it is extremely important that one should manage the I and C systems more efficiently and economically. Meanwhile, obsolescence problem associated with I and C systems encouraged the usage of advanced digital techniques in I and C systems. Thus, new methodologies are needed to analyze the reliability and determine the maintenance strategy for the digital I and C systems. Probabilistic Safety Assessment (PSA) has been probed to be a promising method to deal with this issue. This paper provides a literature survey on the development of digital I and C systems in NPP, followed by a detailed review of PSA including its benefits, limitations and the future direction of its development. Most importantly, potential applications of PSA in various aspects of I and C systems are brought into perspective throughout the paper. Furthermore, the applicability of PSA in the regulation of safety-related I and C systems is demonstrated. Detailed information on PSA applications in 1) the resource allocation for I and C systems: 2) the determination of surveillance testing strategies; and 3) I and C system designs, is provided. (author)

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

Planning for Parent Choice: A Guide to Parent Surveys and Parent Involvement in Planning for Parent and Professional Choice in the Public Schools. [Parent Choice and the Public Schools: Volume 2].

Science.gov (United States)

Clinchy, Evans

This guide, second in a series of four volumes, offers a method of surveying parents' attitudes about choosing schools for their children and provides a survey instrument used over a period of 5 years in four Massachusetts urban school districts. Section 1 introduces the basic research questions pursued in the survey. Section 2, "The Parent…

Client Perceptions of Occupational Health and Safety Management System Assistance Provided by OSHA On-Site Consultation: Results of a Survey of Colorado Small Business Consultation Clients.

Science.gov (United States)

Autenrieth, Daniel A; Brazile, William J; Gilkey, David P; Reynolds, Stephen J; June, Cathy; Sandfort, Del

2015-01-01

The Occupational Safety and Health Administration (OSHA) On-Site Consultation Service provides assistance establishing occupational health and safety management systems (OHSMS) to small businesses. The Safety and Health Program Assessment Worksheet (Revised OSHA Form 33) is the instrument used by consultants to assess an organization's OHSMS and provide feedback on how to improve a system. A survey was developed to determine the usefulness of the Revised OSHA Form 33 from the perspective of Colorado OSHA consultation clients. One hundred and seven clients who had received consultation services within a six-year period responded to the survey. The vast majority of respondents indicated that the Revised OSHA Form 33 accurately reflected their OHSMS and that information provided on the Revised OSHA Form 33 was helpful for improving their systems. Specific outcomes reported by the respondents included increased safety awareness, reduced injuries, and improved morale. The results indicate that the OHSMS assistance provided by OSHA consultation is beneficial for clients and that the Revised OSHA Form 33 can be an effective tool for assessing and communicating OHSMS results to business management. Detailed comments and suggestions provided on the Revised OSHA Form 33 are helpful for clients to improve their OHSMS.

Aerogeophysical survey in Olkiluoto 2009

International Nuclear Information System (INIS)

Kurimo, M.

2009-08-01

This report describes the survey operation, survey and processing methods and the deliverables of an aerogeophysical survey in Olkiluoto area in May 2009. The survey was conducted by Geological Survey of Finland (GTK). The survey aircraft was a twin-engine Twin Otter operated by Finnish Aviation Academy (SIO) and owned by Natural Environment Research Council / British Geological Survey (NERC / BGS), with whom GTK has established a joint venture called Joint Airborne-geoscience Capability (JAC). The survey was conducted in May 2009 between May 5th and May 18th. The survey consists of ten separate survey flights and two magnetic calibration flights. The survey was based in Pori airport. Survey line spacing was 50 meters and nominal survey altitude was 30 meters. Measurements were completed in May 2009, and data processing and reporting was done in June 2009. Two cesium magnetometers installed onboard the aircraft (at the left wingtip and in a nose cone) were measuring the magnetic total field intensity during the survey flights. An automatic compensation unit corrected the aircraft attitude errors in the magnetic data in real time. The four-frequency electromagnetic (EM) unit included four transmitter coils with amplifiers in right wingtip and four receiver coils in left wingtip. Frequencies were 900 Hz, 3 kHz, 14 kHz and 24.5 kHz. The gamma spectrometer with two crystal packages (total volume 42 litres) measured the 256 channel energy spectra. In addition, auxiliary parameters such as flight altitude and aircraft attitude were also recorded simultaneously. Reference ground base station was used for recording the temporal variations in the magnetic field and also reference data for post-positioning of coordinate information. In the post-processing phase, heading correction, base station correction and microlevelling procedures were applied to the magnetic data. The EM data and radiometric data were corrected with calibration coefficients and levelled. The data was

Study of industry safety management

International Nuclear Information System (INIS)

Park, Pil Su

1987-06-01

This book deals with general remarks, industrial accidents, statistics of industrial accidents, unsafe actions, making machinery and facilities safe, safe activities, having working environment safe, survey of industrial accidents and analysis of causes, system of safety management and operations, safety management planning, safety education, human engineering such as human-machines system, system safety, and costs of disaster losses. It lastly adds individual protective equipment and working clothes including protect equipment for eyes, face, hands, arms and feet.

A survey of radiation safety training among South African interventionalists

Directory of Open Access Journals (Sweden)

A Rose

2018-04-01

Full Text Available Background. Ionising radiation is increasingly being used in modern medicine for diagnostic, interventional and therapeutic purposes. There has been an improvement in technology, resulting in lower doses being emitted. However, an increase in the number of procedures has led to a greater cumulative dose for patients and operators, which places them at increased risk of the effects of ionising radiation. Radiation safety training is key to optimising medical practice.Objective. To present the perceptions of South African interventionalists on the radiation safety training they received and to offer insights into the importance of developing and promoting such training programmes for all interventionalists.Methods. In this cross-sectional study, we collected data from interventionalists (N=108 using a structured questionnaire.Results. All groups indicated that radiation exposure in the workplace is important (97.2%. Of the participants, the radiologists received the most training (65.7%. Some participants (44.1% thought that their radiation safety training was adequate. Most participants (95.4% indicated that radiation safety should be part of their training curriculum. Few (34.3% had received instruction on radiation safety when they commenced work. Only 62% had been trained on how to protect patients from ionising radiation exposure.Conclusion. Radiation safety training should be formalised in the curriculum of interventionalists’ training programmes, as this will assist in stimulating a culture of radiation protection, which in turn will improve patient safety and improve quality of care.

Unresolved safety issues summary. Volume 3, Number 3. Aqua book

International Nuclear Information System (INIS)

1981-01-01

The 'Unresolved Safety Issues' summary is designed to provide the management of the Nuclear Regulatory Commission with a quarterly overview of the progress and plans for completion of generic tasks addressing Unresolved Safety Issues reported to Congress pursuant to section 210 of The Energy Reorganization Act of 1974 as amended. This summary utilizes data collected from the Office of Nuclear Reactor Regulation, Office of Nuclear Regulatory Research, and the National Laboratories and is prepared by the office of Management and Program Analysis. The definition of what constitutes completion of an unresolved safety issue (USI) has recently been expanded to include the implementation of the technical resolution. This is in acknowledgement of the fact that real safety benefits occur only after the implementation has taken place. The schedules in this book include a milestone at the end of each action plan which represents the initiation of the implementation process both with respect to incorporation of the technical resolution in the NRC official guidance or requirements and also the application of changes to individual operating plants. The schedule for implementation will not normally be included in the task action plan(s) for the resolution of a USI since the nature and extent of the activities necessary to accomplish the implementation cannot normally be reasonably determined prior to the determination of a technical resolution. The progress and status for implementation of unresolved safety issues for which a technical resolution has been completed are reported specifically in a separate table provided in this summary

Status of safety issues at licensed power plants

International Nuclear Information System (INIS)

1991-05-01

As part of ongoing US Nuclear Regulatory Commission (NRC) efforts to ensure the quality and accountability of safety issue information, a program has been established whereby an annual NUREG report will be published on the status of licensee implementation and NRC verification of safety issues in major NRC requirement areas. This report, the second volume of a three-volume series, addresses the status of unresolved safety issues (USIs) at licensed plants. The data contained in these NUREG reports are a product of the NRC's Safety Issues Management System (SIMS) database, which is maintained by the Project Management Staff in the Office of Nuclear Reactor Regulation and by NRC regional personnel. The purpose of this report is to provide a comprehensive description of the status of implementation and verification of the 27 safety issues designated as USIs and to make this information available to other interested parties, including the public. A corollary purpose of this NUREG report is to serve as a follow-on to NUREG-0933, ''A Prioritization of Generic Safety Issues,'' which tracks safety issues up until requirements are approved for imposition at licensed plants. 3 figs., 4 tabs

A survey of costs incurred in U.K. X-ray diffraction research laboratories as a consequence of proposed regulations for radiological safety

International Nuclear Information System (INIS)

Blow, D.M.

1981-01-01

A small survey of British X-ray diffraction laboratories was undertaken, with the aim of discovering the effects of the Health and Safety at Work Act (1974) and the draft regulations on radiological protection and ionising radiations (1978) on the practice of X-ray crystallography. The responses lead to the conclusion that the average cost incurred in bringing X-ray diffraction equipment to a safety standard compatible with the draft regulations (as judged by the respondents) will exceed Pound2,000 per X-ray generator. The safety costs will represent an overhead charge of at least 15-18% on the purchase of an X-ray generator, requiring additional capital outlay of over Pound5m to maintain the current level of X-ray diffraction activity in the U.K. There seems to be no evidence of a high accident rate with diffraction equipment, and the cost of the safety precautions bears no relation to the risks involved. (author)

Application of the MERIT survey in the multi-criteria quality assessment of occupational health and safety management.

Science.gov (United States)

Korban, Zygmunt

2015-01-01

Occupational health and safety management systems apply audit examinations as an integral element of these systems. The examinations are used to verify whether the undertaken actions are in compliance with the accepted regulations, whether they are implemented in a suitable way and whether they are effective. One of the earliest solutions of that type applied in the mining industry in Poland involved the application of audit research based on the MERIT survey (Management Evaluation Regarding Itemized Tendencies). A mathematical model applied in the survey facilitates the determination of assessment indexes WOPi for each of the assessed problem areas, which, among other things, can be used to set up problem area rankings and to determine an aggregate (synthetic) assessment. In the paper presented here, the assessment indexes WOPi were used to calculate a development measure, and the calculation process itself was supplemented with sensitivity analysis.

Fire safety engineering

International Nuclear Information System (INIS)

Smith, D.N.

1989-01-01

The periodic occurrence of large-scale, potentially disastrous industrial accidents involving fire in hazardous environments such as oilwell blowouts, petrochemical explosions and nuclear installations highlights the need for an integrated approach to fire safety engineering. Risk reduction 'by design' and rapid response are of equal importance in the saving of life and property in such situations. This volume of papers covers the subject thoroughly, touching on such topics as hazard analysis, safety design and testing, fire detection and control, and includes studies of fire hazard in the context of environment protection. (author)

Report on transparency and nuclear safety - Grenoble CEA centre - 2012

International Nuclear Information System (INIS)

2013-01-01

This report presents the different nuclear base installations (INB) of the Grenoble CEA centre, gives an overview of measures regarding safety within these installations (organisation, general arrangements, human and organizational factors, arrangements related to different risks, management of emergency situations, inspections, audits and second-level controls, arrangements and main events specific to the different installations and buildings) and of measures related to radiation protection (organisation and results, main events). It reports the significant events related to safety and radiation protection which occurred in 2012 and were declared to the ASN, and discusses how the return-on-experience has been used. It reports and comments the results of measurements of radiological and chemical gaseous and liquid effluents, of surveys of the environment. It also presents the environmental management approach. The next part addresses the management of radioactive wastes which are warehoused on this site: arrangements aimed at limiting their volume, and at limiting their impact on health and on the environment, waste production and removal, nature and quantities of warehoused wastes. Remarks and recommendations of the CHSCT are given

Nuclear safety. Technical progress journal, January--March 1996: Volume 37, No. 1

Energy Technology Data Exchange (ETDEWEB)

Muhlheim, M D [ed.

1996-01-01

Nuclear Safety is a journal that covers significant issues in the field of nuclear safety. Its primary scope is safety in the design, construction, operation, and decommissioning of nuclear power reactors worldwide and the research and analysis activities that promote this goal, but is also encompasses the safety aspects of the entire nuclear fuel cycle, including fuel fabrication, spent-fuel processing and handling, and nuclear waste disposal, the handling of fissionable materials and radioisotopes, and the environmental effects of all these activities. Individual articles are indexed separately for the data base.

Small business owners' health and safety intentions: A cross-sectional survey

Directory of Open Access Journals (Sweden)

Li Shelby

2005-10-01

Full Text Available Abstract Background Little is known about the variables underlying small business owners' behavioural intentions toward workplace health and safety. This project explores the relationship between three mediating variables (Attitude Toward Safety, Subjective Norm and Perceived Behavioural Control and owners' Intentions Toward Safety, following the Theory of Planned Behaviour. We also investigate the role of beliefs underlying each mediating variable. Methods Seven hundred businesses (5–50 employees were randomly selected from 4084 eligible companies in a manufacturing business database (SIC codes 24 to 39. The 348 respondents are on average 51 yrs of age, 86% male, 96% white and have 2 to 4 years of post-secondary school. Results All three mediator variables are significantly correlated with Intentions Toward Safety; Attitude Toward Safety shows the strongest correlation, which is confirmed by path analysis. Owners with higher attitudes toward safety have a higher probability of believing that improving workplace health and safety will make employees' healthier and happier, show that they care, increase employee productivity, lower workers' compensation costs, increase product quality and lower costs. Conclusion These results suggest that interventions aimed at increasing owners' health and safety intentions (and thus, behaviours should focus on demonstrating positive employee health and product quality outcomes.

AGI Safety Literature Review

OpenAIRE

Everitt, Tom; Lea, Gary; Hutter, Marcus

2018-01-01

The development of Artificial General Intelligence (AGI) promises to be a major event. Along with its many potential benefits, it also raises serious safety concerns (Bostrom, 2014). The intention of this paper is to provide an easily accessible and up-to-date collection of references for the emerging field of AGI safety. A significant number of safety problems for AGI have been identified. We list these, and survey recent research on solving them. We also cover works on how best to think of ...

1987 Oak Ridge model conference: Proceedings: Volume 3, Health and safety

International Nuclear Information System (INIS)

1987-01-01

See the abstract for Volume I for general information on the conference. Topics discussed in Volume III include the use of models in handling hazardous materials, communication at waste sites, asbestos, regulatory decisions, emergency planning, training programs, occupational hazards, and protection of subcontractors

Current safety practices in nano-research laboratories in China.

Science.gov (United States)

Zhang, Can; Zhang, Jing; Wang, Guoyu

2014-06-01

China has become a key player in the global nanotechnology field, however, no surveys have specifically examined safety practices in the Chinese nano-laboratories in depth. This study reports results of a survey of 300 professionals who work in research laboratories that handle nanomaterials in China. We recruited participants at three major nano-research laboratories (which carry out research in diverse fields such as chemistry, material science, and biology) and the nano-chemistry session of the national meeting of the Chinese Chemical Society. Results show that almost all nano-research laboratories surveyed had general safety regulations, whereas less than one third of respondents reported having nanospecific safety rules. General safety measures were in place in most surveyed nano-research laboratories, while nanospecific protective measures existed or were implemented less frequently. Several factors reported from the scientific literature including nanotoxicology knowledge gaps, technical limitations on estimating nano-exposure, and the lack of nano-occupational safety legislation may contribute to the current state of affairs. With these factors in mind and embracing the precautionary principle, we suggest strengthening or providing nanosafety training (including raising risk awareness) and establishing nanosafety guidelines in China, to better protect personnel in the nano-workplace.

Blanket comparison and selection study. Volume II

International Nuclear Information System (INIS)

1983-10-01

This volume contains extensive data for the following chapters: (1) solid breeder tritium recovery, (2) solid breeder blanket designs, (3) alternate blanket concept screening, and (4) safety analysis. The following appendices are also included: (1) blanket design guidelines, (2) power conversion systems, (3) helium-cooled, vanadium alloy structure blanket design, (4) high wall loading study, and (5) molten salt safety studies

Safety climate practice in Korean manufacturing industry

International Nuclear Information System (INIS)

Baek, Jong-Bae; Bae, Sejong; Ham, Byung-Ho; Singh, Karan P.

2008-01-01

Safety climate survey was sent to 642 plants in 2003 to explore safety climate practices in the Korean manufacturing plants, especially in hazardous chemical treating plants. Out of 642 plants contacted 195 (30.4%) participated in the surveys. Data were collected by e-mail using SQL-server and mail. The main objective of this study was to explore safety climate practices (level of safety climate and the underlying problems). In addition, the variables that may influence the level of safety climate among managers and workers were explored. The questionnaires developed by health and safety executive (HSE) in the UK were modified to incorporate differences in Korean culture. Eleven important factors were summarized. Internal reliability of these factors was validated. Number of employees in the company varied from less than 30 employees (9.2%) to over 1000 employees (37.4%). Both managers and workers showed generally high level of safety climate awareness. The major underlying problems identified were inadequate health and safety procedures/rules, pressure for production, and rule breaking. The length of employment was a significant contributing factor to the level of safety climate. In this study, participants showed generally high level of safety climate, and length of employment affected the differences in the level of safety climate. Managers' commitment to comply safety rules, procedures, and effective safety education and training are recommended

Safety climate practice in Korean manufacturing industry.

Science.gov (United States)

Baek, Jong-Bae; Bae, Sejong; Ham, Byung-Ho; Singh, Karan P

2008-11-15

Safety climate survey was sent to 642 plants in 2003 to explore safety climate practices in the Korean manufacturing plants, especially in hazardous chemical treating plants. Out of 642 plants contacted 195 (30.4%) participated in the surveys. Data were collected by e-mail using SQL-server and mail. The main objective of this study was to explore safety climate practices (level of safety climate and the underlying problems). In addition, the variables that may influence the level of safety climate among managers and workers were explored. The questionnaires developed by health and safety executive (HSE) in the UK were modified to incorporate differences in Korean culture. Eleven important factors were summarized. Internal reliability of these factors was validated. Number of employees in the company varied from less than 30 employees (9.2%) to over 1000 employees (37.4%). Both managers and workers showed generally high level of safety climate awareness. The major underlying problems identified were inadequate health and safety procedures/rules, pressure for production, and rule breaking. The length of employment was a significant contributing factor to the level of safety climate. In this study, participants showed generally high level of safety climate, and length of employment affected the differences in the level of safety climate. Managers' commitment to comply safety rules, procedures, and effective safety education and training are recommended.

Safety climate practice in Korean manufacturing industry

Energy Technology Data Exchange (ETDEWEB)

Baek, Jong-Bae [Department of Safety Engineering, Chungju National University, Chungju 380-702 (Korea, Republic of); Bae, Sejong [Department of Biostatistics, University of North Texas Health Science Center, 3500 Camp Bowie Boulevard, Fort Worth, TX 76107 (United States)], E-mail: sbae@hsc.unt.edu; Ham, Byung-Ho [Department of Industrial Safety, Ministry of Labor (Korea, Republic of); Singh, Karan P. [Department of Biostatistics, University of North Texas Health Science Center, 3500 Camp Bowie Boulevard, Fort Worth, TX 76107 (United States)

2008-11-15

Safety climate survey was sent to 642 plants in 2003 to explore safety climate practices in the Korean manufacturing plants, especially in hazardous chemical treating plants. Out of 642 plants contacted 195 (30.4%) participated in the surveys. Data were collected by e-mail using SQL-server and mail. The main objective of this study was to explore safety climate practices (level of safety climate and the underlying problems). In addition, the variables that may influence the level of safety climate among managers and workers were explored. The questionnaires developed by health and safety executive (HSE) in the UK were modified to incorporate differences in Korean culture. Eleven important factors were summarized. Internal reliability of these factors was validated. Number of employees in the company varied from less than 30 employees (9.2%) to over 1000 employees (37.4%). Both managers and workers showed generally high level of safety climate awareness. The major underlying problems identified were inadequate health and safety procedures/rules, pressure for production, and rule breaking. The length of employment was a significant contributing factor to the level of safety climate. In this study, participants showed generally high level of safety climate, and length of employment affected the differences in the level of safety climate. Managers' commitment to comply safety rules, procedures, and effective safety education and training are recommended.

The value of safety indicators

NARCIS (Netherlands)

Kampen, J. van; Beek, B.D. van der; Groeneweg, J.

2013-01-01

Organisations are looking for ways to gain insight into the level of safety in their company so that additional measures can be taken when necessary and the effectiveness of interventions can be measured. That said, measuring safety, health and the environment is not easy. A survey among members of

The value of safety indicators

NARCIS (Netherlands)

Kampen, J. van; Beek, D. van der; Groeneweg, J.

2014-01-01

Organizations are searching for ways to gain insight into the level of safety in their company so that additional measures can be taken when necessary, and so the effectiveness of interventions can be measured. That said, measuring safety, health, and the environment is not easy. A survey among

Gross tumor volume and clinical target volume: soft-tissue sarcoma of the extremities

International Nuclear Information System (INIS)

Lartigau, E.; Kantor, G.; Lagarde, P.; Taieb, S.; Ceugnart, L.; Vilain, M.O.; Penel, N.; Depadt, G.

2001-01-01

Soft tissue sarcomas of the extremities are currently treated with more conservative and functional approaches, combining surgery, radiotherapy and chemotherapy. The role of external beam radiotherapy and brachytherapy has been defined through randomized studies performed in the 80's and 90's. However, the ubiquity of tumour location for these tumours makes difficult a systematic definition of local treatments. Tumour volume definition is based on pre and post surgical imaging (MRI) and on described pathological report. The clinical target volume will take into account quality of the resection and anatomical barriers and will be based on an anatomy and not only on safety margins around the tumour bed. General rules for this irradiation (doses, volumes) and principal results will be presented. (authors)

The Energy Information Administration`s assessment of reformulated gasoline. Volume 1

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-09-28

This report is divided into two volumes. The first volume contains EIA`s findings and analyses on reformulated gasoline as it affects the petroleum industry. The data contained herein should assist members of the Congress, Federal, State and local governments, analysts, researchers, the media and academia to understand the RFG program and the current status of implementation. This second volume contains 10 appendices that include letter from Congressman Dingell, survey results, survey forms, and historical summary data. A glossary and a list of acronyms and abbreviations are printed in Volumes 1 and 2.

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

Science.gov (United States)

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

2010-10-01

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

Safety Culture Perceptions in a Collegiate Aviation Program: A Systematic Assessment

OpenAIRE

Adjekum, Daniel Kwasi

2014-01-01

An assessment of the perceptions of respondents on the safety culture at an accredited Part 141 four year collegiate aviation program was conducted as part of the implementation of a safety management system (SMS). The Collegiate Aviation Program Safety Culture Assessment Survey (CAPSCAS), which was modified and revalidated from the existing Commercial Aviation Safety Survey (CASS), was used. Participants were drawn from flight students and certified flight instructors in the program. The sur...

Radiological impacts analysis with use of new endpoint as complementary safety indicators

International Nuclear Information System (INIS)

Peralta Vital, J.L.; Gil Castillo, R.; Fleitas Estevez, G.G.; Olivera Acosta, J.

2015-01-01

The paper shows the new safety indicators on risk assessment (safety assessment) to radioactive waste environmental management implementation (concentrations and fluxes of naturally occurring radioactive materials (NORM)). The endpoint obtained, allow the best analysis of the radiological impact associated to radioactive waste isolation system. The common safety indicators for safety assessment purpose, dose and risk, are very time dependent, increasing the uncertainties in the results for long term assessment. The complementary and new proposed endpoints are more stable and they are not affected by changes in the critical group, pathways, etc. The NORM values on facility site were obtained as result of national surveys, the natural concentrations of U, Ra, Th, K has been associated with the variation of the lithologies in 3 geographical areas of the Country (Occidental, Central and Oriental). The results obtained are related with the safety assessment topics and allowed to apply the new complementary safety indicators, by comparisons between the natural concentrations and fluxes on site and its calculated values for the conceptual repository design. In order to normalize the concentration results, the analysis was realized adopting the criteria of the Repository Equivalent Rock Volume (RERV). The preliminary comparison showed that the calculated concentrations and fluxes in the Cuban conceptual radioactive waste repository are not higher than the natural values in the host rock. According to the application of new safety indicators, the reference disposal facility does not increase the natural activity concentration and fluxes in the environment. In order to implement these new safety indicator it has been used the current 226 Ra inventory of the Repository and the 226 Ra as natural concentration on the site. (authors)

An application of the Pareto method in surveys to diagnose managers' and workers' perception of occupational safety and health on selected Polish construction sites.

Science.gov (United States)

Obolewicz, Jerzy; Dąbrowski, Andrzej

2017-11-16

The construction industry is an important sector of the economy in Poland. According to the National Labour Inspectorate (PIP) data of 2014, the number of victims of fatal accidents in the construction sector amounted to 80 as compared with 187 injured in all other sectors of economy in Poland. This article presents the results of surveys on the impact of construction worker behaviour on the occupational safety and health outcomes. The surveys took into account the point of view of both construction site management (tactical level) and construction workers (operational level). For the analysis of results, the method of numerical taxonomy and Pareto charts was employed, which allowed the authors to identify the areas of occupational safety and health at both an operational and a tactical level, in which improvement actions needed to be proposed for workers employed in micro, small, medium and large construction enterprises.

Safety monitoring in process and control

International Nuclear Information System (INIS)

Esparza, V. Jr.; Sebo, D.E.

1984-01-01

Safety Functions provide a method of ensuring the safe operation of any large-scale processing plant. Successful implementation of safety functions requires continuous monitoring of safety function values and trends. Because the volume of information handled by a plant operator occassionally can become overwhelming, attention may be diverted from the primary concern of maintaining plant safety. With this in mind EG and G, Idaho developed various methods and techniques for use in a computerized Safety Function Monitoring System and tested the application of these techniques using a simulated nuclear power plant, the Loss-of-Fluid Test Facility (LOFT) at the Idaho National Engineering Laboratory (INEL). This paper presents the methods used in the development of a Safety Function Monitoring System

Unresolved safety issues summary. Aqua Book. Volume 6, No. 3

International Nuclear Information System (INIS)

Butts, J.

1984-01-01

The unresolved safety issues summary is designed to provide the management of the Nuclear Regulatory Commission with a quarterly overview of the progress and plans for completion of generic tasks addressing unresolved safety issues reported to Congress pursuant to Section 210 of the Energy Reorganization Act of 1974 as amended. This summary utilizes data collected from the Office of Nuclear Reactor Regulation, Office of Nuclear Regulatory Research, and the national laboratories and is prepared by the Office of Nuclear Reactor Regulation

Safety analysis of urban signalized intersections under mixed traffic.

Science.gov (United States)

S, Anjana; M V L R, Anjaneyulu

2015-02-01

This study examined the crash causative factors of signalized intersections under mixed traffic using advanced statistical models. Hierarchical Poisson regression and logistic regression models were developed to predict the crash frequency and severity of signalized intersection approaches. The prediction models helped to develop general safety countermeasures for signalized intersections. The study shows that exclusive left turn lanes and countdown timers are beneficial for improving the safety of signalized intersections. Safety is also influenced by the presence of a surveillance camera, green time, median width, traffic volume, and proportion of two wheelers in the traffic stream. The factors that influence the severity of crashes were also identified in this study. As a practical application, the safe values of deviation of green time provided from design green time, with varying traffic volume, is presented in this study. This is a useful tool for setting the appropriate green time for a signalized intersection approach with variations in the traffic volume. Copyright © 2014 Elsevier Ltd. All rights reserved.

Computer aided safety analysis 1989

International Nuclear Information System (INIS)

1990-04-01

The meeting was conducted in a workshop style, to encourage involvement of all participants during the discussions. Forty-five (45) experts from 19 countries, plus 22 experts from the GDR participated in the meeting. A list of participants can be found at the end of this volume. Forty-two (42) papers were presented and discussed during the meeting. Additionally an open discussion was held on the possible directions of the IAEA programme on Computer Aided Safety Analysis. A summary of the conclusions of these discussions is presented in the publication. The remainder of this proceedings volume comprises the transcript of selected technical papers (22) presented in the meeting. It is the intention of the IAEA that the publication of these proceedings will extend the benefits of the discussions held during the meeting to a larger audience throughout the world. The Technical Committee/Workshop on Computer Aided Safety Analysis was organized by the IAEA in cooperation with the National Board for Safety and Radiological Protection (SAAS) of the German Democratic Republic in Berlin. The purpose of the meeting was to provide an opportunity for discussions on experiences in the use of computer codes used for safety analysis of nuclear power plants. In particular it was intended to provide a forum for exchange of information among experts using computer codes for safety analysis under the Technical Cooperation Programme on Safety of WWER Type Reactors (RER/9/004) and other experts throughout the world. A separate abstract was prepared for each of the 22 selected papers. Refs, figs tabs and pictures

A Survey of Occupational Safety & Health Libraries in the United States.