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Sample records for safety question usq

  1. A refined safety analysis approach for closure of the Hanford Site flammable gas unreviewed safety question

    International Nuclear Information System (INIS)

    Bratzel, D.R.

    1997-01-01

    Following a 1990 investigation into flammable gas generation, retention, and release mechanisms within the Hanford Site high-level waste tanks, personnel concluded that the existing Authorization Basis documentation did not adequately evaluate flammable gas hazards. This declaration was based primarily on the fact that personnel did not adequately consider hydrogen and nitrous oxide evolution within the material in certain waste tanks and subsequent hypothetical ignition in the development of safety documentation for the waste tanks. The US Department of Energy-Headquarters subsequently declared an Unreviewed Safety Question (USQ). Although work scope has been focused on closure of the USQ since 1990, the DOE has yet to close the USQ because of considerable uncertainty regarding essential technical parameters and associated risk. The DOE recently approved a Basis for Interim Operation to revise the Authorization Basis for managing the tank farms, however, the USQ remains open. The two fundamental requirements for closure of the flammable gas USQ are as follows: development of a defensible technical basis for existing controls; development of a process to assess the adequacy of controls as the waste tank mission progresses

  2. Closure of 324 Facility potential HEPA filter failure unreviewed safety questions

    International Nuclear Information System (INIS)

    Enghusen, M.B.

    1997-01-01

    This document summarizes the activities which occurred to resolve an Unreviewed Safety Question (USQ) for the 324 Facility [Waste Technology Engineering Laboratory] involving Potential HEPA Filter Breach. The facility ventilation system had the capacity to fail the HEPA filters during accident conditions which would totally plug the filters. The ventilation system fans were modified which lowered fan operating parameters and prevented HEPA filter failures which might occur during accident conditions

  3. Closure of the condensed-phase organic-nitrate reaction unreviewed safety question at Hanford site

    International Nuclear Information System (INIS)

    COWLEY, W.L.

    1999-01-01

    A discovery Unreviewed Safety Question (USQ) was declared on the underground waste storage tanks at the Hanford Site in May 1996. The USQ was for condensed-phase organic-nitrate reactions (sometimes called organic complexant reactions) in the tanks. This paper outlines the steps taken to close the USQ, and resolve the related safety issue. Several processes were used at the Hanford Site to extract and/or process plutonium. These processes resulted in organic complexants (for chelating multivalent cations) and organic extraction solvents being sent to the underground waste storage tanks. This paper addresses the organic complexant hazard. The organic complexants are in waste matrices that include inert material, diluents, and potential oxidizers. In the presence of oxidizing material, the complexant salts can be made to react exothermically by heating to high temperatures or by applying an external ignition source of sufficient energy. The first organic complexant hazard assessments focused on determining whether a hulk runaway reaction could occur, similar to the 1957 accident at Kyshtm (a reprocessing plant in the former U.S.S.R.). Early analyses (1977 through 1994) examined organic-nitrate reaction onset temperatures and concluded that a bulk runaway reaction could not occur at the Hanford Site because tank temperatures were well below that necessary for bulk runaway. Therefore, it was believed that organic-nitrate reactions were adequately described in the then current Authorization Basis (AB). Subsequent studies examined a different accident scenario, propagation resulting from an external ignition source (e.g., lightning or welding slag) that initiates a combustion front that propagates through the organic waste. A USQ evaluation determined that localized high energy ignition sources were credible, and that point source ignition of organic complexant waste was not adequately addressed i n the then existing AB. Consequently, the USQ was declared on the

  4. Safety assessment for the above ground storage of Cadmium Safety and Control Rods at the Solid Waste Management Facility

    International Nuclear Information System (INIS)

    Shaw, K.W.

    1993-11-01

    The mission of the Savannah River Site is changing from radioisotope production to waste management and environmental restoration. As such, Reactor Engineering has recently developed a plan to transfer the safety and control rods from the C, K, L, and P reactor disassembly basin areas to the Transuranic (TRU) Waste Storage Pads for long-term, retrievable storage. The TRU pads are located within the Solid Waste Management Facilities at the Savannah River Site. An Unreviewed Safety Question (USQ) Safety Evaluation has been performed for the proposed disassembly basin operations phase of the Cadmium Safety and Control Rod Project. The USQ screening identified a required change to the authorization basis; however, the Proposed Activity does not involve a positive USQ Safety Evaluation. A Hazard Assessment for the Cadmium Safety and Control Rod Project determined that the above-ground storage of the cadmium rods results in no change in hazard level at the TRU pads. A Safety Assessment that specifically addresses the storage (at the TRU pads) phase of the Cadmium Safety and Control Rod Project has been performed. Results of the Safety Assessment support the conclusion that a positive USQ is not involved as a result of the Proposed Activity

  5. Unreviewed safety question evaluation of 100 K West fuel canister gas and liquid sampling

    International Nuclear Information System (INIS)

    Alwardt, L.D.

    1995-01-01

    The purpose of this report is to provide the basis for answers to an Unreviewed Safety Question (USQ) safety evaluation for the gas and liquid sampling activities associated with the fuel characterization program at the 100 K West (KW) fuel storage basin. The scope of this safety evaluation is limited to the movement of canisters between the main storage basin, weasel pit, and south loadout pit transfer channel (also known as the decapping station); gas and liquid sampling of fuel canisters in the weasel pit; mobile laboratory preliminary sample analysis in or near the 105 KW basin building; and the placement of sample containers in an approved shipping container. It was concluded that the activities and potential accident consequences associated with the gas and liquid sampling of 100 KW fuel canisters are bounded by the current safety basis documents and do not constitute an Unreviewed Safety Question

  6. Safety assessment of discharge chute isolation barrier preparation and installation activities. Revision 3

    International Nuclear Information System (INIS)

    Meichle, R.H.

    1994-01-01

    This revision adds a section addressing impacts of dropping surfacing tool and rack cutter on the basin floor, and corrects typographical errors. The safety assessment is made for the activities for the preparation and installation of the discharge chute isolation barriers. The safety assessment includes a hazard assessment and comparisons of potential accidents/events to those addressed by the current safety basis documentation. No significant hazards were identified. An evaluation against the USQ evaluation questions was made and the determination made that the activities do not represent a USQ. Hazard categorization techniques were used to provide a basis for readiness review classifications

  7. Ferrocyanide Safety Program: Safety criteria for ferrocyanide watch list tanks

    International Nuclear Information System (INIS)

    Postma, A.K.; Meacham, J.E.; Barney, G.S.

    1994-01-01

    This report provides a technical basis for closing the ferrocyanide Unreviewed Safety Question (USQ) at the Hanford Site. Three work efforts were performed in developing this technical basis. The efforts described herein are: 1. The formulation of criteria for ranking the relative safety of waste in each ferrocyanide tank. 2. The current classification of tanks into safety categories by comparing available information on tank contents with the safety criteria; 3. The identification of additional information required to resolve the ferrocyanide safety issue

  8. Safety assessment of discharge chute isolation barrier preparation and installation

    International Nuclear Information System (INIS)

    Meichle, R.H.

    1994-01-01

    This analysis examines activities associated with the installation of isolation barriers in the K Basins at the Hanford Reservation. This revision adds evaluation of barrier drops on stored fuel and basin floor, identifies fuel which will be moved and addresses criticality issues with sludge. The safety assessment is made for the activities for the preparation and installation of the discharge chute isolation barriers. The safety assessment includes a hazard assessment and comparisons of potential accidents/events to those addressed by the current safety basis documentation. No significant hazards were identified. An evaluation against the USQ evaluation questions was made and the determination made that the activities do not represent a USQ. Hazard categorization techniques were used to provide a basis for readiness review classifications

  9. Strategy for resolution of the flammable gas safety issue

    International Nuclear Information System (INIS)

    Johnson, G.D.

    1997-01-01

    This document provides a strategy for resolution of the Flammable Gas Safety Issue. It defines the key elements required for the following: Closing the Flammable Gas Unreviewed Safety Question (USQ); Providing the administrative basis for resolving the safety issue; Defining the data needed to support these activities; and Providing the technical and administrative path for removing tanks from the Watch List

  10. Strategy for resolution of the flammable gas safety issue

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, G.D.

    1997-05-23

    This document provides a strategy for resolution of the Flammable Gas Safety Issue. It defines the key elements required for the following: Closing the Flammable Gas Unreviewed Safety Question (USQ); Providing the administrative basis for resolving the safety issue; Defining the data needed to support these activities; and Providing the technical and administrative path for removing tanks from the Watch List.

  11. Safety analysis of exothermic reaction hazards associated with the organic liquid layer in tank 241-C-103

    International Nuclear Information System (INIS)

    Postma, A.K.; Bechtold, D.B.; Borsheim, G.L.; Grisby, J.M.; Guthrie, R.L.; Kummerer, M.; Turner, D.A.; Plys, M.G.

    1994-03-01

    Safety hazards associated with the interim storage of a potentially flammable organic liquid in waste Tank C-103 are identified and evaluated. The technical basis for closing the unreviewed safety question (USQ) associated with the floating liquid organic layer in this tank is presented

  12. Safety analysis of exothermic reaction hazards associated with the organic liquid layer in tank 241-C-103

    Energy Technology Data Exchange (ETDEWEB)

    Postma, A.K.; Bechtold, D.B.; Borsheim, G.L.; Grisby, J.M.; Guthrie, R.L.; Kummerer, M.; Turner, D.A. [Westinghouse Hanford Co., Richland, WA (United States); Plys, M.G. [Fauske and Associates, Inc., Burr Ridge, IL (United States)

    1994-03-01

    Safety hazards associated with the interim storage of a potentially flammable organic liquid in waste Tank C-103 are identified and evaluated. The technical basis for closing the unreviewed safety question (USQ) associated with the floating liquid organic layer in this tank is presented.

  13. Using Addenda in Documented Safety Analysis Reports

    International Nuclear Information System (INIS)

    Swanson, D.S.; Thieme, M.A.

    2003-01-01

    This paper discusses the use of addenda to the Radioactive Waste Management Complex (RWMC) Documented Safety Analysis (DSA) located at the Idaho National Engineering and Environmental Laboratory (INEEL). Addenda were prepared for several systems and processes at the facility that lacked adequate descriptive information and hazard analysis in the DSA. They were also prepared for several new activities involving unreviewed safety questions (USQs). Ten addenda to the RWMC DSA have been prepared since the last annual update

  14. 10CFR50.59 safety evaluation training and expert system development

    International Nuclear Information System (INIS)

    Kline, S.W.; Dickinson, D.B.

    1988-01-01

    10CFR50.59 permits utilities to make changes to and conduct tests or experiments on operating nuclear power plants without prior US Nuclear Regulatory Commission (NCR) approval unless the proposed change, test, or experiment (i.e, the proposed activity) involves a change to the plant technical specifications or an unreviewed safety question (USQ). To provide guidance to their engineers for making the determination of whether a proposed activity involves a USQ. Bechtel has developed a safety evaluation training program. This training program incorporates the guidance in and NRC comments to the November 1987 draft Nuclear Management and Resources Council safety evaluation guidance document, NRC statements contained in inspection reports and other documents, and the experience of senior Bechtel engineers. To further develop the question and concerns that need to be addressed in a safety evaluation in a systematic manner, Bechtel is incorporating the training program guidance and other information into an IBM PC-AT-based working model of an expert system using the NEXPERT expert system development tool. The development and use of this expert system working model are being undertaken to provide consistency and completeness to the thought process used and the output provided by Bechtel engineers when performing a safety evaluation

  15. Safety basis for selected activities in single-shell tanks with flammable gas concerns. Revision 1

    International Nuclear Information System (INIS)

    Schlosser, R.L.

    1996-01-01

    This is full revision to Revision 0 of this report. The purpose of this report is to provide a summary of analyses done to support activities performed for single-shell tanks. These activities are encompassed by the flammable gas Unreviewed Safety Question (USQ). The basic controls required to perform these activities involve the identification, elimination and/or control of ignition sources and monitoring for flammable gases. Controls are implemented through the Interim Safety Basis (ISB), IOSRs, and OSDs. Since this report only provides a historical compendium of issues and activities, it is not to be used as a basis to perform USQ screenings and evaluations. Furthermore, these analyses and others in process will be used as the basis for developing the Flammable Gas Topical Report for the ISB Upgrade

  16. Unreviewed safety question evaluation of 100K East and 100K West in-basin fuel characterization program activities

    International Nuclear Information System (INIS)

    Alwardt, L.D.

    1995-01-01

    The purpose of this report is to provide the basis for answers to an Unreviewed Safety Question (USQ) safety evaluation of the 105K East (KE) and 105K West (KW) in-basin activities associated with the fuel characterization program as described in the characterization shipping plan. The significant activities that are common to both 105 KE and 105 KW basins are the movement of canisters from their main basin storage locations (or potentially from the 105 KE Tech View Pit if a dump table is available) to the south loadout pit transfer channel, hydrogen generation testing in the single element fuel container, loading the single element fuel container into the shipping cask, loading of the shipping cask onto a flat-bed trailer, return of the test fuel elements or element pieces from the 327 facility, placement of the fuel elements back into Mark 2 canisters, and placement of the canisters in the main storage basin. Decapping of canisters in the south loadout pit transfer channel and re-encapsulation of canisters are activities specific to the 105 KW basin. The scope of this safety evaluation includes only those characterization fuel shipment activities performed in the 105 KE and 105 KW fuel storage basin structures up to installation of the overpack. The packaging safety evaluation report governs the shipment of the fuel elements. The K Basins Plant Review Committee has determined that the in-basin activities associated with the fuel characterization program fuel shipments are bounded by the current safety envelop and do not constitute an unreviewed safety question. This determination is documented on Attachment 1

  17. Safety issue resolution strategy plan for inactive miscellaneous underground storage tanks

    International Nuclear Information System (INIS)

    Wang, O.S.; Powers, T.B.

    1994-09-01

    The purpose of this strategy plan is to identify, confirm, and resolve safely issues associated with inactive miscellaneous underground storage tanks (MUSTs) using a risk-based priority approach. Assumptions and processes to assess potential risks and operational concerns are documented in this report. Safety issue priorities are ranked based on a number of considerations including risk ranking and cost effectiveness. This plan specifies work scope and recommends schedules for activities related to resolving safety issues, such as collecting historical data, searching for authorization documents, performing Unreviewed Safety Question (USQ) screening and evaluation, identifying safety issues, imposing operational controls and monitoring, characterizing waste contents, mitigating and resolving safety issues, and fulfilling other remediation requirements consistent with the overall Tank Waste Remediation System strategy. Recommendations for characterization and remediation are also recommended according to the order of importance and practical programmatic consideration

  18. Lessons Learned in the Update of a Safety Limit for the High Flux Isotope Reactor

    International Nuclear Information System (INIS)

    Cook, David Howard

    2009-01-01

    A recent unreviewed safety question (USQ) regarding a portion of the High Flux Isotope Reactor (HFIR) transient decay heat removal analysis focused on applicability of a heat transfer correlation at the low flow end of reactor operations. During resolution of this issue, review of the correlations used to establish the safety limit (SL) on reactor flux-to-flow ratio revealed the need to change the magnitude of the SL at the low flow end of reactor operations and the need to update the hot spot fuel damage criteria to incorporate current knowledge involving parallel channel flow stability. Because of the original safety design strategy for the reactor, resolution of the issues for the flux-to-flow ratio involved reevaluation of all key process variable SLs and limiting control settings (LCSs) using the current version of the heat transfer analysis code for the reactor. Goals of the work involved updating and upgrading the SL analysis where necessary, while preserving the safety design strategy for the reactor. Changes made include revisions to the safety design criteria at low flows to address the USQ, update of the process- and analysis input-variable uncertainty considerations, and upgrade of the safety design criteria at high flow. The challenges faced during update/upgrade of this SL and LCS are typical of the problems found in the integration of safety into the design process for a complex facility. In particular, the problems addressed in the area of instrument uncertainties provide valuable lessons learned for establishment and configuration control of SLs for large facilities

  19. Westinghouse Hanford Company safety analysis reports and technical safety requirements upgrade program

    International Nuclear Information System (INIS)

    Busche, D.M.

    1995-09-01

    During Fiscal Year 1992, the US Department of Energy, Richland Operations Office (RL) separately transmitted the following US Department of Energy (DOE) Orders to Westinghouse Hanford Company (WHC) for compliance: DOE 5480.21, ''Unreviewed Safety Questions,'' DOE 5480.22, ''Technical Safety Requirements,'' and DOE 5480.23, ''Nuclear Safety Analysis Reports.'' WHC has proceeded with its impact assessment and implementation process for the Orders. The Orders are closely-related and contain some requirements that are either identical, similar, or logically-related. Consequently, WHC has developed a strategy calling for an integrated implementation of the three Orders. The strategy is comprised of three primary objectives, namely: Obtain DOE approval of a single list of DOE-owned and WHC-managed Nuclear Facilities, Establish and/or upgrade the ''Safety Basis'' for each Nuclear Facility, and Establish a functional Unreviewed Safety Question (USQ) process to govern the management and preservation of the Safety Basis for each Nuclear Facility. WHC has developed policy-revision and facility-specific implementation plans to accomplish near-term tasks associated with the above strategic objectives. This plan, which as originally submitted in August 1993 and approved, provided an interpretation of the new DOE Nuclear Facility definition and an initial list of WHC-managed Nuclear Facilities. For each current existing Nuclear Facility, existing Safety Basis documents are identified and the plan/status is provided for the ISB. Plans for upgrading SARs and developing TSRs will be provided after issuance of the corresponding Rules

  20. Tank 241-C-103 organic vapor and liquid characterization and supporting activities, Hanford Site, Richland, Washington

    International Nuclear Information System (INIS)

    1993-01-01

    The action proposed is to sample the vapor space and liquid waste and perform other supporting activities in Tank 241-C-103 located in the 241-C Tank Farm on the Hanford Site. Operations at Tank 241-C-103 are curtailed because of an unreviewed safety question (USQ) concerning flammability issues of the organic waste in the tank. This USQ must be resolved before normal operation and surveillance of the tank can resume. In addition to the USQ, Tank 241-C-103 is thought to be involved in several cases of exposure of individuals to noxious vapors. This safety issue requires the use of supplied air for workers in the vicinity of the tank. Because of the USQ, the US Department of Energy proposes to characterize the waste in the vapor space and the organic and aqueous layers, to determine the volume of the organic layer. This action is needed to: (1) assess potential risks to workers, the public, and the environment from continued routine tank operations and (2) provide information on the waste material in the tank to facilitate a comprehensive safety analysis of this USQ. The information would be used to determine if a flammable condition within the tank is credible. This information would be used to prevent or mitigate an accident during continued waste storage and future waste characterization. Alternatives to the proposed activities have been considered in this analysis

  1. Interim safety basis compliance matrix for Trenches 31 and 34

    International Nuclear Information System (INIS)

    Ames, R.R.

    1994-01-01

    The tables provided in this document identify the specific requirements and basis for the administrative controls established in the Westinghouse Hanford Company (WHC) Solid Waste Burial Ground (SWBG) Interim Safety Basis (ISB) for operation of the Project W-025, Mixed Waste Lined Landfill (Trenches 31 and 34). The tables document the necessary controls and implementing procedures to ensure compliance with the requirements of the ISB. These requirements provide a basis for future Unreviewed Safety Questions (USQ) screening of applicable procedure changes, proposed physical modifications, tests, experiments, and occurrences. Table 1 provides the SWBG interim Operational Safety Requirements administrative controls matrix. The specific assumptions and commitments used in the safety analysis documents applicable to disposal of mixed wastes in Trenches 31 and 34 are provided in Table 2. Table 3 is provided to document the potential engineered and administrative mitigating features identified in the Preliminary Hazard Analysis (PHA) for disposal of mixed waste

  2. On safety goals and related questions

    International Nuclear Information System (INIS)

    Kaplan, S.

    1985-01-01

    The question of what safety goals should be established for nuclear power plants has been receiving a great deal of urgent attention and debate recently, both by those responsible for reactor licensing and by others interested in establishing a quantitative measure of reactor safety. The same question, phrased alternately in the forms: ''What is acceptable risk?'' and ''How safe is safe enough?,'' has been debated extensively for quite a long time. The purpose of the present paper, therefore, is to show that the above questions, taken at face value, exist within an unworkable context, which the authors shall call the Old Regulatory Context (ORC), and that within this context lead to several absurdities. They shall argue that this context needs to be replaced by another context, which they call the Decision Theory Context (DTC), and which the authors discuss here

  3. Ferrocyanide Safety Project Task 3 Ferrocyanide Aging Studies FY 1993 annual report

    International Nuclear Information System (INIS)

    Lilga, M.A.; Lumetta, M.R.; Schiefelbein, G.F.

    1993-10-01

    The Hanford Ferrocyanide Task Team is addressing issues involving ferrocyanide precipitates in single-shell waste storage tanks (SSTs), in particular the storage of waste in a safe manner. This Task Team, composed of researchers from Westinghouse Hanford Company (WHC), Pacific Northwest Laboratory (PNL), and outside consultants, was formed in response to the need for an updated analysis of safety questions about the Hanford ferrocyanide tanks. The Ferrocyanides Safety Project at PNL is part of the Waste Tank Safety Program led by WHC. The overall purpose of the WHC program, sponsored by the US Department of Energy's Tank Farm Project Office, is to (1) maintain the ferrocyanide tanks with minimal risk of an accident, (2) select one or more strategies to assure safe storage, and (3) close out the unreviewed safety question (USQ). This annual report gives the results of the work conducted by PNL in FY 1993 on Task 3, Ferrocyanides Aging Studies, which deals with the aging behavior of simulated ferrocyanide wastes. Aging processes include the dissolution and hydrolysis of nickel ferrocyanides in high pH aqueous solutions. Investigated were the effects of pH variation; ionic strength and sodium ion concentration; the presence of anions such as phosphate, carbonate, and nitrate; temperature; and gamma radiation on solubility of ferrocyanide materials including In-Farm-lA, Rev. 4 flowsheet-prepared Na 2 NiFe(CN) 6

  4. Evaluation of Flammable Gas Monitoring and Ventilation System Alternatives for Double-Contained Receiver Tanks

    International Nuclear Information System (INIS)

    GUSTAVSON, R.D.

    1999-01-01

    This study identifies possible flammable gas monitoring and ventilation system alternatives to ensure adequate removal of flammable gases from the Double-Contained Receiver Tank (DCRT) primary tanks during temporary storage of small amounts of waste. The study evaluates and compares these alternatives to support closure of the Flammable Gas Unreviewed Safety Question (USQ TF-96-04330)

  5. Feed tank transfer requirements

    International Nuclear Information System (INIS)

    Freeman-Pollard, J.R.

    1998-01-01

    This document presents a definition of tank turnover; DOE responsibilities; TWRS DST permitting requirements; TWRS Authorization Basis (AB) requirements; TWRS AP Tank Farm operational requirements; unreviewed safety question (USQ) requirements; records and reporting requirements, and documentation which will require revision in support of transferring a DST in AP Tank Farm to a privatization contractor for use during Phase 1B

  6. Resolving the Ferrocyanide Safety Issue at the Hanford Site

    International Nuclear Information System (INIS)

    Meacham, J.E.; Cash, R.J.; Babad, H.

    1994-02-01

    Considerable data have been obtained on the chemical and physical properties of ferrocyanide waste stored in Hanford Site single-shell tanks (SSTs). Theoretical analyses and ferrocyanide waste simulant studies have led to the development of fuel, moisture, and temperature criteria that define continued safe storage. Developing the criteria provides the technical basis for closing the Ferrocyanide Unreviewed Safety Question (USQ). Using the safety criteria, the ferrocyanide tanks have been ranked into one of three safety categories: Safe, Conditionally Safe, and Unsafe. All the ferrocyanide tanks are currently ranked in either the Safe or Conditionally Safe categories. Analyses of core samples taken from three ferrocyanide tanks have shown cyanide concentrations about a factor of ten lower than predicted by the original flowsheets. Hydrolytic and radiolytic destruction (aging) of the ferrocyanide matrix has occurred during the 35 plus years the waste has been stored at the Hanford Site. Because of waste aging, it is possible that all of the ferrocyanide tanks may now contain less than the 8 wt % sodium nickel ferrocyanide specified in the fuel criterion for the Safe category. Ferrocyanide tanks that remain in the Conditionally Safe category may require monitoring and surveillance to verify that the waste remains in an unreactive state. Further characterization of the tanks by core sampling and analyses should lead to resolution of the Ferrocyanide Safety Issue by September 1997

  7. APPROVAL OF WASTE TREATMENT AND IMMOBILIZATION PLANT CONTRACTOR-INITIATED AUTHORIZATION BASIS AMENDMENT REQUESTS (ABAR)

    International Nuclear Information System (INIS)

    JONES GL

    2008-01-01

    The objective is to describe the process used by the Office of River Protection (ORP) for evaluating and implementing Contractor-initiated changes to the Waste Treatment and Immobilization Plant (WTP) Authorization Basis (AB). The WTP Project's history has provided a unique challenge for establishing and maintaining an ORP-approved AB during design and construction. Until operations begin, the project cannot implement the classic Unreviewed Safety Question (USQ) process to determine when ORP approval of Contractor-initiated changes is required. A 'quasiUSQ' process has been implemented that defines when AB changes could occur. The three types of AB changes are (1) Limited Scope Changes, (2) Authorization Basis Deviations, and (3) Authorization Basis Amendment Request (ABAR). DOE RL/REG 97-13, 'Office of River Protection Position on Contractor-Initiated Changes to the Authorization Basis', describes the process the WTP Contractor must follow to make changes to the AB, with and without ORP approval. The process uses a 'safety evaluation' process that is similar to the USQ process but at a more qualitative level. The maturation of the WTP Contractor's facility design and activities, and other changing conditions, resulted in a process that allows the Contractor to make changes to the AB without ORP approval; however, those changes that may significantly affect nuclear safety do require ORP approval. This process balances the WTP regulatory principle of efficiency with assurance that adequate safety will not be compromised. The process has reduced the number of ABARs requiring ORP approval and reduced the potential for delays in design and procurement activities

  8. Workplace Safety: you've answered the right questions!

    CERN Multimedia

    The Safety Unit (BE Department)

    2011-01-01

    The World Day for Safety and Health at Work was a great success. A big thank you to everyone who took part and took the time to ask themselves the "right questions".   A large number of questionnaires were completed and we were happy to note that many among you had taken the opportunity to give serious thought to your own health and safety on a daily basis. In a few days' time, information on the hazards most frequently identified over the course of that day – and the methods of coping with them – will be posted on the BE Safety Unit's website. If you have any questions, please do not hesitate to contact us. The 15 winners of the tombola are: 1st prize (a FNAC gift voucher) Jean-Benoit Fouillat 2nd, 3rd, 4th and 5th prizes (a bottle of champagne): Maud Scheubel Pierre Juteau Sebastien Ceuterickx Joao Simoes From 6th to 15th prize (a box of chocolates): Antonio Mongelluzzo Francesco Castronuovo Christophe Boucly Marta Csatari Jacky Tonoli Remy Noulib...

  9. Workplace safety: Let’s ask the right questions

    CERN Multimedia

    CERN Bulletin

    2011-01-01

    Since 2003, the International Labour Organization and the World Health Organization have been organising an annual event on 28 April called “World Day for Safety and Health at Work.” This year, CERN is taking part for the first time with campaigns organised by the Safety Unit of the BE Department and by the HSE Unit.   The HSE Unit and the Safety Unit of the BE Department invite you to find out about everyday health and safety questions by visiting the stands they will be setting up at the entrances to the different restaurants at lunchtime on Thursday, 28 April. "This will be a chance to think about safety not just in the workplace but also at home and in the context of leisure activities,” explains Charles-Edouard Sala, who came up with the idea for CERN's participation in the event. “Safety is, first and foremost, a matter of personal awareness of and sensitivity to risks. That is why we in the Safety Unit had the idea for a campaign with the mo...

  10. Ferrocyanide safety project ferrocyanide aging studies. Final report

    International Nuclear Information System (INIS)

    Lilga, M.A.; Hallen, R.T.; Alderson, E.V.

    1996-06-01

    This final report gives the results of the work conducted by Pacific Northwest National Laboratory (PNNL) from FY 1992 to FY 1996 on the Ferrocyanide Aging Studies, part of the Ferrocyanide Safety Project. The Ferrocyanide Safety Project was initiated as a result of concern raised about the safe storage of ferrocyanide waste intermixed with oxidants, such as nitrate and nitrite salts, in Hanford Site single-shell tanks (SSTs). In the laboratory, such mixtures can be made to undergo uncontrolled or explosive reactions by heating dry reagents to over 200 degrees C. In 1987, an Environmental Impact Statement (EIS), published by the U.S. Department of Energy (DOE), Final Environmental Impact Statement, Disposal of Hanford Defense High-Level Transuranic and Tank Waste, Hanford Site, Richland, Washington, included an environmental impact analysis of potential explosions involving ferrocyanide-nitrate mixtures. The EIS postulated that an explosion could occur during mechanical retrieval of saltcake or sludge from a ferrocyanide waste tank, and concluded that this worst-case accident could create enough energy to release radioactive material to the atmosphere through ventilation openings, exposing persons offsite to a short-term radiation dose of approximately 200 mrem. Later, in a separate study (1990), the General Accounting Office postulated a worst-case accident of one to two orders of magnitude greater than that postulated in the DOE EIS. The uncertainties regarding the safety envelope of the Hanford Site ferrocyanide waste tanks led to the declaration of the Ferrocyanide Unreviewed Safety Question (USQ) in October 1990

  11. SAFETY EVALUATION OF OXALIC ACID WASTE RETRIEVAL IN SINGLE SHELL TANK (SST) 241-C-106

    International Nuclear Information System (INIS)

    SHULTZ, M.V.

    2003-01-01

    This report documents the safety evaluation of the process of retrieving sludge waste from single-shell tank 241-C-106 using oxalic acid. The results of the HAZOP, safety evaluation, and control allocation/decision are part of the report. This safety evaluation considers the use of oxalic acid to recover residual waste in single-shell tank (SST) 241-C-106. This is an activity not addressed in the current tank farm safety basis. This evaluation has five specific purposes: (1) Identifying the key configuration and operating assumptions needed to evaluate oxalic acid dissolution in SST 241-C-106. (2) Documenting the hazardous conditions identified during the oxalic acid dissolution hazard and operability study (HAZOP). (3) Documenting the comparison of the HAZOP results to the hazardous conditions and associated analyzed accident currently included in the safety basis, as documented in HNF-SD-WM-TI-764, Hazard Analysis Database Report. (4) Documenting the evaluation of the oxalic acid dissolution activity with respect to: (A) Accident analyses described in HNF-SD-WM-SAR-067, Tank Farms Final Safety Analysis Report (FSAR), and (B) Controls specified in HNF-SD-WM-TSR-006, Tank Farms Technical Safety Requirements (TSR). (5) Documenting the process and results of control decisions as well as the applicability of preventive and/or mitigative controls to each oxalic acid addition hazardous condition. This safety evaluation is not intended to be a request to authorize the activity. Authorization issues are addressed by the unreviewed safety question (USQ) evaluation process. This report constitutes an accident analysis

  12. Light duty utility arm startup plan

    International Nuclear Information System (INIS)

    Barnes, G.A.

    1998-01-01

    This Startup Plan encompasses activities necessary to perform startup and operation of the LDUA in Facility Group 3 tanks and complete turnover to CPO. The activities discussed in this plan will occur prior to, and following the US Department Energy, Richland Operations Office Operational Readiness Review. This startup plan does not authorize or direct any specific field activities or authorize a change of configuration. As such, this startup plan need not be Unresolved Safety Question (USQ) screened

  13. 242-A evaporator safety analysis report

    International Nuclear Information System (INIS)

    Campbell, T.A.

    1998-01-01

    In compliance with DOE Orders, an update of the 242-A SAR has been prepared, as documented in the referenced ECN. Several categories of changes were identified for inclusion in this revision of the SAR. These categories will be utilized to simplify the discussion of the changes for this USQ document. However, it is important to note that no new tests or experiments were included in this revision of the SAR. Editorial changes and/or informational updates to Chapters 9 and 11 were included as part of this revision. However, no changes to Operational Safety Requirements (OSRs) contained in Chapter 11 were required. General categories of changes included in this revision are listed

  14. Organic layer sampling for SST 241-C-103 background, and Data Quality Objectives, and analytical plan

    International Nuclear Information System (INIS)

    Wood, T.W.; Willingham, C.E.; Campbell, J.A.

    1993-08-01

    A layer of organic material floating on the surface of the high level radioactive waste in single-shell tank 241-C-103 has been declared an Unreviewed Safety Question (USQ). This designation is motivated by concern that a ''pool fire'' in this layer could release radioactive material from the tank. This layer is believed to consist largely of Tri-Butyl Phosphate (TBP) and Normal Paraffin Hydrocarbon (NPH), but its composition is not known definitively. Resolution of this USQ hinges on a more complete and detailed understanding of the flammability potential of this layer and vapors that could evolve from it, and to a lesser extent on the propagation and energetics of such a pool ire if initiated, and the source-term associated with a release event following a pool fire. This increased understanding of the risk posed by this layer in turn requires better information on its composition. This report documents a Data Quality Objectives (DQO) study conducted to define this information in detail

  15. Feed tank transfer requirements

    Energy Technology Data Exchange (ETDEWEB)

    Freeman-Pollard, J.R.

    1998-09-16

    This document presents a definition of tank turnover. Also, DOE and PC responsibilities; TWRS DST permitting requirements; TWRS Authorization Basis (AB) requirements; TWRS AP Tank Farm operational requirements; unreviewed safety question (USQ) requirements are presented for two cases (i.e., tank modifications occurring before tank turnover and tank modification occurring after tank turnover). Finally, records and reporting requirements, and documentation which will require revision in support of transferring a DST in AP Tank Farm to a privatization contractor are presented.

  16. Feed tank transfer requirements

    International Nuclear Information System (INIS)

    Freeman-Pollard, J.R.

    1998-01-01

    This document presents a definition of tank turnover. Also, DOE and PC responsibilities; TWRS DST permitting requirements; TWRS Authorization Basis (AB) requirements; TWRS AP Tank Farm operational requirements; unreviewed safety question (USQ) requirements are presented for two cases (i.e., tank modifications occurring before tank turnover and tank modification occurring after tank turnover). Finally, records and reporting requirements, and documentation which will require revision in support of transferring a DST in AP Tank Farm to a privatization contractor are presented

  17. Can Workers Answer Their Questions about Occupational Safety and Health: Challenges and Solutions

    NARCIS (Netherlands)

    Rhebergen, Martijn; van Dijk, Frank; Hulshof, Carel

    2012-01-01

    Many workers have questions about occupational safety and health (OSH). Answers to these questions empower them to further improve their knowledge about OSH, make good decisions about OSH matters and improve OSH practice when necessary. Nevertheless, many workers fail to find the answers to their

  18. Increased Efficiencies in the INEEL SAR/TSR/USQ Process

    International Nuclear Information System (INIS)

    Cole, N.E.

    2002-01-01

    The Idaho National Engineering and Environmental Laboratory (INEEL) has implemented a number of efficiencies to reduce the time and cost of preparing safety basis documents. The INEEL is continuing to look at other aspects of the safety basis process to identify other efficiencies that can be implemented and remain in compliance with Title 10 Code of Federal Regulations (CFR) Part 830. A six-sigma approach is used to identify areas to improve efficiencies and develop the action plan for implementation of the new process, as applicable. Three improvement processes have been implemented: The first was the development of standardized Documented Safety Analysis (DSA) and technical safety requirement (TSR) documents that all nuclear facilities use, by adding facility-specific details. The second is a material procurement process, which is based on safety systems specified in the individual safety basis documents. The third is a restructuring of the entire safety basis preparation and approval process. Significant savings in time to prepare safety basis document, cost of materials, and total cost of the documents are currently being realized

  19. Control Decisions for Flammable Gas Hazards in Double Contained Receiver Tanks (DCRTs)

    Energy Technology Data Exchange (ETDEWEB)

    KRIPPS, L.J.

    2000-06-28

    This report describes the control decisions for flammable gas hazards in double-contained receiver tanks (DCRTs) made at control decision meetings on November 16, 17, and 18, 1999, on April 19,2000, and on May 10,2000, and their basis. These control decisions, and the analyses that support them, will be documented in an amendment to the Final Safety Analysis Report (FSAR) (CHG 2000a) and Technical Safety Requirements (TSR) (CHG 2000b) to close the Flammable Gas Unreviewed Safety Question (USQ) (Bacon 1996 and Wagoner 1996) for DCRTs. Following the contractor Tier I review of the FSAR and TSR amendment, it will be submitted to the U.S. Department of Energy (DOE), Office of River Protection (ORP) for review and approval.

  20. Advanced Test Reactor (ATR) Facility 10CFR830 Safety Basis Related to Facility Experiments

    International Nuclear Information System (INIS)

    Tomberlin, T.A.

    2002-01-01

    The Idaho National Engineering and Environmental Laboratory (INEEL) Advanced Test Reactor (ATR), a DOE Category A reactor, was designed to provide an irradiation test environment for conducting a variety of experiments. The ATR Safety Analysis Report, determined by DOE to meet the requirements of 10 CFR 830, Subpart B, provides versatility in types of experiments that may be conducted. This paper addresses two general types of experiments in the ATR facility and how safety analyses for experiments are related to the ATR safety basis. One type of experiment is more routine and generally represents greater risks; therefore this type of experiment is addressed with more detail in the safety basis. This allows individual safety analyses for these experiments to be more routine and repetitive. The second type of experiment is less defined and is permitted under more general controls. Therefore, individual safety analyses for the second type of experiment tend to be more unique from experiment to experiment. Experiments are also discussed relative to ''major modifications'' and DOE-STD-1027-92. Application of the USQ process to ATR experiments is also discussed

  1. A meta-analysis of personality and workplace safety: addressing unanswered questions.

    Science.gov (United States)

    Beus, Jeremy M; Dhanani, Lindsay Y; McCord, Mallory A

    2015-03-01

    [Correction Notice: An Erratum for this article was reported in Vol 100(2) of Journal of Applied Psychology (see record 2015-08139-001). Table 3 contained formatting errors. Minus signs used to indicate negative statistical estimates within the table were inadvertently changed to m-dashes. All versions of this article have been corrected.] The purpose of this meta-analysis was to address unanswered questions regarding the associations between personality and workplace safety by (a) clarifying the magnitude and meaning of these associations with both broad and facet-level personality traits, (b) delineating how personality is associated with workplace safety, and (c) testing the relative importance of personality in comparison to perceptions of the social context of safety (i.e., safety climate) in predicting safety-related behavior. Our results revealed that whereas agreeableness and conscientiousness were negatively associated with unsafe behaviors, extraversion and neuroticism were positively associated with them. Of these traits, agreeableness accounted for the largest proportion of explained variance in safety-related behavior and openness to experience was unrelated. At the facet level, sensation seeking, altruism, anger, and impulsiveness were all meaningfully associated with safety-related behavior, though sensation seeking was the only facet that demonstrated a stronger relationship than its parent trait (i.e., extraversion). In addition, meta-analytic path modeling supported the theoretical expectation that personality's associations with accidents are mediated by safety-related behavior. Finally, although safety climate perceptions accounted for the majority of explained variance in safety-related behavior, personality traits (i.e., agreeableness, conscientiousness, neuroticism) still accounted for a unique and substantive proportion of the explained variance. Taken together, these results substantiate the value of considering personality traits as key

  2. Frequently Asked Questions in Fire Probabilistic Safety Assessment

    International Nuclear Information System (INIS)

    Kang, Dae Il; Kim, Kil Yoo; Park, Gee Yong

    2010-05-01

    The FAQs(Frequently Asked Questions) in the Fire Probabilistic Safety Assessment(FPSA) are the issues occurred during performing the engineering evaluation based on NFPA-805. In this report, the background and resolutions are reviewed and described for 17 FAQs related to FPSA among 57 FAQs. The current FAQs related to FPSA are the issues concerning to NUREG/CR-6850, and are almost resolved but for the some FAQ, the current resolutions would be changed depending on the results of the future or on-going research. Among FAQs related to FPSA, best estimate approaches are suggested concerning to the conservative method of NUREG/CR-6850. If these best estimate solutions are used in the FPSA of nuclear power plants, realistic evaluation results of fire risk would be obtained

  3. Can workers answer their questions about occupational safety and health: challenges and solutions.

    Science.gov (United States)

    Rhebergen, Martijn; Van Dijk, Frank; Hulshof, Carel

    2012-01-01

    Many workers have questions about occupational safety and health (OSH). Answers to these questions empower them to further improve their knowledge about OSH, make good decisions about OSH matters and improve OSH practice when necessary. Nevertheless, many workers fail to find the answers to their questions. This paper explores the challenges workers may face when seeking answers to their OSH questions. Findings suggest that many workers may lack the skills, experience or motivation to formulate an answerable question, seek and find information, appraise information, compose correct answers and apply information in OSH practice. Simultaneously, OSH knowledge infrastructures often insufficiently support workers in answering their OSH questions. This paper discusses several potentially attractive strategies for developing and improving OSH knowledge infrastructures: 1) providing courses that teach workers to ask answerable questions and to train them to find, appraise and apply information, 2) developing information and communication technology tools or facilities that support workers as they complete one or more stages in the process from question to answer and 3) tailoring information and implementation strategies to the workers' needs and context to ensure that the information can be applied to OSH practice more easily.

  4. Flammable gas project topical report

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, G.D.

    1997-01-29

    The flammable gas safety issue was recognized in 1990 with the declaration of an unreviewed safety question (USQ) by the U. S. Department of Energy as a result of the behavior of the Hanford Site high-level waste tank 241-SY-101. This tank exhibited episodic releases of flammable gas that on a couple of occasions exceeded the lower flammability limit of hydrogen in air. Over the past six years there has been a considerable amount of knowledge gained about the chemical and physical processes that govern the behavior of tank 241-SY-1 01 and other tanks associated with the flammable gas safety issue. This report was prepared to provide an overview of that knowledge and to provide a description of the key information still needed to resolve the issue. Items covered by this report include summaries of the understanding of gas generation, retention and release mechanisms, the composition and flammability behavior of the gas mixture, the amounts of stored gas, and estimated gas release fractions for spontaneous releases. `Me report also discusses methods being developed for evaluating the 177 tanks at the Hanford Site and the problems associated with these methods. Means for measuring the gases emitted from the waste are described along with laboratory experiments designed to gain more information regarding rates of generation, species of gases emitted and modes of gas storage and release. Finally, the process for closing the USQ is outlined as are the information requirements to understand and resolve the flammable gas issue.

  5. Loaded Questions: Internet Commenters' Opinions on Physician-Patient Firearm Safety Conversations.

    Science.gov (United States)

    Knoepke, Christopher E; Allen, Amanda; Ranney, Megan L; Wintemute, Garen J; Matlock, Daniel D; Betz, Marian E

    2017-08-01

    Medical and public health societies advocate that healthcare providers (HCPs) counsel at-risk patients to reduce firearm injury risk. Anonymous online media comments often contain extreme viewpoints and may therefore help in understanding challenges of firearm safety counseling. To help inform injury prevention efforts, we sought to examine commenters' stated opinions regarding firearm safety counseling HCPs. Qualitative descriptive analysis of online comments posted following news items (in May-June, 2016) about a peer-reviewed publication addressing when and how HCPs should counsel patients regarding firearms. Among 871 comments posted by 522 individuals, most (57%) were generally negative toward firearm discussions, 17% were positive, and 26% were neutral/unclear. Two major categories and multiple themes emerged. "Areas of agreement" included that discussions may be valuable (1) when addressing risk of harm to self or others, (2) in pediatric injury prevention, and (3) as general safety education (without direct questioning), and that (4) HCPs lack gun safety and cultural knowledge. "Areas of tension" included whether (1) firearms are a public health issue, (2) counseling is effective prevention practice, (3) suicide could/should be prevented, and (4) firearm safety counseling is within HCPs' purview. Among this set of commenters with likely extreme viewpoints, opinions were generally negative toward firearm safety conversations, but with some support in specific situations. Providing education, counseling, or materials without asking about firearm ownership was encouraged. Engaging firearm advocates when developing materials may enhance the acceptability of prevention activities.

  6. Saccharomyces boulardii probiotic-associated fungemia: questioning the safety of this preventive probiotic's use.

    Science.gov (United States)

    Martin, Isabella W; Tonner, Rita; Trivedi, Julie; Miller, Heather; Lee, Richard; Liang, Xinglun; Rotello, Leo; Isenbergh, Elena; Anderson, Jennifer; Perl, Trish; Zhang, Sean X

    2017-03-01

    We report a case of fungemia in an immunocompetent patient after administration of probiotic containing Saccharomyces boulardii. We demonstrated the strain relatedness of the yeast from the probiotic capsule and the yeast causing fungal infection using genomic and proteomic typing methods. Our study questions the safety of this preventative biotherapy. Copyright © 2016 Elsevier Inc. All rights reserved.

  7. An online network tool for quality information to answer questions about occupational safety and health: usability and applicability

    NARCIS (Netherlands)

    Rhebergen, Martijn D. F.; Hulshof, Carel T. J.; Lenderink, Annet F.; van Dijk, Frank J. H.

    2010-01-01

    Common information facilities do not always provide the quality information needed to answer questions on health or health-related issues, such as Occupational Safety and Health (OSH) matters. Barriers may be the accessibility, quantity and readability of information. Online Question & Answer (Q&A)

  8. Convention on nuclear safety. Questions posted to Switzerland in 2008

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    nuclear safety for each NPP based on the analysis of events, inspection results and operator licensing reviews. The assurance of low radiation doses to both NPP workers and the general public is an additional goal that is directly associated with the safe operation of NPPs. In case of an accident in a nuclear installation, contingency plans are in place and are continually updated. Emergency drills are conducted at regular intervals. The international alerting system is also in a mature stage. This report on 2008 presents the 91 questions asked by the reviewers of the Swiss report and the answers provided by the Swiss delegation represented by the Swiss Federal Nuclear Safety Inspectorate (ENSI)

  9. Convention on nuclear safety. Questions posted to Switzerland in 2008

    International Nuclear Information System (INIS)

    2008-01-01

    for each NPP based on the analysis of events, inspection results and operator licensing reviews. The assurance of low radiation doses to both NPP workers and the general public is an additional goal that is directly associated with the safe operation of NPPs. In case of an accident in a nuclear installation, contingency plans are in place and are continually updated. Emergency drills are conducted at regular intervals. The international alerting system is also in a mature stage. This report on 2008 presents the 91 questions asked by the reviewers of the Swiss report and the answers provided by the Swiss delegation represented by the Swiss Federal Nuclear Safety Inspectorate (ENSI)

  10. FY 1993 Ferrocyanide Tank Safety Project: Effects of Aging on Ferrocyanide Wastes test plan for the remainder of FY 1993

    International Nuclear Information System (INIS)

    Lilga, M.A.; Schiefelbein, G.F.

    1993-06-01

    Researchers in the Hanford Ferrocyanide Task Team are studying safety issues associated with ferrocyanide precipitates in single shell waste storage tanks (SST). Ferrocyanide is a stable complex of ferrous, ion and cyanide ion that is considered nontoxic because it does not dissociate readily in aqueous solutions. However, in the laboratory at temperatures in excess of 180 degrees C and in the presence of oxidizers such as nitrates and nitrites, dry ferrocyanide and ferrocyanide waste stimulants can be made to react exothermically. The Ferrocyanide Safety Project at the Pacific Northwest Laboratory (PNL) is part of the Waste Tank Safety Program at Westinghouse Hanford Company (WHC). The purpose of the WHC program is to (1) maintain the ferrocyanide tanks with minimal risk of an accident, (2) select one or more strategies to assure safe storage, and (3) close out the unreviewed safety question (USQ). Tank ferrocyanide wastes were exposed to highly alkaline wastes from subsequent processing operations. Chemical reactions with caustic may have changed the ferrocyanide materials during 40 years of storage in the SSTs. Research in the open-quotes Effects of Aging on Ferrocyanide Wastesclose quotes task is targeted at studying aging of ferrocyanide tank simulants and other ferrocyanide materials to obtain a better understanding of how tank materials may have changed over the years. The research objective in this project is to determine the solubility and hydrolysis characteristics of simulated ferrocyanide tank wastes in alkaline media. The behavior of ferrocyanide simulant wastes is being determined by performing chemical reactions under conditions that might mimic the potential ranges in SST environments. Experiments are conducted at high pH, at high ionic strength, and in the presence of gamma radiation. Verification of simulant study findings by comparison with results with actual waste will also be required

  11. Hazard Analysis Database Report

    CERN Document Server

    Grams, W H

    2000-01-01

    The Hazard Analysis Database was developed in conjunction with the hazard analysis activities conducted in accordance with DOE-STD-3009-94, Preparation Guide for U S . Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports, for HNF-SD-WM-SAR-067, Tank Farms Final Safety Analysis Report (FSAR). The FSAR is part of the approved Authorization Basis (AB) for the River Protection Project (RPP). This document describes, identifies, and defines the contents and structure of the Tank Farms FSAR Hazard Analysis Database and documents the configuration control changes made to the database. The Hazard Analysis Database contains the collection of information generated during the initial hazard evaluations and the subsequent hazard and accident analysis activities. The Hazard Analysis Database supports the preparation of Chapters 3 ,4 , and 5 of the Tank Farms FSAR and the Unreviewed Safety Question (USQ) process and consists of two major, interrelated data sets: (1) Hazard Analysis Database: Data from t...

  12. Photovoltaic Devices Prepared through a Trihydroxy Substitution Strategy on an Unsymmetrical Squaraine Dye.

    Science.gov (United States)

    Wu, Jianglin; Si, Changfeng; Chen, Yao; Yang, Lin; Hu, Bin; Chen, Guo; Lu, Zhiyun; Huang, Yan

    2018-03-02

    A series of unsymmetrical arene-1,3-squaraine (USQ) derivatives with two, three, or four hydroxy (-OH) substituents, namely, USQ-2-OH, USQ-3-OH, or USQ-4-OH, respectively, were designed and synthesized, and the effect of the number of hydroxy groups on the optoelectronic properties of USQs were investigated. Despite the three compounds having similar UV/Vis absorption and HOMO energy levels, solution-processed bulk-heterojunction (BHJ) small-molecule organic solar cells with USQ-3-OH as electron-donor materials exhibit the highest power conversion efficiency of 6.07 %, which could be mainly attributed to the higher hole mobility and smaller phase separation. It is also noteworthy that the short-circuit current (J sc ) of the USQ-3-OH-based device is as high as 14.95 mA cm -2 , which is the highest J sc values reported for squaraine-based BHJ solar cells to date. The results also indicate that more -OH substituents on squaraine dyes do not necessarily lead to better photovoltaic performance. © 2018 Wiley-VCH Verlag GmbH & Co. KGaA, Weinheim.

  13. A program for occupational radiological protection in a nuclear installation linked to a NORM/TENORM phosphate

    International Nuclear Information System (INIS)

    Pereira, Wagner de S.; Py Junior, Delcy de A.; Kelecom, Alphonse; Mortagua, Valter

    2009-01-01

    of 20 mSv y -1 , 2,000 hours of work per year, and a breathing volume of 2,400 m 3 y -1 . The radionuclide in question was U-nat (composed of 48.9% of 238 U, 48.9% of 234 U and 2.2% of 235 U), type F. The maximum estimated dose in operation for the OEI was 3.5 mSv y -1 , and for the individual the public 0.15 mSv y -1 . Admission, periodic, special and demission examinations are indicated as medical supervision. Aiming optimization, a training program will be implemented at USQ. The OEI of the USQ will be trained before starting its activities with radioactive materials, annually as a routine, and whenever there are changes to the ORPP, to the operation of equipment or procedures in general, as work is in progress. People contracted for temporary services will receive an introductory training to radioprotection. Their services will be continuously monitored by technicians of Radiological Protection. The administrative support workers will receive only basic instructions. (author)

  14. In question: the scientific value of preclinical safety pharmacology and toxicology studies with cell-based therapies

    Directory of Open Access Journals (Sweden)

    Christiane Broichhausen

    2014-01-01

    Full Text Available A new cell-based medicinal product containing human regulatory macrophages, known as Mreg_UKR, has been developed and conforms to expectations of a therapeutic drug. Here, Mreg_UKR was subjected to pharmacokinetic, safety pharmacology, and toxicological testing, which identified no adverse reactions. These results would normally be interpreted as evidence of the probable clinical safety of Mreg_UKR; however, we contend that, owing to their uncertain biological relevance, our data do not fully support this conclusion. This leads us to question whether there is adequate scientific justification for preclinical safety testing of similar novel cell-based medicinal products using animal models. In earlier work, two patients were treated with regulatory macrophages prior to kidney transplantation. In our opinion, the absence of acute or chronic adverse effects in these cases is the most convincing available evidence of the likely safety of Mreg_UKR in future recipients. On this basis, we consider that safety information from previous clinical investigations of related cell products should carry greater weight than preclinical data when evaluating the safety profile of novel cell-based medicinal products. By extension, we argue that omitting extensive preclinical safety studies before conducting small-scale exploratory clinical investigations of novel cell-based medicinal products data may be justifiable in some instances.

  15. An Online Network Tool for Quality Information to Answer Questions about Occupational Safety and Health: Usability and Applicability

    NARCIS (Netherlands)

    Rhebergen, M.D.F.; Hulshof, C.T.J.; Lenderink, A.F.; van Dijk, F.J.H.

    2010-01-01

    ABSTRACT: BACKGROUND: Common information facilities do not always provide the quality information needed to answer questions on health or health-related issues, such as Occupational Safety and Health (OSH) matters. Barriers may be the accessibility, quantity and readability of information. Online

  16. INERT Atmosphere confinement operability test procedure

    International Nuclear Information System (INIS)

    RISENMAY, H.R.

    1999-01-01

    This Operability Test Procedure (OTP) provides instructions for testing operability of the Inert Atmosphere Confinement (IAC). The Inert Atmosphere Confinement was designed and built for opening cans of metal items that might have hydrided surfaces. Unreviewed Safety Question (USQ) PFP-97-005 addresses the discovery of suspected plutonium hydride forming on plutonium metal currently stored in the Plutonium Finishing Plant vaults. Plutonium hydride reacts quickly with air, liberating energy. The Inert Atmosphere Confinement was designed to prevent this sudden liberation of energy by opening the material in an inert argon atmosphere instead of the normal glovebox atmosphere. The IAC is located in glovebox HC-21A, room 230B of the 234-5Z Building at the Plutonium Finishing Plant (PFP) in the 200-West Area of the Hanford Site

  17. Can online networks provide quality answers to questions about occupational safety and health?

    Science.gov (United States)

    Rhebergen, Martijn D F; Lenderink, Annet F; van Dijk, Frank J H; Hulshof, Carel T J

    2012-05-01

    To assess whether experts can provide high-quality answers to occupational safety and health (OSH) questions in online Question & Answer (Q&A) networks. The authors evaluated the quality of answers provided by qualified experts in two Dutch online networks: ArboAntwoord and the Helpdesk of the Netherlands Center for Occupational Diseases. A random sample of 594 answers was independently evaluated by two raters using nine answer quality criteria. An additional criterion, the agreement of answers with the best available evidence, was explored by peer review of a sample of 42 answers. Reviewers performed an evidence search in Medline. The median answer quality score of ArboAntwoord (N=295) and the Netherlands Center for Occupational Diseases Helpdesk (N=299) was 8 of 9 (IQR 2). The inter-rater reliability of the first nine quality criteria was high (κ 0.82-0.90, p<0.05). A question answered by two or more experts had a greater probability of a high-quality score than questions answered by one expert (OR 4.9, 95% CI 2.7 to 9.0). Answers most often scored insufficient on the use of evidence to underpin the answer (36% and 38% for the networks, respectively) and on conciseness (35% and 31%, respectively). Peer review demonstrated that 43%-72% of the answers in both online networks were in complete agreement with the best available evidence. OSH experts are able to provide quality answers in online OSH Q&A networks. Our answer quality appraisal instrument was feasible and provided information on how to improve answer quality.

  18. Answers to questions on National report of the Slovak Republic compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. April 2009

    International Nuclear Information System (INIS)

    2009-01-01

    In this publication detail answers to questions on National report of the Slovak Republic compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management of April 2009 are published

  19. Answers to questions on National report of the Slovak Republic compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. April 2011

    International Nuclear Information System (INIS)

    2011-04-01

    In this publication detail answers to questions on National report of the Slovak Republic compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management of April 2011 are published.

  20. Answers to questions on National report of the Slovak Republic compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. April 2012

    International Nuclear Information System (INIS)

    2012-04-01

    In this publication detail answers to questions on National report of the Slovak Republic compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management of April 2011 are published.

  1. Answers to questions on National report of the Slovak Republic compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. April 2011

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-04-15

    In this publication detail answers to questions on National report of the Slovak Republic compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management of April 2011 are published.

  2. Answers to questions on National report of the Slovak Republic compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. April 2014

    International Nuclear Information System (INIS)

    2014-04-01

    In this publication detail answers to questions on National report of the Slovak Republic compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management of April 2014 are published.

  3. 324 Building fire hazards analysis implementation plan

    International Nuclear Information System (INIS)

    BARILO, N.F.

    1999-01-01

    In March 1998, the 324 Building Fire Hazards Analysis (FHA) (Reference 1) was approved by the U S. Department of Energy, Richland Operations Office (DOE-RL) for implementation by B and W Hanford Company (BWHC). The purpose of the FHA was to identify gaps in compliance with DOE Order 5480.7A (Reference 2) and Richland Operations Office Implementation Directive (RLID) 5480.7 (Reference 3), especially in regard to loss limitation. The FHA identified compliance gaps in six areas and provided 20 recommendations to bring the 324 Building into compliance with DOE Order 5480 7A. Additionally, one observation was provided. A status is provided for each recommendation in this document. The actions for recommendations associated with the safety related part of the 324 Building and operation of the cells and support areas were evaluated using the Unreviewed Safety Question (USQ) process BWHC will use this Implementation Plan to bring the 324 Building and its operation into compliance with DOE Order 5480 7A and RLID 5480.7

  4. CAT questions and answers

    International Nuclear Information System (INIS)

    1993-02-01

    This document, prepared in February 1993, addresses the most common questions asked by APS Collaborative Access Teams (CATs). The answers represent the best judgment on the part of the APS at this time. In some cases, details are provided in separate documents to be supplied by the APS. Some of the answers are brief because details are not yet available. The questions are separated into five categories representing different aspects of CAT interactions with the APS: (1) Memorandum of Understanding (MOU), (2) CAT Beamline Review and Construction, (3) CAT Beamline Safety, (4) CAT Beamline Operations, and (5) Miscellaneous. The APS plans to generate similar documents as needed to both address new questions and clarify answers to present questions

  5. Let's talk nuclear energy in 30 questions; Parlons nucleaire en 30 questions

    Energy Technology Data Exchange (ETDEWEB)

    Reuss, Paul

    2012-01-11

    The Fukushima catastrophe of March 11, 2011 has called into question the share of nuclear energy in France and in foreign countries. Its replacement by renewable energy sources and the safety of nuclear power plants are in the center of today's debates. But what is the reality behind the mass of contradictory information that exists on this complex topic? This book moves the question out of the media noise and supplies objective and factual information with reliable figures about the nuclear industry by answering 30 key-questions. (J.S.)

  6. Public meeting on radiation safety for industrial radiographerss: remarks, questions and answers at five NRC regional meetings

    International Nuclear Information System (INIS)

    1978-11-01

    Over the past several years thenumber of radiation overexposures experienced in the radiography industry has been higher than for any other single group of NRC licensees. To inform radiography licensees of NRC's concern fo these recurring overexposure incidents, NRC staff representatives met with licensees in a series of five regional meetings. At these meetings the staff presented prepared remarks and answered questions on NRC regulations and operations. The main purposes of the meetings were to express NRC's concern for the high incidence of overexposures, and to open a line of communication between the NRC and radiography licensees in an effort to achieve the common goal of improved radiation safety. The remarks presented by the staff and subjects discussed at these meetings included: the purpose, scope, findings and goals of the NRC inspection program; ways and means of incorporating safety into radiography operations; and case histories of overexposure incidents, with highlights of the causes and possible preventions. At each of the regional meetings the staff received a request for a copy of the prepared remarks and a consolidation of the questions and answers that were discussed. This document includes that information, and a copy is being provided to each organizaion or firm attending the regional meetings. Requests for other copies should be made in accordance with the directions printed inside the front cover of this document

  7. 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

  8. Tank 244A tank characterization plan

    International Nuclear Information System (INIS)

    Schreiber, R.D.

    1994-01-01

    The Double-Shell Tank (DST) System currently receives waste from the Single-Shell Tank (SST) System in support of SST stabilization efforts or from other on-site facilities which generate or store waste. Waste is also transferred between individual DSTs. The mixing or commingling of potentially incompatible waste types at the Hanford Site must be addressed prior to any waste transfers into the DSTs. The primary goal of the Waste Compatibility Program is to prevent the formation of an Unreviewed Safety Question (USQ) as a result of improper waste management. Tank 244A is a Double Contained Receiver Tank (DCRT) which serves as any overflow tank for the East Area Farms. Waste material is able to flow freely between the underground storage tanks and tank 244A. Therefore, it is necessary to test the waste in tank 244A for compatibility purposes. Two issues related to the overall problem of waste compatibility must be evaluated: Assurance of continued operability during waste transfer and waste concentration and Assurance that safety problems are not created as a result of commingling wastes under interim storage. The results of the grab sampling activity prescribed by this Tank Characterization Plan shall help determine the potential for four kinds of safety problems: criticality, flammable gas accumulation, energetics, and corrosion and leakage

  9. Control Decisions for Flammable Gas Hazards in Waste Transfer Systems

    International Nuclear Information System (INIS)

    KRIPPS, L.J.

    2000-01-01

    This report describes the control decisions for flammable gas hazards in waste transfer systems (i.e., waste transfer piping and waste transfer-associated structures) made at control decision meetings on November 30, 1999a and April 19, 2000, and their basis. These control decisions, and the analyses that support them, will be documented in an amendment to the Final Safety Analysis Report (FSAR) (CHG 2000a) and Technical Safety Requirements (TSR) (CHG 2000b) to close the Flammable Gas Unreviewed Safety Question (USQ) (Bacon 1996 and Wagoner 1996). Following the Contractor Tier I review of the FSAR and TSR amendment, it will be submitted to the US. Department of Energy (DOE), Office of River Protection (ORP) for review and approval. The control decision meeting on November 30, 1999 to address flammable gas hazards in waste transfer systems followed the control decision process and the criteria for control decisions described in Section 3.3.1.5 of the FSAR. The control decision meeting agenda, attendance list, and introductory and background presentations are included in Attachments 1 through 4. The control decision discussions on existing and other possible controls for flammable gas hazards in waste transfer systems and the basis for selecting or not selecting specific controls are summarized in this report

  10. An online network tool for quality information to answer questions about occupational safety and health: usability and applicability

    Directory of Open Access Journals (Sweden)

    van Dijk Frank JH

    2010-10-01

    Full Text Available Abstract Background Common information facilities do not always provide the quality information needed to answer questions on health or health-related issues, such as Occupational Safety and Health (OSH matters. Barriers may be the accessibility, quantity and readability of information. Online Question & Answer (Q&A network tools, which link questioners directly to experts can overcome some of these barriers. When designing and testing online tools, assessing the usability and applicability is essential. Therefore, the purpose of this study is to assess the usability and applicability of a new online Q&A network tool for answers on OSH questions. Methods We applied a cross-sectional usability test design. Eight occupational health experts and twelve potential questioners from the working population (workers were purposively selected to include a variety of computer- and internet-experiences. During the test, participants were first observed while executing eight tasks that entailed important features of the tool. In addition, they were interviewed. Through task observations and interviews we assessed applicability, usability (effectiveness, efficiency and satisfaction and facilitators and barriers in use. Results Most features were usable, though several could be improved. Most tasks were executed effectively. Some tasks, for example searching stored questions in categories, were not executed efficiently and participants were less satisfied with the corresponding features. Participants' recommendations led to improvements. The tool was found mostly applicable for additional information, to observe new OSH trends and to improve contact between OSH experts and workers. Hosting and support by a trustworthy professional organization, effective implementation campaigns, timely answering and anonymity were seen as important use requirements. Conclusions This network tool is a promising new strategy for offering company workers high quality information

  11. Repetitive Questioning II

    Directory of Open Access Journals (Sweden)

    R. C. Hamdy MD

    2018-02-01

    Full Text Available Repetitive questioning is a major problem for caregivers, particularly taxing if they are unable to recognize and understand the reasons why their loved one keeps asking the same question over and over again. Caregivers may be tempted to believe that the patient does not even try to remember the answer given or is just getting obnoxious. This is incorrect. Repetitive questioning is due to the underlying disease: The patient’s short term memory is impaired and he is unable to register, encode, retain and retrieve the answer. If he is concerned about a particular topic, he will keep asking the same question over and over again. To the patient each time she asks the question, it is as if she asked it for the first time. Just answering repetitive questioning by providing repeatedly the same answer is not sufficient. Caregivers should try to identify the underlying cause for this repetitive questioning. In an earlier case study, the patient was concerned about her and her family’s safety and kept asking whether the doors are locked. In this present case study, the patient does not know how to handle the awkward situation he finds himself in. He just does not know what to do. He is not able to adjust to the new unexpected situation. So he repeatedly wants to reassure himself that he is not intruding by asking the same question over and over again. We discuss how the patient’s son-in-law could have avoided this situation and averted the catastrophic ending.

  12. The question of caution in professional medium

    International Nuclear Information System (INIS)

    Godard, O.

    2006-01-01

    Contrived in Europe to tackle the environment protection policies and management of natural resources, the principle of caution has seen since 1990 its interest developed towards the fields of food safety and public health. The importance and the relevance of questions have lead the national institute of research and safety to constitute a working group to explore the problems and the potentialities that could be linked to the explicit introduction of this principle and this in the field of the prevention of professional risks. This work tackles several aspects of the question of caution in professional medium such history, concepts, evolution...as well as cases judged exemplary ones. (N.C.)

  13. Repetitive Questioning Exasperates Caregivers

    Directory of Open Access Journals (Sweden)

    R. C. Hamdy MD

    2018-01-01

    Full Text Available Repetitive questioning is due to an impaired episodic memory and is a frequent, often presenting, problem in patients with Alzheimer’s disease (amnestic type. It is due to the patients’ difficulties learning new information, retaining it, and recalling it, and is often aggravated by a poor attention span and easy distractibility. A number of factors may trigger and maintain repetitive questioning. Caregivers should try to identify and address these triggers. In the case discussion presented, it is due to the patient’s concerns about her and her family’s safety triggered by watching a particularly violent movie aired on TV. What went wrong in the patient/caregiver interaction and how it could have been avoided or averted are explored. Also reviewed are the impact of repetitive questioning, the challenges it raises for caregivers, and some effective intervention strategies that may be useful to diffuse the angst that caregivers experience with repetitive questioning.

  14. Nuclear power and the environment: questions and answers

    International Nuclear Information System (INIS)

    Anon.

    1976-01-01

    The purpose of this book is to present information and answers to questions about nuclear power and the environment, e.g., questions on its effects on public health, safety, and welfare. Information on the overall U.S. energy outlook, with emphasis on nuclear power generation, is provided. Although proponents of nuclear power, the authors have attempted to present factual information and to maintain objectivity. Included are answers to questions on these aspects of nuclear power: the energy situation and nuclear power; economics and reliability; alternative technologies; radioactivity; biological effects of radiation; transportation in the nuclear fuel cycle; fuel reprocessing and nuclear waste disposal; plutonium toxicity; nuclear plant security; thermal pollution; nuclear power plant siting--earthquakes; nuclear reactor safety; public risk and benefits; nuclear liability and insurance; breeder reactors; and thermonuclear fusion. (232 references)

  15. Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management. Third review meeting. Questions asked to France and answers

    International Nuclear Information System (INIS)

    2009-01-01

    The Joint Convention on the Safety of Spent Fuel Management and the Safety of Radioactive Waste Management, referred to as the 'Joint Convention', is the result of international discussions that followed the adoption of the Convention on Nuclear Safety, in 1994. France signed the Joint Convention at the General Conference of the International Atomic Energy Agency (IAEA) held on 29 September 1997, the very first day the Joint Convention was opened for signature. She approved it on 22 February 2000 and filed the corresponding instruments with the IAEA on 27 April 2000. The Joint Convention entered into force on 18 June 2001. For many years, France has been taking an active part in the pursuit of international actions to reinforce nuclear safety and considers the Joint Convention to be a key step in that direction. The fields covered by the Joint Convention have long been part of the French approach to nuclear safety. For his third report, France presented a document reflecting the viewpoints of the various stakeholders (regulatory authorities and operators). Thus, for each of the chapters in which the regulatory authority is not the only party to express its point of view, a three-stage structure was adopted: first of all a description by the regulatory authority of the regulations, followed by a presentation by the operators of the steps taken to meet the regulations and finally, an analysis by the regulatory authority of the steps taken by the operators. This third report was distributed in October 2008 to all Contracting Parties who asked 213 questions on the French report. France answered each of them in the present document

  16. Hazard evaluation for 244-AR vault facility

    International Nuclear Information System (INIS)

    BRAUN, D.J.

    1999-01-01

    This document presents the results of a hazard identification and evaluation performed on the 244-AR Vault Facility to close a USQ (USQ No. TF-98-0785, Potential Inadequacy in Authorization Basis (PIAB): To Evaluate Miscellaneous Facilities Listed in HNF-2503 And Not Addressed In The TWRS Authorization Basis) that was generated as part of an evaluation of inactive TWRS facilities

  17. Hazard Evaluation for 244-CR Vault

    Energy Technology Data Exchange (ETDEWEB)

    GRAMS, W.H.

    1999-08-19

    This document presents the results of a hazards identification and evaluation performed on the 244-CR Vault to close a USQ (USQ No.TF-98-0785, Potential Inadequacy in Authorization Basis (PIAB): To Evaluate Miscellaneous Facilities Listed In HNF-2503 And Not Addressed In The TWRS Authorization Basis) that was generated as part of an evaluation of inactive TWRS facilities.

  18. Hazard Evaluation for 244-CR Vault

    International Nuclear Information System (INIS)

    GRAMS, W.H.

    1999-01-01

    This document presents the results of a hazards identification and evaluation performed on the 244-CR Vault to close a USQ (USQ No.TF-98-0785, Potential Inadequacy in Authorization Basis (PIAB): To Evaluate Miscellaneous Facilities Listed In HNF-2503 And Not Addressed In The TWRS Authorization Basis) that was generated as part of an evaluation of inactive TWRS facilities

  19. Nuclear power: Questions and answers

    International Nuclear Information System (INIS)

    1988-01-01

    In 1988, the Uranium Institute, a London-based international association of industrial enterprises in the nuclear industry, published a report entitled The Safety of Nuclear Power Plants. Based on an assessment by an international group of senior nuclear experts from eight countries, the report provides an authoritative explanation, for non-specialists of the basic principles of reactor safety, their application, and their implications. Some questions and answers are selected from that report; they address only a few of the subjects that the report itself examines in greater detail

  20. Safety culture

    International Nuclear Information System (INIS)

    Keen, L.J.

    2003-01-01

    Safety culture has become a topic of increasing interest for industry and regulators as issues are raised on safety problems around the world. The keys to safety culture are organizational effectiveness, effective communications, organizational learning, and a culture that encourages the identification and resolution of safety issues. The necessity of a strong safety culture places an onus on all of us to continually question whether the safety measures already in place are sufficient, and are being applied. (author)

  1. Vaccine Safety

    Science.gov (United States)

    ... During Pregnancy Frequently Asked Questions about Vaccine Recalls Historical Vaccine Safety Concerns FAQs about GBS and Menactra ... CISA Resources for Healthcare Professionals Evaluation Current Studies Historical Background 2001-12 Publications Technical Reports Vaccine Safety ...

  2. Reactor safety research and safety technology. Pt. 2

    International Nuclear Information System (INIS)

    Theenhaus, R.; Wolters, J.

    1987-01-01

    The state of HTR safety research work reached permits a comprehensive and reliable answer to be given to questions which have been raised by the reactor accident at Chernobyl, regarding HTR safety. Together with the probability safety analyses, the way to a safety concept suitable for an HTR is cleared; instructions are given for design optimisation with regard to safety technique and economy. The consequences of a graphite fire, the neutron physics design and the consequenes of the lack of a safety containment are briefly described. (DG) [de

  3. Transforming classroom questioning using emerging technology.

    Science.gov (United States)

    Mahon, Paul; Lyng, Colette; Crotty, Yvonne; Farren, Margaret

    2018-04-12

    Classroom questioning is a common teaching and learning strategy in postgraduate nurse education. Technologies such as audience response systems (ARS) may offer advantage over traditional approaches to classroom questioning. However, despite being available since the 1960s, ARSs are still considered novel in many postgraduate nurse education classroom settings. This article aims to explicate the attitudes of postgraduate nursing students in an Irish academic teaching hospital towards classroom questioning (CQ) and the use of ARSs as an alternative to traditional CQ techniques. The results of this small-scale study demonstrate that ARSs have a role to play in CQ in the postgraduate setting, being regarded by students as beneficial to learning, psychological safety and classroom interaction.

  4. Flu Vaccine Safety Information

    Science.gov (United States)

    ... Influenza Types Seasonal Avian Swine Variant Pandemic Other Flu Vaccine Safety Information Questions & Answers Language: English (US) ... safety of flu vaccines monitored? Egg Allergy Are flu vaccines safe? Flu vaccines have good safety record. ...

  5. Application of fuzzy set theory for safety culture and safety management assessment of Kartini research reactor

    International Nuclear Information System (INIS)

    Syarip; Hauptmanns, U.

    2000-01-01

    The safety culture status of nuclear power plant is usually assessed through interview and/or discussions with personnel and management in plant, and an assessment of the pertinent documentation. The approach for safety culture assessment described in IAEA Safety Series, make uses of a questionnaire composed of questions which require 'Yes' or 'No' as an answer. Hence, it is basically a check-list approach which is quite common for safety assessments in industry. Such a procedure ignores the fact that the expert answering the question usually has knowledge which goes far beyond a mere binary answer. Additionally, many situations cannot readily be described in such restricted terms. Therefore, it was developed a checklist consisting of questions which are formulated such that they require more than a simple 'yes' or 'no' as an answer. This allows one to exploit the expert knowledge of the analyst appropriately by asking him to qualify the degree of compliance of each of the topics examined. The method presented has proved useful in assessing the safety culture and quality of safety management of the research reactor. The safety culture status and the quality of safety management of Kartini research reactor is rated as 'average'. The method is also flexible and allows one to add questions to existing areas or to introduce new areas covering related topics

  6. Hazard evaluation for transfer of waste from tank 241-SY-101 to tank 241-SY-102

    International Nuclear Information System (INIS)

    SHULTZ, M.V.

    1999-01-01

    Tank 241-SY-101 (SY-101) waste level growth is an emergent, high priority issue. The purpose of this document is to record the hazards evaluation process and document potential hazardous conditions that could lead to the release of radiological and toxicological material from the proposed transfer of a limited quantity (approximately 100,000 gallons) of waste from SY-101 to 241-SY-102 (SY-102). The results of the hazards evaluation will be compared to the current Tank Waste Remediation System (TWRS) Basis for Interim Operation (HNF-SD-WM-BIO-001, 1998, Revision 1) to identify any hazardous conditions where Authorization Basis (AB) controls may not be sufficient or may not exist. Comparison to LA-UR-92-3196, A Safety Assessment for Proposed Pump Mixing Operations to Mitigate Episodic Gas Releases in Tank 241-SY-101, was also made in the case of transfer pump removal activities. This document is not intended to authorize the activity or determine the adequacy of controls; it is only intended to provide information about the hazardous conditions associated with this activity. The Unreviewed Safety Question (USQ) process will be used to determine the adequacy of controls and whether the proposed activity is within the AB. This hazard evaluation does not constitute an accident analysis

  7. Characterization of Hanford tank wastes containing ferrocyanides

    International Nuclear Information System (INIS)

    Tingey, J.M.; Matheson, J.D.; McKinley, S.G.; Jones, T.E.; Pool, K.H.

    1993-02-01

    Currently, 17 storage tanks on the Hanford site that are believed to contain > 1,000 gram moles (465 lbs) of ferrocyanide compounds have been identified. Seven other tanks are classified as ferrocyanide containing waste tanks, but contain less than 1,000 gram moles of ferrocyanide compounds. These seven tanks are still included as Hanford Watch List Tanks. These tanks have been declared an unreviewed safety question (USQ) because of potential thermal reactivity hazards associated with the ferrocyanide compounds and nitrate and nitrite. Hanford tanks with waste containing > 1,000 gram moles of ferrocyanide have been sampled. Extensive chemical, radiothermical, and physical characterization have been performed on these waste samples. The reactivity of these wastes were also studied using Differential Scanning Calorimetry (DSC) and Thermogravimetric analysis. Actual tank waste samples were retrieved from tank 241-C-112 using a specially designed and equipped core-sampling truck. Only a small portion of the data obtained from this characterization effort will be reported in this paper. This report will deal primarily with the cyanide and carbon analyses, thermal analyses, and limited physical property measurements

  8. Animal Product Safety Information

    Science.gov (United States)

    ... Home Animal & Veterinary Safety & Health Product Safety Information Product Safety Information Share Tweet Linkedin Pin it More ... to report adverse experiences with veterinary drugs. Additional Product Information Questions and Answers: Evanger’s Dog and Cat ...

  9. Answers to questions on National Report of the Slovak Republic. Compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. April 2006

    International Nuclear Information System (INIS)

    2003-04-01

    Slovakia is pleased to present to the State Parties of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management the Answers to questions received on the National Report of the Slovak Republic compiled according to the terms of the Joint Convention (2005). Slovakia is ready to provide additional explanations to these Answers during the 2 nd Review Meeting. In the Annexes the 541/2004 Coll. LL. Act of 9 September 2004 on Peaceful Use of Nuclear Energy (Atomic Act) and on Alternations and Amendments to Some Acts

  10. Questions for the nuclear installations inspectorate

    International Nuclear Information System (INIS)

    Conroy, C.; Flood, M.; MacRory, R.; Patterson, W.C.

    1976-01-01

    The responsibilities of the Nuclear Installations Inspectorate are considered, and the responsibilities of other bodies for (a) reprocessing and enrichment, and (b) security. Questions for the Nuclear Installations Inspectorate are then set out under the following heads: general (on such topics as vandalism, sabotage, threats, security, reactor incidents); magnox reactors; corrosion; advanced gas-cooled reactor; steam generating heavy water reactor; fast breeder reactor; reproces-sing and waste. Most of the questions are concerned with technical problems that have been reported or might possibly arise during construction or operation, affecting the safety of the reactor or process. (U.K.)

  11. 222 questions about the energy

    International Nuclear Information System (INIS)

    Barrachina Gomez, M.; Cerrolaza Asenjo, J.A.; Garcia Alonso, J.M.; Iranzo Martin, J.E.; Lopez Perez, B.; Minguez Perres, E.; Minguez Torres, E.; Pascualena Cambra, M.T.; Poza Galiano, A. de la; Secades Ariz, I.

    1993-01-01

    The book presents with an easy language, questions about energy. The main topics are: - Energy and energy sources - Energy and society - The energy in the world - Basic concepts of Nuclear Physics - Basic concepts of radiological protection - Electric power - Nuclear Fuel cycle - Environmental impact - Radioactive wastes management - The risk in the electricity production - Standardization of Nuclear Safety - Economic aspects of electricity generation - Energy and Spanish economy

  12. Living with risk: a management question

    International Nuclear Information System (INIS)

    Ale, Ben J.M.

    2005-01-01

    Public authorities started to be really involved in risk management of hazardous materials some 30 years ago. Recent developments have led to fresh attention for this matter and many further developments are underway. The history of risk management and safety regulation is one of strongly variable interest, forgotten lessons and rude awakenings. The impetus exerted by accidents is short lived. Safety cases become documents to satisfy regulation rather than instruments to reduce risk. Deregulation, privatisation, and outsourcing pose new challenges to safety and risk management. Some of the unfortunate side effects have already become apparent. This invariably leads to the next disaster, which will have a striking resemblance to the previous one when abstracted from the immediate technological context. Lessons can be learned if we really want. The question remains: 'Do we?'

  13. Army 86 Cost Sensitivity Analysis Verification.

    Science.gov (United States)

    1980-09-01

    NIGHT VIS SI AN/TAS-6 11 P21220 (Z50154) P-A DET SYS AN/USQ-70 24 QUANTITY LINE ITEM NUMBER NOMENCLATURE 26 Q16110 RADAR SET AN/PPS- SALP 54 Q16173...4 W/IMG 48 N04982 NIGHT VIS SI AN/TAS-4 55 NOSOSO NIGHT VIS SI AN/TAS-6 13 P21220 (Z50154) P-A BET SYS AN/USQ-70 -6 Q16110 RADAR SET AN/PPS- SALP 36

  14. Introducing Laboratory Safety.

    Science.gov (United States)

    DeLorenzo, Ronald

    1985-01-01

    Presents a simple, 10-item quiz designed to make students aware that they must learn laboratory safety. The items include questions on acid/base accidents, several types of fire extinguishers, and safety glassses. Answers and some explanations are included. (DH)

  15. Answers to questions on National Report of the Slovak Republic. Compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. October 2003

    International Nuclear Information System (INIS)

    2003-10-01

    Slovakia is pleased to present to the State Parties of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management the Answers to questions received on the National Report of the Slovak Republic compiled according to the terms of the Joint Convention (April 2003). Slovakia is ready to provide additional explanations to these Answers during the 1 st Review Meeting. In the Annexes the 254/1994 Coll. LL. Act of the National Council of the Slovak Republic of 25 August 1994 on State Fund of Decommissioning of Nuclear Installations and Handling of Spent Nuclear Fuels and Nuclear Wastes is included

  16. Unanswered clinical questions: a survey of specialists and primary care providers

    Directory of Open Access Journals (Sweden)

    Ellen Brassil, MSLS, MAT, AHIP

    2017-01-01

    Conclusions: While the reasons for unanswered clinical questions varied, thoughtful review of the responses suggested that a combination of educational strategies, embedded librarian services, and technology applications could help providers pursue answers to their clinical questions, enhance patient safety, and contribute to patient-based, self-directed learning.

  17. Ethical questions within the context of final storage of radioactive wastes

    International Nuclear Information System (INIS)

    Gundelach, H.

    1994-01-01

    This work deals with some ethical questions within the context of final storage of radioactive wastes. The questions concern particularly the hazard or safety in general, the relationship between the protection of present and future generation and the necessary limitation of burdens on future generations. (O.L.)

  18. Questions on maintenance of ecological safety in space of the CIS

    International Nuclear Information System (INIS)

    Maharramov, A.A.

    2009-01-01

    Disintegration of the USSR has led to disintegration uniform economic and legal space and it has led to occurrence of some problems in ecological sphere. In given article it is shown some directions of maintenance of ecological safety, agreements on this sphere and organizational mechanisms, forms of mutual relations of the CIS countries in this sphere. At the end it is shownthe basic directions on maintenance of ecological safety in framework of CIS and elements of development of mutual relations of the CIS countries

  19. National nuclear safety report 2005. Convention on nuclear safety

    International Nuclear Information System (INIS)

    2006-01-01

    This National Nuclear Safety Report was presented at the 3rd. Review meeting. In general the information contained in the report are: Highlights / Themes; Follow-up from 2nd. Review meeting; Challenges, achievements and good practices; Planned measures to improve safety; Updates to National report to 3rd. Review meeting; Questions from peer review of National Report; and Conclusions

  20. 324 Building fire hazards analysis implementation plan

    International Nuclear Information System (INIS)

    Eggen, C.D.

    1998-01-01

    In March 1998, the 324 Building Fire Hazards Analysis (FHA) (Reference 1) was approved by the US Department of Energy, Richland Operations Office (DOE-RL) for implementation by B and W Hanford Company (BWHC). The purpose of the FHA was to identify gaps in compliance with DOE Order 5480.7A (Reference 2) and Richland Operations Office Implementation Directive (RLID) 5480.7 (Reference 3), especially in regard to loss limitation. The FHA identified compliance gaps in six areas and provided 20 recommendations to bring the 324 Building into compliance with DOE Order 5480.7A. Additionally, one observation was provided. To date, four of the recommendations and the one observation have been completed. Actions identified for seven of the recommendations are currently in progress. Exemption requests will be transmitted to DOE-RL for three of the recommendations. Six of the recommendations are related to future shut down activities of the facility and the corrective actions are not being addressed as part of this plan. The actions for recommendations associated with the safety related part of the 324 Building and operation of the cells and support areas were evaluated using the Unreviewed Safety Question (USQ) process. Major Life Safety Code concerns have been corrected. The status of the recommendations and actions was confirmed during the July 1998 Fire Protection Assessment. BVMC will use this Implementation Plan to bring the 324 Building and its operation into compliance with DOE Order 5480.7A and RLID 5480.7

  1. Safety in the Chemical Laboratory: Safety in the Chemistry Laboratories: A Specific Program.

    Science.gov (United States)

    Corkern, Walter H.; Munchausen, Linda L.

    1983-01-01

    Describes a safety program adopted by Southeastern Louisiana University. Students are given detailed instructions on laboratory safety during the first laboratory period and a test which must be completely correct before they are allowed to return to the laboratory. Test questions, list of safety rules, and a laboratory accident report form are…

  2. Visit safety

    CERN Document Server

    2012-01-01

    Experiment areas, offices, workshops: it is possible to have co-workers or friends visit these places.     You already know about the official visits service, the VIP office, and professional visits. But do you know about the safety instruction GSI-OHS1, “Visits on the CERN site”? This is a mandatory General Safety Instruction that was created to assist you in ensuring safety for all your visits, whatever their nature—especially those that are non-official. Questions? The HSE Unit will be happy to answer them. Write to safety-general@cern.ch.   The HSE Unit

  3. Questioning the Questions

    Science.gov (United States)

    Tienken, Christopher H.; Goldberg, Stephanie; DiRocco, Dominic

    2010-01-01

    Historical accounts of questioning used in the education process trace back to Socrates. One of the best examples of his use of questioning is found in Plato's "The Republic." Socrates used a series of strategic questions to help his student Glaucon come to understand the concept of justice. Socrates purposefully posed a series of…

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

    Science.gov (United States)

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

    2017-11-01

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

  5. Nuclear Safety

    International Nuclear Information System (INIS)

    1978-09-01

    In this short paper it has only been possible to deal in a rather general way with the standards of safety used in the UK nuclear industry. The record of the industry extending over at least twenty years is impressive and, indeed, unique. No other industry has been so painstaking in protection of its workers and in its avoidance of damage to the environment. Headings are: introduction; how a nuclear power station works; radiation and its effects (including reference to ICRP, the UK National Radiological Protection Board, and safety standards); typical radiation doses (natural radiation, therapy, nuclear power programme and other sources); safety of nuclear reactors - design; key questions (matters of concern which arise in the public mind); safety of operators; safety of people in the vicinity of a nuclear power station; safety of the general public; safety bodies. (U.K.)

  6. Food Safety and Raw Milk

    Science.gov (United States)

    ... and Food Safety Food Safety Modernization Act Raw Milk Recommend on Facebook Tweet Share Compartir RAW MILK ... Decide? Questions & Answers Outbreak Studies Resources & Publications Raw Milk Infographic [PDF – 1 page] More Resources 5 Raw ...

  7. Reviewing the regulatory barriers for nanomedicine: global questions and challenges.

    Science.gov (United States)

    Bowman, Diana M; Gatof, Jake

    2015-01-01

    Nanomedicine will play an increasing role in prevention and treatment across the entire healthcare spectrum. However, their precise market size, economic value and areas of application remain unclear. This opacity, including the question of what constitutes nanomedicine matters, especially when considered alongside the key regulatory questions and concerns. This article begins by placing these key questions into context in relation to the current scientific state of the art, focusing particular attention on the human health and safety context. In exploring these central questions surrounding the regulation of nanomedicine, this perspective also explores existing and suggested frameworks that aim to deal with emerging technologies more generally. It then outlines priority areas for action and general conclusions specific to nanomedicine.

  8. Testing of isolation barrier sealing surfaces

    Energy Technology Data Exchange (ETDEWEB)

    Graves, C.E.

    1994-12-15

    Isolation barrier doors are to be installed in the 105KE and 105KW basins as part of the 1994 unreviewed safety question (USQ) resolution plan to isolate the fuel storage basin from the fuel discharge chute. Included in this installation is the placement of new sealing surfaces for the barriers by affixing stainless steel plates to existing carbon steel angle bars with a specially formulated epoxy adhesive/sealant material. The sealant is a two-part component consisting of an epoxy resin (the condensation product of bisphenol A and epichlorohydrin) and a curing agent (a proprietary cycloaliphatic polyamine). The sealant is solvent free (complying with air pollution regulations) and capable of withstanding the surrounding radiation fields over an estimated 15-year service life. The epoxy sealant experiences negligible water damage partly because of its hydrophobic (water-repelling) nature. With bond tensile strengths measured at greater than 862 kPa (125 lbf/in{sup 2}), the epoxy sealant is judged acceptable for its intended application. The four-hour pot life of the epoxy sealant provides sufficient time to apply the epoxy, examine the epoxy bead for continuity, and position the stainless steel sealing plates.

  9. Tank characterization data report: Tank 241-C-112

    Energy Technology Data Exchange (ETDEWEB)

    Simpson, B.C.; Borsheim, G.L.; Jensen, L.

    1993-09-01

    Tank 241-C-112 is a Hanford Site Ferrocyanide Watch List tank that was most recently sampled in March 1992. Analyses of materials obtained from tank 241-C-112 were conducted to support the resolution of the Ferrocyanide Unreviewed Safety Question (USQ) and to support Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-10-00. Analysis of core samples obtained from tank 241-C-112 strongly indicates that the fuel concentration in the tank waste will not support a propagating exothermic reaction. Analysis of the process history of the tank as well as studies of simulants provided valuable information about the physical and chemical condition of the waste. This information, in combination with the analysis of the tank waste, sup ports the conclusion that an exothermic reaction in tank 241-C-112 is not plausible. Therefore, the contents of tank 241-C-112 present no imminent threat to the workers at the Hanford Site, the public, or the environment from its forrocyanide inventory. Because an exothermic reaction is not credible, the consequences of this accident scenario, as promulgated by the General Accounting Office, are not applicable.

  10. Tank characterization data report: Tank 241-C-112

    International Nuclear Information System (INIS)

    Simpson, B.C.; Borsheim, G.L.; Jensen, L.

    1993-09-01

    Tank 241-C-112 is a Hanford Site Ferrocyanide Watch List tank that was most recently sampled in March 1992. Analyses of materials obtained from tank 241-C-112 were conducted to support the resolution of the Ferrocyanide Unreviewed Safety Question (USQ) and to support Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-10-00. Analysis of core samples obtained from tank 241-C-112 strongly indicates that the fuel concentration in the tank waste will not support a propagating exothermic reaction. Analysis of the process history of the tank as well as studies of simulants provided valuable information about the physical and chemical condition of the waste. This information, in combination with the analysis of the tank waste, sup ports the conclusion that an exothermic reaction in tank 241-C-112 is not plausible. Therefore, the contents of tank 241-C-112 present no imminent threat to the workers at the Hanford Site, the public, or the environment from its forrocyanide inventory. Because an exothermic reaction is not credible, the consequences of this accident scenario, as promulgated by the General Accounting Office, are not applicable

  11. Testing of isolation barrier sealing surfaces

    International Nuclear Information System (INIS)

    Graves, C.E.

    1994-01-01

    Isolation barrier doors are to be installed in the 105KE and 105KW basins as part of the 1994 unreviewed safety question (USQ) resolution plan to isolate the fuel storage basin from the fuel discharge chute. Included in this installation is the placement of new sealing surfaces for the barriers by affixing stainless steel plates to existing carbon steel angle bars with a specially formulated epoxy adhesive/sealant material. The sealant is a two-part component consisting of an epoxy resin (the condensation product of bisphenol A and epichlorohydrin) and a curing agent (a proprietary cycloaliphatic polyamine). The sealant is solvent free (complying with air pollution regulations) and capable of withstanding the surrounding radiation fields over an estimated 15-year service life. The epoxy sealant experiences negligible water damage partly because of its hydrophobic (water-repelling) nature. With bond tensile strengths measured at greater than 862 kPa (125 lbf/in 2 ), the epoxy sealant is judged acceptable for its intended application. The four-hour pot life of the epoxy sealant provides sufficient time to apply the epoxy, examine the epoxy bead for continuity, and position the stainless steel sealing plates

  12. Some questions of monitoring on nuclear installations and quality of safety assessments

    International Nuclear Information System (INIS)

    Labazov, V.

    1998-01-01

    The paper is prepared on the basis of assessment performed by the State Scientific and Technical Centre on Nuclear and Radiation safety which deals with scientific and technical support of the Regulatory Authorities of Ukraine concerning integrity of pressurised elements in the NPP. A number of acute issues on control equipment could be distinguished: placement of sensors should provide adequate information on the data under control necessary for safety analysis; properties of instrumentation should provide trustworthy information about measured values; accurate recommendations should be imposed to operating organisations for performing special analyses for control devices

  13. Conceptual and safety-related questions in the final storage of radioactive waste - a comparison of various types of host rock

    International Nuclear Information System (INIS)

    Kleemann, U.

    2005-01-01

    The German Federal Office for Radiation Protection (BfS) in early November published the synthesis report (BfS 2005) about the conceptual and safety-related specific questions associated with the final storage of radioactive waste. In addition to a condensed version of twelve individual projects, the report contains a description of the results of the peer review and the workshops carried out, in particular an evaluation comparing different types of host rock in Germany. The whole project constitutes a comprehensive documentation of the current state of the art. Findings are expressed at a general level referring neither to the suitability of any specific repository site nor to that of salts as a repository formation, but covering all potential repository formations in deep geologic strata in Germany. The limits to and possibilities of, generic comparisons of various types of host rock are shown. It si seen that, in principle, none of the host rock varieties in Germany would be preferable to others. Numerous problems can be solved only for specific sites, thus requiring site comparisons. While some questions indicate a need for regulatory treatment, the need for basic research is considered to be low. The contribution presents the main findings made in each of the specific projects and the evaluations by the Office. (orig.)

  14. IRSN safety research carried out for reviewing geological disposal safety case

    International Nuclear Information System (INIS)

    Serres, Christophe; Besnus, Francois; Gay, Didier

    2010-01-01

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

  15. VQABQ: Visual Question Answering by Basic Questions

    KAUST Repository

    Huang, Jia-Hong

    2017-03-19

    Taking an image and question as the input of our method, it can output the text-based answer of the query question about the given image, so called Visual Question Answering (VQA). There are two main modules in our algorithm. Given a natural language question about an image, the first module takes the question as input and then outputs the basic questions of the main given question. The second module takes the main question, image and these basic questions as input and then outputs the text-based answer of the main question. We formulate the basic questions generation problem as a LASSO optimization problem, and also propose a criterion about how to exploit these basic questions to help answer main question. Our method is evaluated on the challenging VQA dataset and yields state-of-the-art accuracy, 60.34% in open-ended task.

  16. VQABQ: Visual Question Answering by Basic Questions

    KAUST Repository

    Huang, Jia-Hong; Alfadly, Modar; Ghanem, Bernard

    2017-01-01

    Taking an image and question as the input of our method, it can output the text-based answer of the query question about the given image, so called Visual Question Answering (VQA). There are two main modules in our algorithm. Given a natural language question about an image, the first module takes the question as input and then outputs the basic questions of the main given question. The second module takes the main question, image and these basic questions as input and then outputs the text-based answer of the main question. We formulate the basic questions generation problem as a LASSO optimization problem, and also propose a criterion about how to exploit these basic questions to help answer main question. Our method is evaluated on the challenging VQA dataset and yields state-of-the-art accuracy, 60.34% in open-ended task.

  17. Balancing safety and economics

    International Nuclear Information System (INIS)

    Kroeger, W.; Fischer, P.U.

    2000-01-01

    The safety requirements of NPPs have always aimed at limiting societal risks. This risk approach initially resulted in deterministic design criteria and concepts. In the 1980s the paradigm 'safety at all costs' arose and often led to questionable backfitting measures. Conflicts between new requirements, classical design concepts and operational demands were often ignored. The design requirements for advanced reactors ensure enhanced protection against severe accidents. Still, it is questionable whether the 'no-damage-outside-the-fence' criteria can be achieved deterministically and at competitive costs. Market deregulation and utility privatisation call for a balance between safety and costs, without jeopardising basic safety concepts. An ideal approach must be risk-based and imply modern PSAs and new methods for cost-benefit and ALARA analyses, embed nuclear risks in a wider risk spectrum, but also make benefits transparent within the context of a broader life experience. Governments should define basic requirements, minimum standards and consistent comparison criteria, and strengthen operator responsibility. Internationally sufficient and binding safety requirements must be established and nuclear technology transfer handled in a responsible way, while existing plants, with their continuous backfitting investments, should receive particular attention. (orig.)

  18. Clear progress in nuclear safety worldwide: Convention on nuclear safety concludes

    International Nuclear Information System (INIS)

    2002-01-01

    It has been concluded that a significant progress has been observed in a number of key areas, such as strengthened legislation, regulatory independence, the availability of financial resources, enhanced emergency preparedness and safety improvements at nuclear power plants built to earlier standards. The objective of the Convention is to achieve and maintain a high level of nuclear safety worldwide. During the two week Review Meeting, parties engaged in a 'peer review' process in which the National Reports from individual States were collectively examined and discussed, with written replies provided to all the questions raised. Clear improvement was noted in the quality of the National Reports, the number of questions and the openness and quality of discussion and answers. The Contracting Parties praised the IAEA's various safety review missions and services, which they use widely to help enhance the effectiveness of their national safety arrangements. Forty-six contracting parties participated at the Review Meeting with over 400 delegates attending, including many heads and senior officers from regulatory bodies and experts from industry. To date, the Convention has been signed by sixty-five States and ratified by fifty-four, representing 428 of the 448 nuclear power reactors worldwide

  19. Safety regulation on high-pressure gas and gas business

    International Nuclear Information System (INIS)

    Kim, Du Yeoung; An, Dae Jun

    1978-09-01

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

  20. Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management. France's answers to questions and comments received from other Contracting Parties on its second report for the JC

    International Nuclear Information System (INIS)

    2009-01-01

    The Joint Convention on the Safety of Spent Fuel Management and the Safety of Radioactive Waste Management, referred to as the 'Joint Convention', is the result of international discussions that followed the adoption of the Convention on Nuclear Safety, in 1994. France signed the Joint Convention at the General Conference of the International Atomic Energy Agency (IAEA) held on 29 September 1997, the very first day the Joint Convention was opened for signature. She approved it on 22 February 2000 and filed the corresponding instruments with the IAEA on 27 April 2000. The Joint Convention entered into force on 18 June 2001. For many years, France has been taking an active part in the pursuit of international actions to reinforce nuclear safety and considers the Joint Convention to be a key step in that direction. The fields covered by the Joint Convention have long been part of the French approach to nuclear safety. For his second report, France presented a document reflecting the viewpoints of the various stakeholders (regulatory authorities and operators). Thus, for each of the chapters in which the regulatory authority is not the only party to express its point of view, a three-stage structure was adopted: first of all a description by the regulatory authority of the regulations, followed by a presentation by the operators of the steps taken to meet the regulations and finally, an analysis by the regulatory authority of the steps taken by the operators. France received questions and comments from the other contracting parties of the joint convention and answered them in the present document

  1. Investor Outlook: The Unanswered Questions.

    Science.gov (United States)

    Schimmer, Joshua; Breazzano, Steven

    2017-06-01

    The year 2016 was an exciting one for the field, with several notable successes outweighing a few setbacks. As the number of patients treated successfully (and safely) with gene therapy grows, the totality of evidence points to a robust platform with utility in orphan/ultra-orphan diseases as well as broader indications, and with hopefully increasing predictability of results. This year promises to feature more patients treated, more clinical data, and more gene therapy products in registration-enabling studies. For the field to continue to advance and mature into the next great drug delivery platform, a few unsolved and remaining questions need to be addressed, including the business model for cures, a broader safety/efficacy profile once more patients are treated, optimization of delivery (including next-generation approaches), and greater understanding of the impact of competitive dynamics. In this report, we detail the success and setbacks of 2016 and highlight the unanswered questions-and how the answers may shape the field in the years ahead.

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

    CERN Document Server

    International Organization for Standardization. Geneva

    2002-01-01

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

  3. Electronics and data processing for safety

    International Nuclear Information System (INIS)

    1995-01-01

    Industrial installations, and in particular installations involving risk, are more and more monitored and controlled by computerized systems. The use of such systems raises questions about their contribution to the installation safety and about the qualities required in these systems to avoid additional risk. The February 1995 Electronics Days were organized by the CEA-LETI Department of Electronics and Nuclear Instrumentation to try to answer these questions. Four sessions were organized on the following topics: computerized systems and functioning safety, components and architectures, softwares and norms, and tools and methods. Only the communications dealing with the safety of computerized systems and components involved in nuclear applications have been retained (17 over 36). (J.S.)

  4. Questioning Questions: Elementary Teachers' Adaptations of Investigation Questions Across the Inquiry Continuum

    Science.gov (United States)

    Biggers, Mandy

    2018-02-01

    Questioning is a central practice in science classrooms. However, not every question translates into a "good" science investigation. Questions that drive science investigations can be provided by many sources including the teacher, the curriculum, or the student. The variations in the source of investigation questions were explored in this study. A dataset of 120 elementary science classroom videos and associated lesson plans from 40 elementary teachers (K-5) across 21 elementary school campuses were scored on an instrument measuring the amount of teacher-direction or student-direction of the lessons' investigation questions. Results indicated that the investigation questions were overwhelmingly teacher directed in nature, with no opportunities for students to develop their own questions for investigation. This study has implications for researchers and practitioners alike, calling attention to the teacher-directed nature of investigation questions in existing science curriculum materials, and the need for teacher training in instructional strategies to adapt their existing curriculum materials across the continuum of teacher-directed and student-directed investigation questions. Teachers need strategies for adapting the teacher-directed questions provided in their existing curriculum materials in order to allow students the opportunity to engage in this essential scientific practice.

  5. Food quality and safety: Consumer perception and demand

    DEFF Research Database (Denmark)

    Grunert, Klaus G.

    2005-01-01

    choice and consumer demand, addressing questions of price perception and the validity of willingness-to-pay measurements. It is concluded that food quality and safety are central issues in today's food economics, though many research questions remain to be addressed. Udgivelsesdato: SEP 1......Research on consumer quality perception is reviewed using the Total Food Quality Model as a structuring device. The relationship between food safety and quality is addressed, and is discussed in the context of research on consumer risk perception. Quality and safety perception is linked to food...

  6. Food quality and safety: Consumer perception and demand

    DEFF Research Database (Denmark)

    Grunert, Klaus G.

    2005-01-01

    Research on consumer quality perception is reviewed using the Total Food Quality Model as a structuring device. The relationship between food safety and quality is addressed, and is discussed in the context of research on consumer risk perception. Quality and safety perception is linked to food...... choice and consumer demand, addressing questions of price perception and the validity of willingness-to-pay measurements. It is concluded that food quality and safety are central issues in today's food economics, though many research questions remain to be addressed. Udgivelsesdato: SEP 1...

  7. Indicators of safety culture - selection and utilization of leading safety performance indicators

    Energy Technology Data Exchange (ETDEWEB)

    Reiman, Teemu; Pietikaeinen, Elina (VTT, Technical Research Centre of Finland (Finland))

    2010-03-15

    Safety indicators play a role in providing information on organizational performance, motivating people to work on safety and increasing organizational potential for safety. The aim of this report is to provide an overview on leading safety indicators in the domain of nuclear safety. The report explains the distinction between lead and lag indicators and proposes a framework of three types of safety performance indicators - feedback, monitor and drive indicators. Finally the report provides guidance for nuclear energy organizations for selecting and interpreting safety indicators. It proposes the use of safety culture as a leading safety performance indicator and offers an example list of potential indicators in all three categories. The report concludes that monitor and drive indicators are so called lead indicators. Drive indicators are chosen priority areas of organizational safety activity. They are based on the underlying safety model and potential safety activities and safety policy derived from it. Drive indicators influence control measures that manage the socio technical system; change, maintain, reinforce, or reduce something. Monitor indicators provide a view on the dynamics of the system in question; the activities taking place, abilities, skills and motivation of the personnel, routines and practices - the organizational potential for safety. They also monitor the efficacy of the control measures that are used to manage the socio technical system. Typically the safety performance indicators that are used are lagging (feedback) indicators that measure the outcomes of the socio technical system. Besides feedback indicators, organizations should also acknowledge the important role of monitor and drive indicators in managing safety. The selection and use of safety performance indicators is always based on an understanding (a model) of the socio technical system and safety. The safety model defines what risks are perceived. It is important that the safety

  8. Indicators of safety culture - selection and utilization of leading safety performance indicators

    International Nuclear Information System (INIS)

    Reiman, Teemu; Pietikaeinen, Elina

    2010-03-01

    Safety indicators play a role in providing information on organizational performance, motivating people to work on safety and increasing organizational potential for safety. The aim of this report is to provide an overview on leading safety indicators in the domain of nuclear safety. The report explains the distinction between lead and lag indicators and proposes a framework of three types of safety performance indicators - feedback, monitor and drive indicators. Finally the report provides guidance for nuclear energy organizations for selecting and interpreting safety indicators. It proposes the use of safety culture as a leading safety performance indicator and offers an example list of potential indicators in all three categories. The report concludes that monitor and drive indicators are so called lead indicators. Drive indicators are chosen priority areas of organizational safety activity. They are based on the underlying safety model and potential safety activities and safety policy derived from it. Drive indicators influence control measures that manage the socio technical system; change, maintain, reinforce, or reduce something. Monitor indicators provide a view on the dynamics of the system in question; the activities taking place, abilities, skills and motivation of the personnel, routines and practices - the organizational potential for safety. They also monitor the efficacy of the control measures that are used to manage the socio technical system. Typically the safety performance indicators that are used are lagging (feedback) indicators that measure the outcomes of the socio technical system. Besides feedback indicators, organizations should also acknowledge the important role of monitor and drive indicators in managing safety. The selection and use of safety performance indicators is always based on an understanding (a model) of the socio technical system and safety. The safety model defines what risks are perceived. It is important that the safety

  9. Proceedings of the driving safety technology forum

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    This one day forum focused on improving driving safety in the petroleum industry by introducing new technologies and strategies. The forum featured several keynote addresses on driving safety as well as the Government of Alberta's Tactical Plan and Alberta Road Safety at Work Strategy. Presentations consisted of success stories of new technology or process applications or proposed technology demonstration projects followed by question and answer panels around the following topics: industry and government strategies; driver fatigue management and prevention; driver behaviour and culture change; vehicle monitoring systems and innovative wildlife avoidance techniques. Specific presentations addressed BP's driving safety strategy, in-cabin air quality and truck drivers' health and safety and how Talisman Energy implemented oilfield fleet safety using event driven automated vehicle location technologies. A total of 3 keynote addresses, 3 panel question and answer sessions and 11 presentations were presented at the conference, of which 3 have been catalogued separately for inclusion in this database. refs., tabs., figs.

  10. Vision and commercial motor vehicle driver safety : vol. 1 : evidence report

    Science.gov (United States)

    2008-06-06

    The purpose of this evidence report is to address several key questions posed by the Federal Motor Carrier Safety Administration (FMCSA) that pertain to vision and commercial motor vehicle (CMV) driver safety. Each of these key questions was develope...

  11. National Chemistry Teacher Safety Survey

    Science.gov (United States)

    Plohocki, Barbra A.

    This study evaluated the status of secondary school instructional chemistry laboratory safety using a survey instrument which focused on Teacher background Information, Laboratory Safety Equipment, Facility Safety, General Safety, and a Safety Content Knowledge Survey. A fifty question survey instrument based on recent research and questions developed by the researcher was mailed to 500 secondary school chemistry teachers who participated in the 1993 one-week Woodrow Wilson National Fellowship Foundation Chemistry Institute conducted at Princeton University, New Jersey. The data received from 303 respondents was analyzed by t tests and Analysis of Variance (ANOVA). The level of significance for the study was set at ~\\ performance on the Safety Content Knowledge Survey and secondary school chemistry teachers who have had undergraduate and/or graduate safety training and those who have not had undergraduate and/or graduate safety training. Secondary school chemistry teachers who attended school district sponsored safety inservices did not score higher on the Safety Content Knowledge Survey than teachers who did not attend school district sponsored safety inservice sessions. The type of school district (urban, suburban, or rural) had no significant correlation to the type of laboratory safety equipment found in the instructional chemistry laboratory. The certification area (chemistry or other type of certificate which may or may not include chemistry) of the secondary school teacher had no significant correlation to the type of laboratory equipment found in the instructional chemistry laboratory. Overall, this study indicated a majority of secondary school chemistry teachers were interested in attending safety workshops applicable to chemistry safety. Throughout this research project, many teachers indicated they were not adequately instructed on the collegiate level in science safety and had to rely on common sense and self-study in their future teaching careers.

  12. Probabilistic modeling of dietary intake of substances - The risk management question governs the method

    NARCIS (Netherlands)

    Pieters MN; Ossendorp BC; Bakker MI; Slob W; SIR

    2005-01-01

    In this report the discussion on the use of probabilistic modeling in relation to pesticide use in food crops is analyzed. Due to different policy questions the current discussion is complex and considers safety of an MRL as well as probability of a health risk. The question regarding the use of

  13. Electric Power Lines : Questions and Answers on Research into Health Effects.

    Energy Technology Data Exchange (ETDEWEB)

    United States. Bonneville Power Administration.

    1994-05-01

    Most people know that electric power lines, like the wiring in our homes, can cause serious electric shocks if we`re not careful. Many people also want to know whether the electric and magnetic fields (EMF) produced by power lines and other electrical devices cause health effects. The purpose of this booklet is to answer some common questions that the Bonneville Power Administration (BPA) receives about the possible effects of power lines on health. First, some basic electrical terms are defined, and electric and magnetic fields are debed. Next, answers are given to several questions about recent scientific studies. Some important information about electrical safety follows. We then describe how BPA is addressing public concerns about potential health effects of power lines. The last section tells you how to obtain more detailed information about the health and safety issues summarized in this booklet.

  14. Safety culture and quality management

    International Nuclear Information System (INIS)

    Edmondson, B.

    1992-01-01

    The concept of Safety Culture is defined along with its general attributes. The characteristics of a satisfactory level of Safety Culture, as it applies to an operating organisation are then presented in two ways, descriptive and as sets of questions against which an organisation's provision may be judged. (author) 1 fig

  15. Research, climate, energy : Questions of destiny for the chemical industry

    Energy Technology Data Exchange (ETDEWEB)

    Kastinen, A., email: aimo.kastinen@chemind.fi

    2010-07-01

    Registration for the first phase of Reach finishes at the end of November. Then we will see whether the standard of legislation has been set correctly in respect of the EU's operational ability. If it isn't, significant problems will result for the community's treatment of materials and the EU's competitiveness, and Reach's value as a global model will become questionable. Also, the CLP regulation concerning classification, labelling and packaging of chemicals will start to come into effect as from the beginning of December. In the first phase, the question is one of classification of substances, and gradually the requirements will be applied to mixtures too. At the same time, Safety Data Sheets shall be renewed in accordance with their own transition period. The current product legislation concerning chemicals shall be fully revised by the mid-point of the decade, but before then company safety officers will have to do lots of work to change the previous routines

  16. THE VACCINATION AGAINST VARICELLA. THE ANSWERS TO THE PEDIATRISTS QUESTIONS

    Directory of Open Access Journals (Sweden)

    V.К. Tatochenko

    2009-01-01

    Full Text Available Varicella is a disease which can be stopped by methods of specific prophylaxis. At the same time, there are no official recommendations on vaccinal prophylaxis of varicella in Russia nowadays. The article presents the answers to the most frequently asked questions of pediatrists concerning vaccination techniques, its effectiveness and safety, and vaccination in epidemic nidus. Special attention was given to the questions of vaccinal prophylaxis of varicella in immunocompromised patients.Key words: varicella, prophylaxis, vaccination.(Voprosy sovremennoi pediatrii — Current Pediatrics. 2009;8(3:114-119

  17. Answering Key Fuel Cycle Questions

    International Nuclear Information System (INIS)

    Piet, S.J.; Dixon, B.W.; Bennett, R.G.; Smith, J.D.; Hill, R.N.

    2004-01-01

    Given the range of fuel cycle goals and criteria, and the wide range of fuel cycle options, how can the set of options eventually be narrowed in a transparent and justifiable fashion? It is impractical to develop all options. We suggest an approach that starts by considering a range of goals for the Advanced Fuel Cycle Initiative (AFCI) and then posits seven questions, such as whether Cs and Sr isotopes should be separated from spent fuel and, if so, what should be done with them. For each question, we consider which of the goals may be relevant to eventually providing answers. The AFCI program has both ''outcome'' and ''process'' goals because it must address both waste already accumulating as well as completing the fuel cycle in connection with advanced nuclear power plant concepts. The outcome objectives are waste geologic repository capacity and cost, energy security and sustainability, proliferation resistance, fuel cycle economics, and safety. The process objectives are rea diness to proceed and adaptability and robustness in the face of uncertainties

  18. Safety Goal, Multi-unit Risk and PSA Uncertainty

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Joon-Eon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    The safety goal is an answer of each country to the question 'How safe is safe enough?'. Table 1 shows some examples of the safety goal. However, many countries including Korea do not have the official safety goal for NPPs up to now since the establishment of safety goal is not just a technical issue but a very complex socio-technical issue. In establishing the safety goal for nuclear facilities, we have to consider various factors including not only technical aspects but also social, cultural ones. Recently, Korea is trying to establish the official safety goal. In this paper, we will review the relationship between the safety goal and Probabilistic Safety Assessment (PSA). We will also address some important technical issues to be considered in establishing the safety goal for NPPs from PSA point of view, i.e. a multi-unit risk issue and the uncertainty of PSA. In this paper, we reviewed some issues related to the safety goal and PSA. We believe that the safety goal is to be established in Korea considering the multi-unit risk. In addition, the relationship between the safety goal and PSA should be also defined clearly since PSA is the only way to answer to the question 'How safe is safe enough?'.

  19. Nuclear safety. Seguranca nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Aveline, A [Rio Grande do Sul Univ., Porto Alegre, RS (Brazil). Inst. de Fisica

    1981-01-01

    What is nuclear safety Is there any technical way to reduce risks Is it possible to put them at reasonable levels Are there competitiveness and economic reliability to employ the nuclear energy by means of safety technics Looking for answers to these questions the author describes the sources of potential risks to nuclear reactors and tries to apply the answers to the Brazilian Nuclear Programme. (author).

  20. France's answers to question and comments received from other contracting parties on its 1. report for the JC

    International Nuclear Information System (INIS)

    2003-10-01

    The Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management is supplementing the Convention on Nuclear Safety. It was approved by France on February 22, 2000 and it entered into force on June 18, 2001. France has received 211 questions, coming from 19 Contracting Parties, on its first report and has provided written answers to each one. These answers were gathered in a single document, which lists them along the articles of the Convention. France has presented these answers on November 5, 2003, at the review meeting of the contracting Parties of the Convention and has decided to make them available to the public, however without mention of the countries that had asked them. The 211 questions received on the first report for the Joint Convention are listed along the sections suggested by the guidelines for the answers to the articles of the convention, sorted by the related page number of the French report and, within each section, grouped by issues raised. The written answers to each question have been coordinated by the French Nuclear Safety Authority (ASN), but have been provided either by the regulators or by the operators (or even both) depending on the related issue. In the case where various questions are related to a same issue but are referred to different articles of the Conventions, they have been referred to the most relevant article in order to have the same issue dealt with in a single location in the present answers report. The answer to each question is provided immediately under the related question

  1. Electric Power Lines : Questions and Answers on Research into Health Effects.

    Energy Technology Data Exchange (ETDEWEB)

    United States. Bonneville Power Administration.

    1993-11-01

    Most people know that electric power lines, like the wiring in our homes, can cause serious electric shocks if we`re not careful. Many people also want to know whether the electric and magnetic fields (EMF) produced by power lines and other electrical devices cause health effects. The purpose of this pamphlet is to answer some common questions that the Bonneville Power Administration (BPA) receives about the possible effects of power lines on health. (BPA is the Pacific Northwest`s Federal electric power marketing agency.) First, some basic electrical terms are defined, and electric and magnetic fields are described. Next, answers are given to several questions about recent scientific studies. We then describe how BPA is addressing public concerns raised by these studies. Some important information about electrical safety follows. The last section tells you how to obtain more detailed information about the health and safety issues summarized in this pamphlet.

  2. Safety Bulletin 2014-2

    CERN Multimedia

    HSE Unit

    2014-01-01

    The HSE Unit would like to inform you that the Safety Bulletin 2014-2 entitled “False floors: real dangers” has just been released.     The Bulletin is available on EDMS under the following number: 1366385. We would like to remind you that HSE Safety Bulletins are published in English and French and incorporate feedback from incidents/near misses/accidents that have occurred on the CERN site, with the aim of improving prevention. We remain at your disposal in case you have further questions: safety.bulletin@cern.ch.

  3. Safety supervision on high-pressure gas regulations

    International Nuclear Information System (INIS)

    Lee, Won Il

    1991-01-01

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

  4. Questioning Questions: Elementary Teachers' Adaptations of Investigation Questions across the Inquiry Continuum

    Science.gov (United States)

    Biggers, Mandy

    2018-01-01

    Questioning is a central practice in science classrooms. However, not every question translates into a "good" science investigation. Questions that drive science investigations can be provided by many sources including the teacher, the curriculum, or the student. The variations in the source of investigation questions were explored in…

  5. Safety culture in transport

    International Nuclear Information System (INIS)

    Decobert, V.

    1998-01-01

    'Safety culture' is a wording that appeared first in 1986, during the evaluation of what happened during the Tchernobyl accident. Safety culture is defined in the IAEA 75-INSAG-4 document as the characteristics and attitude which, in organizations and in men behaviours, make that questions related to safety of nuclear power plants benefits, in priority, of the attention that they need in function of their importance. The INSAG-4 document identifies three different elements necessary to the development of the safety culture: commitment of the policy makers, commitment of the managers of the industry, and commitment of individuals. This paper gives examples to show how safety culture is existing in the way Transnucleaire performs the activities in the field of transport of nuclear materials. (author)

  6. Safety advice sheets

    CERN Multimedia

    HSE Unit

    2013-01-01

    You never know when you might be faced with questions such as: when/how should I dispose of a gas canister? Where can I find an inspection report? How should I handle/store/dispose of a chemical substance…?   The SI section of the DGS/SEE Group is primarily responsible for safety inspections, evaluating the safety conditions of equipment items, premises and facilities. On top of this core task, it also regularly issues “Safety Advice Sheets” on various topics, designed to be of assistance to users but also to recall and reinforce safety rules and procedures. These clear and concise sheets, complete with illustrations, are easy to display in the appropriate areas. The following safety advice sheets have been issued so far: Other sheets will be published shortly. Suggestions are welcome and should be sent to the SI section of the DGS/SEE Group. Please send enquiries to general-safety-visits.service@cern.ch.

  7. The Five Key Questions of Human Performance Modeling.

    Science.gov (United States)

    Wu, Changxu

    2018-01-01

    Via building computational (typically mathematical and computer simulation) models, human performance modeling (HPM) quantifies, predicts, and maximizes human performance, human-machine system productivity and safety. This paper describes and summarizes the five key questions of human performance modeling: 1) Why we build models of human performance; 2) What the expectations of a good human performance model are; 3) What the procedures and requirements in building and verifying a human performance model are; 4) How we integrate a human performance model with system design; and 5) What the possible future directions of human performance modeling research are. Recent and classic HPM findings are addressed in the five questions to provide new thinking in HPM's motivations, expectations, procedures, system integration and future directions.

  8. Safety review of experiments at Albuquerque Operations Office

    International Nuclear Information System (INIS)

    Elliott, K.

    1984-01-01

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

  9. Rhetorical questions or rhetorical uses of questions?

    Directory of Open Access Journals (Sweden)

    Špago Džemal

    2016-12-01

    Full Text Available This paper aims to explore whether some rhetorical questions contain certain linguistic elements or forms which would differentiate them from answer-eliciting and action-eliciting questions, and thereby hint at their rhetorical nature even outside the context. Namely, despite the fact that the same questions can be rhetorical in one context, and answer-eliciting in another, some of them are more likely to be associated with rhetorical or non-rhetorical use. The analysis is based on extensive data (over 1200 examples of rhetorical questions taken from 30 plays by two British and two American writers, and the results are expected to give an insight into whether we can talk about rhetorical questions or just a rhetorical use of questions.

  10. Safety Day Prize Competition: results and answers

    CERN Multimedia

    HSE Unit

    2014-01-01

    The three winners of the Safety Day Prize Competition are...   • 1st Prize: Fernando LEITE PEREIRA – smoke detector • 2nd Prize: Thomas DE BORTOLI – water filter jug • 3rd Prize: Matti KALLIOKOSKI – safety goggles Please see the image below for the answers to the questionnaire. If you have any questions regarding the Safety Day, please contact: safety.communication@cern.ch. And again, thank you to all the participants!

  11. Questions and answers based on revised 10 CFR Part 20

    International Nuclear Information System (INIS)

    Borges, T.; Stafford, R.S.; Lu, P.Y.; Carter, D.

    1994-05-01

    NUREG/CR-6204 is a collection of questions and answers that were originally issued in seven sets and which pertain to revised 10 CFR Part 20. The questions came from both outside and within the NRC. The answers were compiled and provided by NRC staff within the offices of Nuclear Reactor Regulation, Nuclear Material Safety and Safeguards, Nuclear Regulatory Research, the Office of State Programs, and the five regional offices. Although all of the questions and answers have been reviewed by attorneys in the NRC Office of the General Counsel, they do not constitute official legal interpretations relevant to revised 10 CFR Part 20. The questions and answers do, however, reflect NRC staff decisions and technical options on aspects of the revised 10 CFR Part 20 regulatory requirements. This NUREG is being made available to encourage communication among the public, industry, and NRC staff concerning the major revisions of the NRC's standards for protection against radiation

  12. Question of right to stay of nuclear-powered vessels in foreign ports

    International Nuclear Information System (INIS)

    Szafranek, J.

    1976-01-01

    Question of right to stay of nuclear-powered vessels in foreign ports is considered in the light of London Convention on Safety of Life at Sea, Brussels Convention on Liability for Operation of Nuclear Ships and bilateral agreements. (Z.M.)

  13. Taking ownership of safety. What are the active ingredients of safety coaching and how do they impact safety outcomes in critical offshore working environments?

    Science.gov (United States)

    Krauesslar, Victoria; Avery, Rachel E; Passmore, Jonathan

    2015-01-01

    Safety coaching interventions have become a common feature in the safety critical offshore working environments of the North Sea. Whilst the beneficial impact of coaching as an organizational tool has been evidenced, there remains a question specifically over the use of safety coaching and its impact on behavioural change and producing safe working practices. A series of 24 semi-structured interviews were conducted with three groups of experts in the offshore industry: safety coaches, offshore managers and HSE directors. Using a thematic analysis approach, several significant themes were identified across the three expert groups including connecting with and creating safety ownership in the individual, personal significance and humanisation, ingraining safety and assessing and measuring a safety coach's competence. Results suggest clear utility of safety coaching when applied by safety coaches with appropriate coach training and understanding of safety issues in an offshore environment. The current work has found that the use of safety coaching in the safety critical offshore oil and gas industry is a powerful tool in managing and promoting a culture of safety and care.

  14. Safety Culture Survey in Krsko NPP

    International Nuclear Information System (INIS)

    Strucic, M.; Bilic Zadric, T.

    2008-01-01

    The high level of nuclear safety, stability and competitiveness of electricity production, and public acceptability are the main objectives of Krsko Nuclear Power Plant. This is achievable only in environment where strong Safety Culture is taking dominant place in the way how employees communicate, perform tasks, share their ideas and attitudes, and demonstrate their concern in all aspects of work and coexistence. To achieve these objectives, behaviour of all employees as well as specific ethical values must become more transparent and that must arise from the heart of organization. Continuous ongoing and periodic self assessments of Safety Culture in Krsko NPP present major tools in implementation process of this approach. Benefits from Periodic interdisciplinary focused self assessment approach, which main intention is finding the strengths and potential areas for improvements, was used second time to assess the area of Safety Culture in Krsko NPP. Main objectives of self assessment, performed in 2006, were to increase the awareness of the present culture, to serve as a basis for improvement and to keep track of the effects of change or improvement over a longer period of time. For the purpose of effective self assessment, extensive questionnaire was used to obtain information that is representative for whole organization. Wide range of questions was chosen to cover five major characteristics of safety culture: Accountability for safety is clear, Safety is integrated into all activities, Safety culture is learning-driven, Leadership for safety is clear and Safety is a clearly recognized value. 484 Krsko NPP employees and 96 contractors were participated in survey. 70-question survey provided information that was quantified and results compared between groups. Anonymity of participant, as well as their willingness to contribute in this assessment implicates the high level of their openness in answering the questions. High number of participant made analysis of

  15. ENSI Approach to Oversight of Safety Culture

    International Nuclear Information System (INIS)

    Humbel Haag, Claudia

    2012-01-01

    Claudia Humbel Haag presented developments in ENSI approach to safety culture oversight. ENSI has developed a definition/understanding of Safety Culture and a concept of how to perform oversight of Safety Culture. ENSI defines safety culture in the following way: Safety Culture comprises the behaviour, world views (in the sense of conceptualisations of reality and explanation models), values (in the sense of aims and evaluation scales), and features of the physical environment (specifically, the nuclear power plant and the documents used) which are shared by many members of an organization, in as much as these are of significance to nuclear safety. A model of the accessibility of safety culture was presented ranging from the observable (external aspects of safety culture), to aspects that are accessible by asking questions, through to aspects that are not accessible (internal part of safety culture). ENSI considers observable aspects through the existing systematic safety assessment compliance program. Aspects that are observable by asking questions will be addressed by additional oversight activities outside the systematic assessment program. Aspects that are not accessible are addressed by helping the licensee to re-think its safety culture through proactive discussions on safety culture. Reports are issued to the licensee on assumptions and observations identified through the discussions. The conclusions of the presentation emphasised the importance of basing any interventions in this area on a solid understanding of the concept of safety culture. ENSI safety culture oversight principles were also described. These include licensee responsibility for safety, and the need for the regulator to critically review their own activities to ensure a positive influence on the licensee

  16. A brief overview of Ignalina NPP safety issues

    International Nuclear Information System (INIS)

    Almenas, K.; Ushpuras, E.

    1998-01-01

    A description of the safety of Ignalina NPP in a very popular form is presented. Answers to the most frequently recurring questions concerning the Ignalina NPP are provided based on recently completed international studies. Questions are like these: can a similar accident to the one that occurred in Chernobyl take place at Ignalina NPP, does the Ignalina NPP have a containment, what are the probabilities and potential consequences of accidents, etc. The brochure contains a short description of Ignalina NPP safety improvement programs

  17. Japan reforms its nuclear safety

    International Nuclear Information System (INIS)

    Anon.

    2013-01-01

    The Fukushima Daiichi NPP accident deeply questioned the bases of nuclear safety and nuclear safety regulation in Japan. It also resulted in a considerable loss of public confidence in the safety of nuclear power across the world. Although the accident was caused by natural phenomena, institutional and human factors also largely contributed to its devastating consequences, as shown by the Japanese Diet's and Government's investigation reports. 'Both regulators and licensees were held responsible and decided to fully reconsider the existing approaches to nuclear safety. Consequently, the regulatory system underwent extensive reform based on the lessons learned from the accident,' Yoshihiro Nakagome, the President of Japan Nuclear Energy Safety Organisation, an ETSON member TSO, explains. (orig.)

  18. National nuclear safety report 2004. Convention on nuclear safety

    International Nuclear Information System (INIS)

    2004-01-01

    The second National Nuclear Safety Report was presented at the second review meeting of the Nuclear Safety Convention. At that time it was concluded that Argentina met the obligations of the Convention. This third National Nuclear Safety Report is an updated report which includes all safety aspects of the Argentinian nuclear power plants and the measures taken to enhance the safety of the plants. The present report also takes into account the observations and discussions maintained during the second review meeting. The conclusion made in the first review meeting about the compliance by Argentina of the obligations of the Convention are included as Annex I and those belonging to the second review meeting are included as Annex II. In general, the information contained in this Report has been updated since March 31, 2001 to April 30, 2004. Those aspects that remain unchanged were not addressed in this third report. As a result of the detailed analysis of all the Articles, it can be stated that the country fulfils all the obligations imposed by the Nuclear Safety Convention. The questions and answers originated at the Second Review Meeting are included as Annex III

  19. Comments on topical questions of nuclear energy

    International Nuclear Information System (INIS)

    Butz, H.; Noll, M.

    1978-05-01

    During the 7th legislative period (1972/76) of the German Bundestag the Federal Government has repeatedly commented on questions concerning nuclear energy. The present documentation comprises a selection of the most important issues. The collection contains in particular: written and oral answers of the Federal Government to written or oral questions of members of parliament; answers of the Federal Government to major and minor interpellations of fractions or factions; statements of the chancellor, the ministers and permanent secretaries; bills of the Federal Government if they were issued as parliamentary documents or as plenary minutes. The main attention when selecting the documents was drawn to giving complete recording of the statements on the safety of nuclear plants and on radiation protection. Furthermore, the comments on questions concerning nuclear energy were considered both in general and in connection with alternative energy sources. Eventually, the general situation concerning energy could be verified. The selection of documents has certainly not thoroughly remained uninfluenced by subjective decisions. The parliamentary documents and plenary minutes given here are recorded by chronological order. An index of subject headings will facilitate access to all documents. (orig.) 891 HP [de

  20. The development of reactor operator license examination question bank

    International Nuclear Information System (INIS)

    Kim, In Hwan; Woo, S. M.; Kam, S. C.; Nam, K. J.; Lim, H. P.

    2001-12-01

    The number of NPP keeps increasing therefore there is more need of reactor operators. This trend requires the more efficiency in managing the license examination. Question bank system will help us to develop good quality examination materials and keep them in it. The ultimate purpose of the bank system is for selecting qualified reactor operators who are primarily responsible for the safety of reactor operation in NPP

  1. Food safety and the reversed political consumer

    DEFF Research Database (Denmark)

    Christensen, Tove; Denver, Sigrid; Mørkbak, Morten Raun

    We address the question of whether people act as political consumers in relation to food safety. By linking evidence from economic valuation studies on consumers' willingness to pay with sociological studies on consumer behaviour and market studies, we find that food safety does not call...

  2. Analysis of safety culture components based on site interviews

    International Nuclear Information System (INIS)

    Ueno, Akira; Nagano, Yuko; Matsuura, Shojiro

    2002-01-01

    Safety culture of an organization is influenced by many factors such as employee's moral, safety policy of top management and questioning attitude among site staff. First this paper analyzes key factors of safety culture on the basis of site interviews. Then the paper presents a safety culture composite model and its applicability in various contexts. (author)

  3. For safety in procurement, follow the guide!

    CERN Multimedia

    HSE Unit

    2014-01-01

    At one time or another, whether as part of a project or for an activity or service, you may find that you have to write a technical specification before placing an order for equipment or machinery. In all cases, when specifying what you need, you must make sure that aspects linked to safety and, in some cases, radiation protection and the protection of the environment, are taken into account in your invitation to tender/price enquiry.   In order to help you with this, the HSE Unit has just published Safety Guideline GS 0-0-1: “27 Key Questions to Ensure that Safety Aspects are Integrated into Invitations to Tender". This guide, available on EDMS under document number 1334815, has been drawn up after the verification of safety aspects of over 300 invitations to tender recently issued by CERN. It collates the most commonly received comments and remarks concerning safety in a question-and-answer format, so you will find plenty of explanations and points to include in your doc...

  4. Health Professionals and hand hygiene: a question of pediatric patient safety

    Directory of Open Access Journals (Sweden)

    Daisy Zanchi de Abreu Botene

    Full Text Available This paper is a qualitative descriptive study, which aims to analyze how the academic education concerning hand hygiene contributes to the pediatric patient safety. This research was developed in an university hospital in Southern Brazil, in the pediatric unit, during the period of August to December, 2012. Sixteen healthcare professionals participated (doctors, nurses and physical therapists. A semi-structured interview was used to gather information. Data was organized by the software QSR Nvivo and analyzed using the content analysis technique. The results allowed us to list two thematic categories: "Hand hygiene and healthcare professionals' academic education"; and "Hand hygiene and professional life". The first thematic category will be presented in this paper. It was identified that the academic education contributes in an ineffective way to the creation of a patient safety culture. According to the professionals, there are gaps during the educational process regarding hand hygiene. The topic is treated in an ineffective and not very significant way to the learning and adhesion of hand hygiene in the professional life. It is recommended that, for the internalization of the practice by future professionals, a transversal, continuous and systematical approach is adopted during the professional's training, evaluations concerning the hand hygiene are done throughout the academic life as well as healthcare professors bethink the topic.

  5. Implementation of safety goals in NRC's regulatory process

    International Nuclear Information System (INIS)

    Murley, T.E.

    1985-01-01

    In May 1983 the Nuclear Regulatory Commission issued a policy statement on Safety Goals For Nuclear Power Plant Operation. The Commission at the same time judged that a two-year evaluation period was necessary to judge the effectiveness of the goals and design objectives, and directed the staff to develop information and understanding as to how to further define and use the design objectives and the cost-benefit guidelines. In carrying out the Commission's mandate, the staff framed three major questions to be addressed during the safety goal evaluation period. These three questions are: 1) to what extent is it practical to use safety goals in the regulatory process. 2) Should the quantitative design objectives be modified or supplemented. If so, how. 3) How should the safety goals be implemented at the end of the evaluation period. The staff's conclusions are discussed

  6. Nuclear energy by way of 110 questions

    International Nuclear Information System (INIS)

    Mandil, C.; Borotra, F.

    1996-01-01

    The main goal of this updated edition is to provide the general public with information on the civil nuclear policy in France. Twelve chapters deal with following topics: nuclear economy, nuclear industry, nuclear fuel cycle and nuclear waste, nuclear safety, radioactivity and health, nuclear accidents in the world, nuclear energy and environment, inspection planning, information, nuclear proliferation prevention, nuclear energy in the world and in the future. At the end of each chapter the authors answer a set of questions corresponding to the general pubic queries. (N.T.)

  7. Some questions and answers concerning fast reactors

    International Nuclear Information System (INIS)

    Marshall, W.

    1980-01-01

    The theme of the lecture is the place of the fast reactor in an evolving nuclear programme. The whole question of plutonium is first considered, ie its method of production and the ways in which it can be used in the fast reactor fuel cycle. Whether fast reactors are necessary is then discussed. Their safety is examined with particular attention to those design features which are most criticised ie high volumetric power density of the core, and the use of liquid sodium as coolant. Attention is then paid to environmental and safeguard aspects. (U.K.)

  8. Can we share questions? Performance of questions from different question banks in a single medical school.

    Science.gov (United States)

    Freeman, Adrian; Nicholls, Anthony; Ricketts, Chris; Coombes, Lee

    2010-01-01

    To use progress testing, a large bank of questions is required, particularly when planning to deliver tests over a long period of time. The questions need not only to be of good quality but also balanced in subject coverage across the curriculum to allow appropriate sampling. Hence as well as creating its own questions, an institution could share questions. Both methods allow ownership and structuring of the test appropriate to the educational requirements of the institution. Peninsula Medical School (PMS) has developed a mechanism to validate questions written in house. That mechanism can be adapted to utilise questions from an International question bank International Digital Electronic Access Library (IDEAL) and another UK-based question bank Universities Medical Assessment Partnership (UMAP). These questions have been used in our progress tests and analysed for relative performance. Data are presented to show that questions from differing sources can have comparable performance in a progress testing format. There are difficulties in transferring questions from one institution to another. These include problems of curricula and cultural differences. Whilst many of these difficulties exist, our experience suggests that it only requires a relatively small amount of work to adapt questions from external question banks for effective use. The longitudinal aspect of progress testing (albeit summatively) may allow more flexibility in question usage than single high stakes exams.

  9. France's answers to question and comments received from other contracting parties on its 1. report for the JC

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-10-01

    The Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management is supplementing the Convention on Nuclear Safety. It was approved by France on February 22, 2000 and it entered into force on June 18, 2001. France has received 211 questions, coming from 19 Contracting Parties, on its first report and has provided written answers to each one. These answers were gathered in a single document, which lists them along the articles of the Convention. France has presented these answers on November 5, 2003, at the review meeting of the contracting Parties of the Convention and has decided to make them available to the public, however without mention of the countries that had asked them. The 211 questions received on the first report for the Joint Convention are listed along the sections suggested by the guidelines for the answers to the articles of the convention, sorted by the related page number of the French report and, within each section, grouped by issues raised. The written answers to each question have been coordinated by the French Nuclear Safety Authority (ASN), but have been provided either by the regulators or by the operators (or even both) depending on the related issue. In the case where various questions are related to a same issue but are referred to different articles of the Conventions, they have been referred to the most relevant article in order to have the same issue dealt with in a single location in the present answers report. The answer to each question is provided immediately under the related question.

  10. Food safety: correct information for pregnant women

    Directory of Open Access Journals (Sweden)

    Bartolomeo Griglio

    2013-04-01

    Full Text Available This study was aimed at investigating the knowledge of pregnant women on food safety with particular attention to the effectiveness of the informative material (pamphlet and poster prepared in a previous study. To this scope, a questionnaire composed by 8 questions (Likert scaled was used except for one which was a Y/N question. Themes of the questionnaire were: level of concerns on food safety, and knowledge on foodborne diseases (salomonellosis, toxoplasmosis and listeriosis, risk factors and preventive measures. Results indicate that knowledge increased in respect to that of the previous study, but in relation to informative material previously distributed.

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

    International Nuclear Information System (INIS)

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

    2012-01-01

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

  12. Assessing flight safety differences between the United States regional and major airlines

    Science.gov (United States)

    Sharp, Broderick H.

    During 2008, the U.S. domestic airline departures exceeded 28,000 flights per day. Thirty-nine or less than 0.2 of 1% of these flights resulted in operational incidents or accidents. However, even a low percentage of airline accidents and incidents continue to cause human suffering and property loss. The charge of this study was the comparison of U.S. major and regional airline safety histories. The study spans safety events from January 1982 through December 2008. In this quantitative analysis, domestic major and regional airlines were statistically tested for their flight safety differences. Four major airlines and thirty-seven regional airlines qualified for the safety study which compared the airline groups' fatal accidents, incidents, non-fatal accidents, pilot errors, and the remaining six safety event probable cause types. The six other probable cause types are mechanical failure, weather, air traffic control, maintenance, other, and unknown causes. The National Transportation Safety Board investigated each airline safety event, and assigned a probable cause to each event. A sample of 500 events was randomly selected from the 1,391 airlines' accident and incident population. The airline groups' safety event probabilities were estimated using the least squares linear regression. A probability significance level of 5% was chosen to conclude the appropriate research question hypothesis. The airline fatal accidents and incidents probability levels were 1.2% and 0.05% respectively. These two research questions did not reach the 5% significance level threshold. Therefore, the airline groups' fatal accidents and non-destructive incidents probabilities favored the airline groups' safety differences hypothesis. The linear progression estimates for the remaining three research questions were 71.5% for non-fatal accidents, 21.8% for the pilot errors, and 7.4% significance level for the six probable causes. These research questions' linear regressions are greater than

  13. Putting Safety in the Frame

    Directory of Open Access Journals (Sweden)

    Valerie Jean O’Keeffe

    2015-06-01

    Full Text Available Current patient safety policy focuses nursing on patient care goals, often overriding nurses’ safety. Without understanding how nurses construct work health and safety (WHS, patient and nurse safety cannot be reconciled. Using ethnography, we examine social contexts of safety, studying 72 nurses across five Australian hospitals making decisions during patient encounters. In enacting safe practice, nurses used “frames” built from their contextual experiences to guide their behavior. Frames are produced by nurses, and they structure how nurses make sense of their work. Using thematic analysis, we identify four frames that inform nurses’ decisions about WHS: (a communicating builds knowledge, (b experiencing situations guides decisions, (c adapting procedures streamlines work, and (d team working promotes safe working. Nurses’ frames question current policy and practice by challenging how nurses’ safety is positioned relative to patient safety. Recognizing these frames can assist the design and implementation of effective WHS management.

  14. Questions about hygiene and work safety in operation of lasers

    Energy Technology Data Exchange (ETDEWEB)

    Kashuba, V A; Semenov, A M

    1976-08-01

    Lasers have found very wide use in science and technology. The USSR now uses several laser type instruments. Korund has tremendously accelerated output in a watch factory (jewel-drilling), freed hundreds of sq. meter space, and lowered personnel numbers by 470 workers (a photo is presented of an automated Korund-laser watch production section). Research by the F. F. Erisman Scientific Research Institute of Hygiene, in Moscow, demonstrated the positive effect of laser introduction in plants. The familiar hazards of use are noted, as are attending dangers from ir and uv, noise, and aerosols. Safety measures must include isolation of instruments shielding and protective goggles; hygienic, physiological, and ergonomic requirements of laser units must be met. Medical control of workers is said to be more intensive than in the USA.

  15. Safety Bulletin 2014-1

    CERN Multimedia

    HSE Unit

    2014-01-01

    The HSE Unit would like to inform you that Safety Bulletin 2014-1 entitled “Call for help!” has just been released.   The Bulletin is available on EDMS under the following number: 1346313. We would like to remind you that HSE Safety Bulletins are published in English and French, and incorporate feedback from incidents/near misses/accidents that have occurred on the CERN site with the aim of improving prevention. We remain at your disposal in case you have further questions.

  16. 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.

  17. When is a research question not a research question?

    Science.gov (United States)

    Mayo, Nancy E; Asano, Miho; Barbic, Skye Pamela

    2013-06-01

    Research is undertaken to answer important questions yet often the question is poorly expressed and lacks information on the population, the exposure or intervention, the comparison, and the outcome. An optimal research question sets out what the investigator wants to know, not what the investigator might do, nor what the results of the study might ultimately contribute. The purpose of this paper is to estimate the extent to which rehabilitation scientists optimally define their research questions. A cross-sectional survey of the rehabilitation research articles published during 2008. Two raters independently rated each question according to pre-specified criteria; a third rater adjudicated all discrepant ratings. The proportion of the 258 articles with a question formulated as methods or expected contribution and not as what knowledge was being sought was 65%; 30% of questions required reworking. The designs which most often had poorly formulated research questions were randomized trials, cross-sectional and measurement studies. Formulating the research question is not purely a semantic concern. When the question is poorly formulated, the design, analysis, sample size calculations, and presentation of results may not be optimal. The gap between research and clinical practice could be bridged by a clear, complete, and informative research question.

  18. Electric Power Lines : Questions and Answers on Research into Health Effects.

    Energy Technology Data Exchange (ETDEWEB)

    United States. Bonneville Power Administration.

    1995-06-01

    Most people know that electric power lines, like the wiring in our homes, can cause serious electric shocks if we`re not careful. Many people also want to know whether the EMF (electric and magnetic fields) produced by power lines and other electrical devices affect our health. Although no adverse health effects of electric power EMF have been confirmed, there is continued scientific uncertainty about this issue. Research on EMF is ongoing throughout the world. The purpose of this booklet is to answer some common questions that the BPA (Bonneville Power Administration) receives about the possible effects of power lines on health. First, some basic electrical terms are defined, and electric and magnetic fields are debed. Next, answers are given to several questions about recent scientific studies. Some important information about electrical safety follows. We then describe how BPA is addressing public concerns about potential health effects of power lines. The last section tells you how to obtain more detailed information about the health and safety issues summarized in this booklet.

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

    Science.gov (United States)

    Hill, Janice; Victor, Daniel

    2008-01-01

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

  20. Flu Vaccine Safety and Pregnancy

    Science.gov (United States)

    ... Influenza Types Seasonal Avian Swine Variant Pandemic Other Flu Vaccine Safety and Pregnancy Questions & Answers Language: English ( ... flu vaccine? Why should pregnant women get a flu shot? Flu is more likely to cause severe ...

  1. Basis Document for Sludge Stabilization

    CERN Document Server

    Risenmay, H R

    2001-01-01

    DOE-RL recently issued Safety Evaluation Report (SER) amendments to the PFP Final Safety Analysis Report, HNF-SD-CP-SAR-021 Rev. 2. The Justification for Continued Operations for 2736-ZB and plutonium oxides in BTCs Safety Basis change (letter DOE-RL ABD-074) was approved by one of the SERs. Also approved by SER was the revised accident analysis for Magnesium Hydroxide Precipitation Process (MHPP) gloveboxes HC-230C-3 and HC-230C-5 containing increased glovebox inventories and corresponding increases in seismic release consequence. Numerous implementing documents require revision and issuance to implement the SER approvals. The SER plutonium oxides into BTCs specifically limited the SER scope to ''pure or clean oxides, i.e., 85 wt% or grater Pu, in this feed change'' (SER Section 3.0 Base Information paragraph 4 [page 11]). Comprehensive USQ Evaluation PFP-2001-12 addressed the packaging of Pu alloy metals into BTCs, and the packaging of Pu alloy oxides (powders) into food pack cans and determined that the ac...

  2. The Morality and Economics of Safety in Defence Procurement

    Science.gov (United States)

    Clement, Tim

    Ministry of Defence policy is to conform as closely as possible to UK health and safety legislation in all its operations. We consider the implications of the law and the guidance provided by the Health and Safety Executive for the arguments we need to make for the safety of defence procurements, and extract four general principles to help in answering the questions that arise when considering the safety of systems with complex behaviour. One of these principles is analysed further to identify how case law and the guidance interpret the requirement for risks to be reduced so far as is reasonably practicable. We then apply the principles to answer some questions that have arisen in our work as Independent Safety Auditors, including the limits to the tolerability of risk to armed forces personnel and civilians in wartime, and the acceptability of the transfer of risk from one group to another when controls on risk are introduced.

  3. Questions and Questioning Techniques: A View of Indonesian Students’ Preferences

    Directory of Open Access Journals (Sweden)

    Debora Tri Ragawanti

    2009-01-01

    Full Text Available This study investigated students’ preference on teacher’s questions and questionings techniques and more importantly on how they could facilitate or impede their learning. The results on teacher’s questioning techniques showed that random nomination was more preferred than pre-arranged format nomination. In addition, techniques of nominating volunteering students and of giving wait-time were disliked by most student-respondents. As for types of question, the yes/no question was favored by most of the respondents. Different from the yes/no question, the number of respondents leaning forward to the analysis question, questions about fact of life, and questions to state opinion did not show a significant difference from the number of those leaning against the same questions.

  4. Efficacy and safety of histamine-2 receptor antagonists

    NARCIS (Netherlands)

    van der Pol, Rachel; Langendam, Miranda; Benninga, Marc; van Wijk, Michiel; Tabbers, Merit

    2014-01-01

    Histamine-2 receptor antagonists (H2RAs) are frequently used in the treatment of gastroesophageal reflux disease (GERD) in children; however, their efficacy and safety is questionable. To systematically review the literature to assess the efficacy and safety of H2RAs in pediatric GERD. PubMed,

  5. Synergy in the areas of NPP nuclear safety and nuclear security

    International Nuclear Information System (INIS)

    Dybach, A.M.; Kuzmyak, I.Ya.; Kukhotskij, A.V.

    2013-01-01

    The paper considers the question of synergy between nuclear safety and nuclear security. Special attention is paid to identifying interface of the two areas of safety and definition of common principles for nuclear security and nuclear safety measures. The principles of defense in depth, safety culture and graded approach are analyzed in detail.Specific features characteristic of nuclear safety and security are outlined

  6. Hazard Analysis Database Report

    Energy Technology Data Exchange (ETDEWEB)

    GAULT, G.W.

    1999-10-13

    The Hazard Analysis Database was developed in conjunction with the hazard analysis activities conducted in accordance with DOE-STD-3009-94, Preparation Guide for US Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports, for the Tank Waste Remediation System (TWRS) Final Safety Analysis Report (FSAR). The FSAR is part of the approved TWRS Authorization Basis (AB). This document describes, identifies, and defines the contents and structure of the TWRS FSAR Hazard Analysis Database and documents the configuration control changes made to the database. The TWRS Hazard Analysis Database contains the collection of information generated during the initial hazard evaluations and the subsequent hazard and accident analysis activities. The database supports the preparation of Chapters 3,4, and 5 of the TWRS FSAR and the USQ process and consists of two major, interrelated data sets: (1) Hazard Evaluation Database--Data from the results of the hazard evaluations; and (2) Hazard Topography Database--Data from the system familiarization and hazard identification.

  7. Permanent Commission for Health and Safety

    CERN Multimedia

    Association du personnel

    2007-01-01

    The mandate of the Staff Association's permanent commission for Health and Safety is to examine all aspects of health and safety related to the working environment at CERN. In no way does it wish to be a substitute for the official bodies that are responsible for these matters. The Commission's aim is to formulate remarks on and make proposals about these questions to the relevant bodies and the CERN Management. Its main focus is the safety of the CERN staff but it is also concerned with the safety of the installations and of the CERN environment. The Commission reports to the Staff Council and the Executive Committee of the Staff Association.

  8. A 2-year study of patient safety competency assessment in 29 clinical laboratories.

    Science.gov (United States)

    Reed, Robyn C; Kim, Sara; Farquharson, Kara; Astion, Michael L

    2008-06-01

    Competency assessment is critical for laboratory operations and is mandated by the Clinical Laboratory Improvement Amendments of 1988. However, no previous reports describe methods for assessing competency in patient safety. We developed and implemented a Web-based tool to assess performance of 875 laboratory staff from 29 laboratories in patient safety. Question categories included workplace culture, categorizing error, prioritization of patient safety interventions, strength of specific interventions, and general patient safety concepts. The mean score was 85.0%, with individual scores ranging from 56% to 100% and scores by category from 81.3% to 88.6%. Of the most difficult questions (laboratory technologists. Computer-based competency assessments help laboratories identify topics for continuing education in patient safety.

  9. Question popularity analysis and prediction in community question answering services.

    Science.gov (United States)

    Liu, Ting; Zhang, Wei-Nan; Cao, Liujuan; Zhang, Yu

    2014-01-01

    With the blooming of online social media applications, Community Question Answering (CQA) services have become one of the most important online resources for information and knowledge seekers. A large number of high quality question and answer pairs have been accumulated, which allow users to not only share their knowledge with others, but also interact with each other. Accordingly, volumes of efforts have been taken to explore the questions and answers retrieval in CQA services so as to help users to finding the similar questions or the right answers. However, to our knowledge, less attention has been paid so far to question popularity in CQA. Question popularity can reflect the attention and interest of users. Hence, predicting question popularity can better capture the users' interest so as to improve the users' experience. Meanwhile, it can also promote the development of the community. In this paper, we investigate the problem of predicting question popularity in CQA. We first explore the factors that have impact on question popularity by employing statistical analysis. We then propose a supervised machine learning approach to model these factors for question popularity prediction. The experimental results show that our proposed approach can effectively distinguish the popular questions from unpopular ones in the Yahoo! Answers question and answer repository.

  10. The scientific truth about nuclear energy (in 10 questions); La verite scientifique sur le nucleaire (en 10 questions)

    Energy Technology Data Exchange (ETDEWEB)

    Bourry, Chantal

    2012-03-22

    In ten questions and as many chapters, this pedagogical book allows the reader to make himself a precise idea of the scientific reality of the nuclear energy development. Far away from sterile debates and policy positions, it offers to the non-specialist the possibility: to better comprehend a complex physical phenomenon, to estimate its health impacts and risks, to identify the institutional actors of the French nuclear industry, to make an appreciation about the safety of facilities, to estimate the expenses generated by the development of this energy source and by its possible abandonment, and finally, to examine the conditions of a nuclear phasing out. (J.S.)

  11. Robustness Analysis of Visual Question Answering Models by Basic Questions

    KAUST Repository

    Huang, Jia-Hong

    2017-11-01

    Visual Question Answering (VQA) models should have both high robustness and accuracy. Unfortunately, most of the current VQA research only focuses on accuracy because there is a lack of proper methods to measure the robustness of VQA models. There are two main modules in our algorithm. Given a natural language question about an image, the first module takes the question as input and then outputs the ranked basic questions, with similarity scores, of the main given question. The second module takes the main question, image and these basic questions as input and then outputs the text-based answer of the main question about the given image. We claim that a robust VQA model is one, whose performance is not changed much when related basic questions as also made available to it as input. We formulate the basic questions generation problem as a LASSO optimization, and also propose a large scale Basic Question Dataset (BQD) and Rscore (novel robustness measure), for analyzing the robustness of VQA models. We hope our BQD will be used as a benchmark for to evaluate the robustness of VQA models, so as to help the community build more robust and accurate VQA models.

  12. Robustness Analysis of Visual Question Answering Models by Basic Questions

    KAUST Repository

    Huang, Jia-Hong

    2017-01-01

    Visual Question Answering (VQA) models should have both high robustness and accuracy. Unfortunately, most of the current VQA research only focuses on accuracy because there is a lack of proper methods to measure the robustness of VQA models. There are two main modules in our algorithm. Given a natural language question about an image, the first module takes the question as input and then outputs the ranked basic questions, with similarity scores, of the main given question. The second module takes the main question, image and these basic questions as input and then outputs the text-based answer of the main question about the given image. We claim that a robust VQA model is one, whose performance is not changed much when related basic questions as also made available to it as input. We formulate the basic questions generation problem as a LASSO optimization, and also propose a large scale Basic Question Dataset (BQD) and Rscore (novel robustness measure), for analyzing the robustness of VQA models. We hope our BQD will be used as a benchmark for to evaluate the robustness of VQA models, so as to help the community build more robust and accurate VQA models.

  13. Two-Year-Old Children Differentiate Test Questions from Genuine Questions

    Science.gov (United States)

    Grosse, Gerlind; Tomasello, Michael

    2012-01-01

    Children are frequently confronted with so-called "test questions". While genuine questions are requests for missing information, test questions ask for information obviously already known to the questioner. In this study we explored whether two-year-old children respond differentially to one and the same question used as either a genuine question…

  14. Work safety and sustainable development in enterprise

    Institute of Scientific and Technical Information of China (English)

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

    2005-01-01

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

  15. Nuclear questions; Le nucleaire en questions

    Energy Technology Data Exchange (ETDEWEB)

    Berg, Eugene

    2012-02-15

    Civilian and military nuclear questions fill a multitude of publications these days, especially after the Japanese tsunami and the Fukushima disaster. The author analyses some of them and highlights the links between civil and military nuclear industries, the realities of the nuclear cycle and related industrial questions before concluding on the controversial issue of weapons and their proliferation potential

  16. Does competition influence safety?

    International Nuclear Information System (INIS)

    Pamme, H.

    2000-01-01

    Competition in the deregulated electricity market does not leave nuclear power plants unaffected. Operators seek to run their plants at maximum availability and with optimized cost structures so that specific generating costs are minimized. The 'costs of safety', with their fixed-cost character, are elements of this cost structure. Hence the question whether safety is going to suffer under the cost pressure on the market. The study shows that the process of economic optimization does not permit cost minimization for its own sake in the area of operating costs which can be influenced by management or are 'avoidable'. The basis of assessment rather must be potential risks which could entail losses of availability. Prophylactic investments made in order to avoid losses of availability to a large extent also imply unchanged or even higher levels of safety. Economic viability and safety thus are closely correlated. Competition in a deregulated marekt so far has not done any direct harm to plant safety. An even more efficient use of scarce funds and, hopefully, a tolerable political environment should allow the safety level of nuclear power plants to be upheld, and safety culture to be maintained, also in the future. (orig.) [de

  17. Innovative Patient Safety Curriculum Using iPAD Game (PASSED) Improved Patient Safety Concepts in Undergraduate Medical Students.

    Science.gov (United States)

    Kow, A W C; Ang, B L S; Chong, C S; Tan, W B; Menon, K R

    2016-11-01

    While healthcare outcomes have improved significantly, the complex management of diseases in the hospitals has also escalated the risks in patient safety. Therefore, in the process of training medical students to be proficient in medical knowledge and skills, the importance of patient safety cannot be neglected. A new innovation using mobile apps gaming system (PAtient Safety in Surgical EDucation-PASSED) to teach medical students on patient safety was created. Students were taught concepts of patient safety followed by a gaming session using iPad games created by us. This study aims to evaluate the outcome of patient safety perception using the PASSED games created. An interactive iPad game focusing on patient safety issues was created by the undergraduate education team in the Department of Surgery, Yong Loo Lin School of Medicine at the National University of Singapore. The game employed the unique touched-screen feature with clinical scenarios extracted from the hospital sentinel events. Some of the questions were time sensitive, with extra bonus marks awarded if the student provided the correct answer within 10 s. Students could reattempt the questions if the initial answer was wrong. However, this entailed demerit points. Third-year medical students posted to the Department of Surgery experienced this gaming system in a cohort of 55-60 students. Baseline understanding of the students on patient safety was evaluated using Attitudes to Patient Safety Questionnaire III (APSQ-III) prior to the game. A 20 min talk on concept of patient safety using the WHO Patient Safety Guidelines was conducted. Following this, students downloaded the apps from ITune store and played with the game for 20-30 min. The session ended with the students completing the postintervention questionnaire. A total of 221 3rd year medical students responded to the survey during the PASSED session. Majority of the students felt that the PASSED game had trained them to understand the

  18. Safety technology comments on Cattenom nuclear power station

    International Nuclear Information System (INIS)

    1986-01-01

    The comments are based on the safety report for the identical Flamanville plant, on the contract documents for the DUP and on results of consultancy by the DFK Working Party and on replies from the French side in the context of a German list of questions. The comments refer to the state in spring 1982. According to the agreement made for the catalogue of questions Cattenom/KKP 2, the 1300 MW Philippsburg II nuclear power station is used as a German comparable plant in these comments. Reference is made to the German comparable plant in the description and assessment of important parts of the plant. The main points of the safety technology comments are in the assessment of site characteristics; the safety technology concept; the derivation of radio-active materials and the radiation exposure in the adjacent German area. (orig./HP) [de

  19. Preliminary study to questions relating to the safety of nuclear power plants A and B at Biblis

    International Nuclear Information System (INIS)

    Fischer, B.; Hahn, L.; Rausch, L.

    1985-01-01

    With a view to developing suitable tools for the safety evaluation of reactors A and B at Biblis, the publication compiles all aspects relevant to safety, creates an evaluation frame, and evaluates the aspects relevant to safety by means of this frame of evaluation. According to the composition of the work, the overall subject is split up into the complexes information, acquisition, evaluation of operational experience, probabilistic analyses, comparison with newer PWR type reactors, fulfilling of injunctions, modifications due to disposal problems, and the disposal situation. (DG) [de

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

    Science.gov (United States)

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

    2014-01-01

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

  1. Investigation of status of safety management in radiation handle works

    International Nuclear Information System (INIS)

    Amauchi, Hiroshi; Nishimura, Kenji; Izumi, Kokichi

    2007-01-01

    This report describes the investigation in the title concerning the system for safety management and for accident prevention, which was done by a questionnaire in a period of 1.5 months in 2005. The questionnaire including 55 questions for safety management system, 33 for instruments and safety utilization of radiation and 57 for present status of safety management in high-risk radiation works, was performed in 780 hospitals, of which 313 answered. The first 55 questions concerned with the facility, patient identification, information exchange, management of private information, safety management activities, measures to prevent accident, manual preparation, personnel education and safety awareness; the second, with management of instruments, package insert, system for reporting the safety information, management of implants, re-imaging and radiation protection; and the third, with the systems for patients' emergency, in departments of CT/MR, of IVR, of nuclear diagnosis and of radiation therapy. Based on the results obtained, many problems, tasks and advices are presented to various items and further continuation of efforts to improve the present status is mentioned to be necessary. Details are given in the homepage of the Japanese Society of Radiological Technology. (T.I.)

  2. Opinion of the Scientific Panel on Genetically Modified Organisms on a question from the Commission related to the Austrian notification of national legislation governing GMOs under article 95(5) of the Treaty

    DEFF Research Database (Denmark)

    Andersson, H. C.; Bartsch, D.; Buhk, H.-J.

    2003-01-01

    Opinion adopted on 4 July 2003 (Question No EFSA-Q-2003-001); EFSA=European Food Safety Authority......Opinion adopted on 4 July 2003 (Question No EFSA-Q-2003-001); EFSA=European Food Safety Authority...

  3. 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

  4. Answers to questions about updated estimates of occupational radiation doses at Three Mile Island, Unit 2

    International Nuclear Information System (INIS)

    1983-12-01

    The purpose of this question and answer report is to provide a clear, easy-to-understand explanation of revised radiation dose estimates which workers are likely to receive over the course of the cleanup at Three Mile Island, Unit 2, and of the possible health consequences to workers of these new estimates. We will focus primarily on occupational dose, although pertinent questions about public health and safety will also be answered

  5. Factors influencing a nurse's decision to question medication administration in a neonatal clinical care unit.

    Science.gov (United States)

    Aydon, Laurene; Hauck, Yvonne; Zimmer, Margo; Murdoch, Jamee

    2016-09-01

    The aim of this study was to identify factors that influence nurse's decisions to question concerning aspects of medication administration within the context of a neonatal clinical care unit. Medication error in the neonatal setting can be high with this particularly vulnerable population. As the care giver responsible for medication administration, nurses are deemed accountable for most errors. However, they are recognised as the forefront of prevention. Minimal evidence is available around reasoning, decision making and questioning around medication administration. Therefore, this study focuses upon addressing the gap in knowledge around what nurses believe influences their decision to question. A critical incident design was employed where nurses were asked to describe clinical incidents around their decision to question a medication issue. Nurses were recruited from a neonatal clinical care unit and participated in an individual digitally recorded interview. One hundred and three nurses participated between December 2013-August 2014. Use of the constant comparative method revealed commonalities within transcripts. Thirty-six categories were grouped into three major themes: 'Working environment', 'Doing the right thing' and 'Knowledge about medications'. Findings highlight factors that influence nurses' decision to question issues around medication administration. Nurses feel it is their responsibility to do the right thing and speak up for their vulnerable patients to enhance patient safety. Negative dimensions within the themes will inform planning of educational strategies to improve patient safety, whereas positive dimensions must be reinforced within the multidisciplinary team. The working environment must support nurses to question and ultimately provide safe patient care. Clear and up to date policies, formal and informal education, role modelling by senior nurses, effective use of communication skills and a team approach can facilitate nurses to

  6. Food safety and ethics

    DEFF Research Database (Denmark)

    Jensen, Karsten Klint; Sandøe, Peter

    2002-01-01

    The general public in Europe seems to have lost its confidence in food safety. The remedy for this, as proposed by the Commission of the EU, is a scientific rearmament. The question, however, is whether more science will be able to overturn the public distrust. Present experience seems to suggest...

  7. The controversy over food irradiation ''open questions'' and reliable answers

    International Nuclear Information System (INIS)

    Diehl, J.F.

    1992-01-01

    During the 1950s and 60s, when ''going nuclear'' was the thing, research and development in the area of food irradiation was generously supported by governments, and was reported by the media with a very positive attitude. In the wake of the antinuclear movement that swept many countries in the 70s and 80s, food irradiation generally had a bad press and governmental support for R and D in this area was reduced more and more. In the meantime, the new technology has become a commerical reality in countries like Belgium, France and the Netherlands. In other countries, Germany for instance, the frightening claims of the opponents that irradiated foods are bad for health and nutritionally worthless - have been gradually replaced by the view: ''There are still too many open questions. A moratorium on food irradiation must be proclaimed until all the questions have been answered''. A situation where no more questions can be asked, will never be reached. However, reliable answers can be given to the important questions concerning nutritional and health quality of irradiated food, and environmental safety, technical efficacy, and economic feasibility of the process. The question that is stipp open, at least in some countries, is to what extent consumers, confused by conflicting claims of opponents and proponents and often misinformed about the difference between radiation and radioactivity, will buy foods labelled ''irradiated''. (orig.) [de

  8. The European atomic politics under the treaty of Lisboa and actual questions of the export of nuclear waste

    International Nuclear Information System (INIS)

    Ehlenz, Christian; Frenz, Walter

    2011-01-01

    In the context of the actual discussion considerably influenced by safety questions activated by the reactor accident in Tschernobyl in 1986, the EAG gains increasing significance. However, a substantial safety risk proceeds not only with nuclear power stations as a possible goal for attacks of terror, but also from the uncontrolled spreading with nuclear material. The latter equally affects the question on handling radioactive waste materials being straightly discussed in Germany as well as in the European Union as proven by the European Union commissioner Oettinger. This is to be considered in connection with the problem how extensively the competences of the Euratom for the nuclear safety may be interpreted. The actual changes of the legal situation by means of the Lisboa contract for the EAG altogether turned out marginally and let its demand for a reform based on the actual conditions appear more urgent.

  9. Can multiple-choice questions simulate free-response questions?

    OpenAIRE

    Lin, Shih-Yin; Singh, Chandralekha

    2016-01-01

    We discuss a study to evaluate the extent to which free-response questions could be approximated by multiple-choice equivalents. Two carefully designed research-based multiple-choice questions were transformed into a free-response format and administered on the final exam in a calculus-based introductory physics course. The original multiple-choice questions were administered in another similar introductory physics course on final exam. Findings suggest that carefully designed multiple-choice...

  10. Answers to frequently asked questions about cleanup activities at Three Mile Island, Unit 2

    International Nuclear Information System (INIS)

    1984-03-01

    This question-and-answer report provides answers in nontechnical language to frequently asked questions about the status of cleanup activities at Three Mile Island, Unit 2. The answers update information first prepared in 1981, shortly after the cleanup got under way. Since then, a variety of important developments in the cleanup has occurred. The information in the report should be read in conjunction with NUREG 1060, a discussion of increased occupational exposure estimates for the cleanup. The questions and answers in this report cover purpose and community involvement, decontamination of water and reactor, fuel removal, radwaste transport, environmental impact, social and economic effects, worker exposures and safety, radiation monitoring, potential for accidents, and schedule and funding

  11. Four Questions

    Science.gov (United States)

    Hark-Weber, Amara G., Ed.

    2013-01-01

    The author is pleased to introduce a new section in "TAJ," Four Questions. The structure is simple: four questions are asked to teaching artists working in various media and locations. The questions are always the same, but because each teaching artist's approach is unique, their answers will provide an insight into particular methodologies that…

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

    Science.gov (United States)

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

    2013-01-01

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

  13. Questions regarding the safety and duration of immunity following live yellow fever vaccination.

    Science.gov (United States)

    Amanna, Ian J; Slifka, Mark K

    2016-12-01

    The World Health Organization (WHO) and other health agencies have concluded that yellow fever booster vaccination is unnecessary since a single dose of vaccine confers lifelong immunity. Areas covered: We reviewed the clinical studies cited by health authorities in their investigation of both the safety profile and duration of immunity for the YFV-17D vaccine and examined the position that booster vaccination is no longer needed. We found that antiviral immunity may be lost in 1-in-3 to 1-in-5 individuals within 5 to 10 years after a single vaccination and that children may be at greater risk for primary vaccine failure. The safety profile of YFV-17D was compared to other licensed vaccines including oral polio vaccine (OPV) and the rotavirus vaccine, RotaShield, which have subsequently been withdrawn from the US and world market, respectively. Expert commentary: Based on these results and recent epidemiological data on vaccine failures (particularly evident at >10 years after vaccination), we believe that current recommendations to no longer administer YFV-17D booster vaccination be carefully re-evaluated, and that further development of safer vaccine approaches should be considered.

  14. Questions regarding the safety and duration of immunity following live yellow fever vaccination

    Science.gov (United States)

    Amanna, Ian J.; Slifka, Mark K.

    2016-01-01

    Introduction The World Health Organization (WHO) and other health agencies have concluded that yellow fever booster vaccination is unnecessary since a single dose of vaccine confers lifelong immunity. Areas Covered We reviewed the clinical studies cited by health authorities in their investigation of both the safety profile and duration of immunity for the YFV-17D vaccine and examined the position that booster vaccination is no longer needed. We found that antiviral immunity may be lost in 1-in-3 to 1-in-5 individuals within 5 to 10 years after a single vaccination and that children may be at greater risk for primary vaccine failure. The safety profile of YFV-17D was compared to other licensed vaccines including oral polio vaccine (OPV) and the rotavirus vaccine, RotaShield, which have subsequently been withdrawn from the US and world market, respectively. Expert Commentary Based on these results and recent epidemiological data on vaccine failures (particularly evident at >10 years after vaccination), we believe that current recommendations to no longer administer YFV-17D booster vaccination be carefully re-evaluated, and that further development of safer vaccine approaches should be considered. PMID:27267203

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

    International Nuclear Information System (INIS)

    Lhomme, Veronique; Daubard, Jean-Paul

    2013-01-01

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

  16. Actual questions in Slovak and European nuclear sector

    International Nuclear Information System (INIS)

    Slugen, V.

    2010-01-01

    The close cohesion of research and education underlines the development of all research areas and contributes to their sustainability. In the paper, new approaches of European Commission (DG RTD Energy) to nuclear power engineering development (focused on area fission and reactor systems) and applications also for Slovak conditions are discussed in details. Research, education and training increase not only economical factor and technical development, but imply the higher level of safety culture by design or operation of nuclear installations. The paper will be focused on the actual questions in frame of Slovak as well as European nuclear sector.

  17. A road safety information system : from concept to implementation. Contribution to the Road Safety Training Course of the World Bank, 1 May 2001, Washington, D.C.

    OpenAIRE

    Wegman, F.C.M.

    2001-01-01

    It is a proven fact that road safety problems are not unsolvable: what is man-made can also be unmade by man. This leads to questions such as which priorities to set, which measures to take, which effects to expect, what costs are involved, and how these can be financed. In order to be able to answer all these questions, data, knowledge, and information are needed to give a comprehensive and objective picture of the road safety problems and of the effectiveness and efficiency of potential roa...

  18. Drivers 55 Plus: Test Your Own Performance. A Self-Rating Form of Questions, Facts and Suggestions for Safe Driving.

    Science.gov (United States)

    Malfetti, James L.; Winter, Darlene J.

    This booklet contains a 15-question rating form that provides some guidance to older drivers in beginning to assess their driving skills. The pages following the self-rating form discuss the various questions on the form. After a general introduction, the discussion is divided into five areas that traffic safety authorities have judged critical to…

  19. The EU Offshore Safety Directive and its potential effects. Opportunity or handicap?; Die EU Offshore Safety Directive und ihre moeglichen Auswirkungen. Chance oder Handicap?

    Energy Technology Data Exchange (ETDEWEB)

    Schwiederowski, Claudia [RWE Dea AG, Hamburg (Germany)

    2014-07-01

    The purpose of the EU Offshore Safety Directive, which took effect on 18 July 2013, is to define minimum requirements for the prevention of severe accidents in connection with offshore crude oil or natural gas activities of any kind and the containment of the follow-on effects of such accidents. This is without question a logical consequence of the offshore incidents seen around the globe over the past decades. An interesting question in this context is for whom the EU Offshore Safety Directive has become an opportunity and for whom a handicap. [German] Ziel der am 18. Juli 2013 in Kraft getretenen EU Offshore Safety Direktive ist die Festlegung von Mindestanforderungen fuer die Verhinderung schwerer Unfaelle bei Offshore-Erdoel- bzw. - Erdgasaktivitaeten und die Begrenzung etwaiger Unfallfolgen. Nach den weltweiten Offshore- Ereignissen der vergangenen Jahrzehnte ist dies ohne Zweifel eine logische Entwicklung. Nun stellt sich die Frage: Fuer wen entwickelt sich die EU Offshore Safety Directive zur Chance, fuer wen zum Handicap?.

  20. Safety goals for nuclear power

    International Nuclear Information System (INIS)

    Fischhoff, B.

    1984-02-01

    The key policy question in managing hazardous technologies is often some variant of How safe is safe enough. The US Nuclear Regulatory Commission has recently broached this topic by adopting safety goals defining acceptable risk levels for nuclear power plants. These goals are analyzed here with a general theory of standard setting (Fischhoff, 1983) which asks: (1) Are standards an appropriate policy tool in this case. (2) Can the Commission's safety philosophy be defended. (3) Do the operational goals capture that philosophy. The anlaysis shows the safety goals proposal to be sophisticated in some respects, incomplete in others. More generally, it points to difficulties with the concept of acceptable risk and any attempt to build policy instruments around it. Although focused on the NRC's safety goals, the present analysis is a prototype of what can be learned by similarly detailed consideration of other standards, not only for nuclear power but also for other hazardous technologies, as well as for issues unrelated to safety

  1. Phrasal Paraphrase Based Question Reformulation for Archived Question Retrieval.

    Directory of Open Access Journals (Sweden)

    Yu Zhang

    Full Text Available Lexical gap in cQA search, resulted by the variability of languages, has been recognized as an important and widespread phenomenon. To address the problem, this paper presents a question reformulation scheme to enhance the question retrieval model by fully exploring the intelligence of paraphrase in phrase-level. It compensates for the existing paraphrasing research in a suitable granularity, which either falls into fine-grained lexical-level or coarse-grained sentence-level. Given a question in natural language, our scheme first detects the involved key-phrases by jointly integrating the corpus-dependent knowledge and question-aware cues. Next, it automatically extracts the paraphrases for each identified key-phrase utilizing multiple online translation engines, and then selects the most relevant reformulations from a large group of question rewrites, which is formed by full permutation and combination of the generated paraphrases. Extensive evaluations on a real world data set demonstrate that our model is able to characterize the complex questions and achieves promising performance as compared to the state-of-the-art methods.

  2. Gas-cooled breeder reactor safety

    Energy Technology Data Exchange (ETDEWEB)

    Chermanne, J.; Burgsmueller, P. [Societe Belge pour l' Industrie Nucleaire, Brussels

    1981-01-15

    The European Association for the Gas-cooled Breeder Reactor (G B R A), set-up in 1969 prepared between 1972 and 1974 a 1200 MWe Gas-cooled Breeder Reactor (G B R) commercial reference design G B R 4. It was then found necessary that a sound and neutral appraisal of the G B R licenseability be carried out. The Commission of the European Communities (C E C) accepted to sponsor this exercise. At the beginning of 1974, the C E C convened a group of experts to examine on a Community level, the safety documents prepared by the G B R A. A working party was set-up for that purpose. The experts examined a ''Preliminary Safety Working Document'' on which written questions and comments were presented. A ''Supplement'' containing the answers to all the questions plus a detailed fault tree and reliability analysis was then prepared. After a final study of this document and a last series of discussions with G B R A representatives, the experts concluded that on the basis of the evidence presented to the Working Party, no fundamental reasons were identified which would prevent a Gas-cooled Breeder Reactor of the kind proposed by the G B R A achieving a satisfactory safety status. Further work carried out on ultimate accident have confirmed this conclusion. One can therefore claim that the overall safety risk associated with G B R s compares favourably with that of any other reactor system.

  3. Safety of GM crops: compositional analysis.

    Science.gov (United States)

    Brune, Philip D; Culler, Angela Hendrickson; Ridley, William P; Walker, Kate

    2013-09-04

    The compositional analysis of genetically modified (GM) crops has continued to be an important part of the overall evaluation in the safety assessment program for these materials. The variety and complexity of genetically engineered traits and modes of action that will be used in GM crops in the near future, as well as our expanded knowledge of compositional variability and factors that can affect composition, raise questions about compositional analysis and how it should be applied to evaluate the safety of traits. The International Life Sciences Institute (ILSI), a nonprofit foundation whose mission is to provide science that improves public health and well-being by fostering collaboration among experts from academia, government, and industry, convened a workshop in September 2012 to examine these and related questions, and a series of papers has been assembled to describe the outcomes of that meeting.

  4. Minutes of the public hearing concerning questions of environmental protection: nuclear power plant waste management

    International Nuclear Information System (INIS)

    1977-01-01

    Minutes of questions of members of the Bundestag addressed to experts of the pro and con camp, of answers and of written statements on the following central subjects: Concept of waste management; fuel cycle centers; technology of fuel reprocessing plants; safety. (HP) [de

  5. Nuclear power: safety and prospects

    International Nuclear Information System (INIS)

    Miniere, D.

    2012-01-01

    Despite the Fukushima accident new countries are willing to use nuclear power and as a nuclear accident somewhere is a nuclear accident everywhere, all countries are concerned with nuclear safety. A big association that would gather all the national Safety Authorities would be an efficient tool to promote and improve safety at the world scale and may be the unique available tool as no country would let a foreign authority to drive its own nuclear industry. An important lesson from Fukushima and Chernobyl accidents is that the signature of a big nuclear accident is not the number of casualties (it will always be limited) but the importance of the radioactive contamination. The question is how to make this long-term and long-range contamination impossible to happen, it is the mission of nuclear safety. (A.C.)

  6. Safety-Culture Exploration in Taiwan’s Metal Industries: Identifying the Workers’ Background Influence on Safety Climate

    Directory of Open Access Journals (Sweden)

    Shu-Chiang Lin

    2017-10-01

    Full Text Available The present study aims to assess the safety-climate level in Taiwan’s metal industries, as well as to identify the influence of workers’ backgrounds on the safety climate. An earlier report showed that a poor safety culture was related to the cause of accidents in Taiwan’s traditional manufacturing industries. This study surveyed a total of 839 workers who voluntarily participated and completed the safety-culture questionnaires. These workers were from a Taiwanese metal company and its five satellite companies. Three safety-climate factors, namely safety perception, safety communication and safety-management systems, were assessed. Confirmatory factor analysis (CFA was conducted by developing structural equation modeling to ensure the questionnaire’s validity. The influence of workers’ backgrounds on the safety climate was identified by using one-way ANOVA. The reliability result of the questionnaire was above the acceptable level. The overall safety-climate score was 4.22 out of a five-point scale for safety perception, 4.23 for safety-management systems and 3.97 for safety communication. The scores indicate a good level of safety climate, with room for improvement in safety communication. Additionally, the influence of workers’ backgrounds on the safety climate was confirmed. Based on the validity test, it was also found that the questionnaire could be improved by reconstructing its questions in its development process in order to increase the safety-climate model’s reliability and validity, as well as its model fit.

  7. Safety and communication, a winning combination

    CERN Multimedia

    HSE Unit

    2014-01-01

    Since 2013, in line with its mission to support CERN’s proactive communication policy in matters of safety, the HSE unit has been following an annual plan for disseminating information on occupational health and safety and environmental protection.   Safety information designed to underline the importance of prevention is published through a variety of channels: Announcements in the CERN Bulletin, Safety bulletins, notably outlining lessons to be learned in the wake of accidents/incidents occuring at CERN, Safety alerts calling for immediate action, sent by e-mail to the services concerned, Prevention campaigns on the CERN site, Poster campaigns in well frequented public areas. Photo: Christoph Balle. Please heed all prevention messages and apply them in your everyday life. Also, we will be pleased to receive any information or suggestions you may have on safety matters. If you have questions about the HSE unit’s communication activities, please send us an e...

  8. Safety climate and accidents at work

    DEFF Research Database (Denmark)

    Ajslev, Jeppe; Dastjerdi, Efat Lali; Dyreborg, Johnny

    2017-01-01

    Aim: Occupational safety climate is utilized as a way to measure the risk of accidents and injuries at work. This study investigates which factors are associated with safety climate and accidents at work. Methods: In the 2012 round of the Danish Work Environment and Health Study, 15,144 workers...... from the general working population of Denmark replied to questions about safety climate and accidents at work. Mutually adjusted logistic regression analyses determined the association between variables. Results: Within the last year, 5.7% had experienced an accident resulting in sickness absence....... The number of safety climate problems was progressively associated with the odds ratio (OR) for accidents. For one safety climate problem the OR for accidents was 2.01 (95% CI 1.67–2.42), for four or more safety climate problems the OR was 4.57 (95% CI 3.64–5.74). Young workers (18–24 years) had higher odds...

  9. Identifying primary care patient safety research priorities in the UK: a James Lind Alliance Priority Setting Partnership.

    Science.gov (United States)

    Morris, Rebecca Lauren; Stocks, Susan Jill; Alam, Rahul; Taylor, Sian; Rolfe, Carly; Glover, Steven William; Whitcombe, Joanne; Campbell, Stephen M

    2018-02-28

    To identify the top 10 unanswered research questions for primary care patient safety research. A modified nominal group technique. UK. Anyone with experience of primary care including: patients, carers and healthcare professionals. 341 patients and 86 healthcare professionals submitted questions. A top 10, and top 30, future research questions for primary care patient safety. 443 research questions were submitted by 341 patients and 86 healthcare professionals, through a national survey. After checking for relevance and rephrasing, a total of 173 questions were collated into themes. The themes were largely focused on communication, team and system working, interfaces across primary and secondary care, medication, self-management support and technology. The questions were then prioritised through a national survey, the top 30 questions were taken forward to the final prioritisation workshop. The top 10 research questions focused on the most vulnerable in society, holistic whole-person care, safer communication and coordination between care providers, work intensity, continuity of care, suicide risk, complex care at home and confidentiality. This study was the first national prioritisation exercise to identify patient and healthcare professional priorities for primary care patient safety research. The research priorities identified a range of important gaps in the existing evidence to inform everyday practice to address primary care patient safety. © Article author(s) (or their employer(s) unless otherwise stated in the text of the article) 2018. All rights reserved. No commercial use is permitted unless otherwise expressly granted.

  10. 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.

  11. Draft evidence report : traumatic brain injury and commercial motor vehicle driver safety (comprehensive review).

    Science.gov (United States)

    2009-03-30

    Purpose of this evidence report is to address several key questions posed by the Federal Motor Carrier Safety Administration : Key question 1: What is the impact of traumatic brain injury on crash risk/driving performance? Key question 2: What factor...

  12. Martin Marietta Energy Systems Nuclear Criticality Safety Improvement Program

    International Nuclear Information System (INIS)

    Speas, I.G.

    1987-01-01

    This report addresses questions raised by criticality safety violation at several DOE plants. Two charts are included that define the severity and reporting requirements for the six levels of accidents. A summary is given of all reported criticality incident at the DOE plants involved. The report concludes with Martin Marietta's Nuclear Criticality Safety Policy Statement

  13. Draft questions of 5S pre-audit with regard to health and safety standards for tires retreating plant

    Directory of Open Access Journals (Sweden)

    Andrzej Pacana

    2016-12-01

    Full Text Available A continuous technological progress forces an improvement of the production process. The article describes the sole beginning of changes in the process of tires retreading on the 5S management method with regard to health and safety standards. The authors point out that the process of the production of retreaded tires is associated with the relationship between a man and a machine. The process improvement can dispense only by improving the machines but it should also pay attention to the man. The improvement of the production process must precede the audit, which can show areas that require intervention. Any such change in the production process cannot be performed without the participation of health and safety inspector, because his knowledge, skills and competence are able to determine whether the proposed changes interfere with the level of safety at the workplace. The authors emphasize that the process of production improvement production should be compatible with the process of improving the health and safety of workers involved in the production process. The combination of 5S audit with health and safety standards results in a holistic approach to the improvement process.

  14. A novel safety assessment strategy applied to non-selective extracts

    NARCIS (Netherlands)

    Koster, S.; Leeman, W.R.; Verheij, E.R.; Dutman, A.E.; Stee, L.L.P. van; Munch Nielsen, L.; Ronsmans, S.; Noteborn, H.; Krul, L.

    2015-01-01

    A main challenge in food safety research is to demonstrate that processing of foodstuffs does not lead to the formation of substances for which the safety upon consumption might be questioned. This is especially so since food is a complex matrix in which the analytical detection of substances, and

  15. Investigation on regulatory requirements for radiation safety management

    International Nuclear Information System (INIS)

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

    2013-01-01

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

  16. Management of safety culture

    International Nuclear Information System (INIS)

    Kavsek, D.

    2004-01-01

    The strengthening of safety culture in an organization has become an increasingly important issue for nuclear industry. A high level of safety performance is essential for business success in intensely competitive global environment. This presentation offers a discussion of some principles and activities used in enhancing safety performance and appropriate safety behaviour at the Krsko NPP. Over the years a number of events have occurred in nuclear industry that have involved problems in human performance. A review of these and other significant events has identified recurring weaknesses in plant safety culture and policy. Focusing attention on the strengthening of relevant processes can help plants avoid similar undesirable events. The policy of the Krsko NPP is that all employees concerned shall constantly be alert to opportunities to reduce risks to the lowest practicable level and to achieve excellence in plant safety. The most important objective is to protect individuals, society and the environment by establishing and maintaining an effective defense against radiological hazard in the nuclear power plant. It is achieved through the use of reliable structures, components, systems, and procedures, as well as plant personnel committed to a strong safety culture. The elements of safety culture include both organizational and individual aspects. Elements commonly included at the organizational level are senior management commitment to safety, organizational effectiveness, effective communication, organizational learning, and a culture that encourages identification and resolution of safety issues. Elements identified at the individual level include personal accountability, a questioning attitude, communication, procedural adherence, etc.(author)

  17. Safety evaluation status report for the prototype license application safety analysis report

    International Nuclear Information System (INIS)

    1989-07-01

    The US Nuclear Regulatory Commission (NRC) staff and consultants reviewed a Prototype License Application Safety Analysis Report (PLASAR) submitted by the US Department of Energy (DOE) for the earth-mounded concrete bunker (EMCB) alternative method of low-level radioactive waste disposal. The NRC reviewers relied extensively on the Standard Review Plan (SRP), Rev.1 (NUREG-1200), to evaluate the acceptability of the information provided in the EMCB PLASAR. The NRC staff selected certain review areas in the PLASAR for development of safety evaluation report input to provide examples of safety assessments that are necessary as part of a licensing review. Because of the fictitious nature of the assumed disposal site, and the decision to limit the review to essentially first-round review status, the NRC staff report is labeled a ''Safety Evaluation Status Report'' (SESR). Appendix A comprises the NRC review comments and questions on the information that DOE submitted in the PLASAR. The NRC concentrated its review on the design and operations-related portions of the EMCB PLASAR

  18. Aviation safety and maintenance under major organizational changes, investigating non-existing accidents.

    Science.gov (United States)

    Herrera, Ivonne A; Nordskag, Arve O; Myhre, Grete; Halvorsen, Kåre

    2009-11-01

    The objective of this paper is to discuss the following questions: Do concurrent organizational changes have a direct impact on aviation maintenance and safety, if so, how can this be measured? These questions were part of the investigation carried out by the Accident Investigation Board, Norway (AIBN). The AIBN investigated whether Norwegian aviation safety had been affected due to major organizational changes between 2000 and 2004. The main concern was the reduction in safety margins and its consequences. This paper presents a summary of the techniques used and explains how they were applied in three airlines and by two offshore helicopter operators. The paper also discusses the development of safety related indicators in the aviation industry. In addition, there is a summary of the lessons learned and safety recommendations. The Norwegian Ministry of Transport has required all players in the aviation industry to follow up the findings and recommendations of the AIBN study.

  19. Mechanisms of gas retention and release: Experimental results for Hanford waste tanks 241-AW-101 and 241-AN-103

    Energy Technology Data Exchange (ETDEWEB)

    Rassat, S.D.; Gauglitz, P.A.; Bredt, P.R.; Mahoney, L.A.; Forbes, S.V.; Tingey, S.M.

    1997-09-01

    The 177 storage tanks at Hanford contain a vast array of radioactive waste forms resulting, primarily, from nuclear materials processing. Through radiolytic, thermal, and other decomposition reactions of waste components, gaseous species including hydrogen, ammonia, and the oxidizer nitrous oxide are generated within the waste tanks. Many of these tanks are known to retain and periodically release quantities of these flammable gas mixtures. The primary focus of the Flammable Gas Project is the safe storage of Hanford tank wastes. To this end, we strive to develop an understanding of the mechanisms of flammable gas retention and release in Hanford tanks through laboratory investigations on actual tank wastes. These results support the closure of the Flammable Gas Unreviewed Safety Question (USQ) on the safe storage of waste tanks known to retain flammable gases and support resolution of the broader Flammable Gas Safety Issue. The overall purpose of this ongoing study is to develop a comprehensive and thorough understanding of the mechanisms of flammable gas retention and release. The first objective of the current study was to classify bubble retention and release mechanisms in two previously untested waste materials from Tanks 241-AN-103 (AN-103) and 241-AW-101 (AW-101). Results were obtained for retention mechanisms, release characteristics, and the maximum gas retention. In addition, unique behavior was also documented and compared with previously studied waste samples. The second objective was to lengthen the duration of the experiments to evaluate the role of slowing bubble growth on the retention and release behavior. Results were obtained for experiments lasting from a few hours to a few days.

  20. Mechanisms of gas retention and release: Experimental results for Hanford waste tanks 241-AW-101 and 241-AN-103

    International Nuclear Information System (INIS)

    Rassat, S.D.; Gauglitz, P.A.; Bredt, P.R.; Mahoney, L.A.; Forbes, S.V.; Tingey, S.M.

    1997-09-01

    The 177 storage tanks at Hanford contain a vast array of radioactive waste forms resulting, primarily, from nuclear materials processing. Through radiolytic, thermal, and other decomposition reactions of waste components, gaseous species including hydrogen, ammonia, and the oxidizer nitrous oxide are generated within the waste tanks. Many of these tanks are known to retain and periodically release quantities of these flammable gas mixtures. The primary focus of the Flammable Gas Project is the safe storage of Hanford tank wastes. To this end, we strive to develop an understanding of the mechanisms of flammable gas retention and release in Hanford tanks through laboratory investigations on actual tank wastes. These results support the closure of the Flammable Gas Unreviewed Safety Question (USQ) on the safe storage of waste tanks known to retain flammable gases and support resolution of the broader Flammable Gas Safety Issue. The overall purpose of this ongoing study is to develop a comprehensive and thorough understanding of the mechanisms of flammable gas retention and release. The first objective of the current study was to classify bubble retention and release mechanisms in two previously untested waste materials from Tanks 241-AN-103 (AN-103) and 241-AW-101 (AW-101). Results were obtained for retention mechanisms, release characteristics, and the maximum gas retention. In addition, unique behavior was also documented and compared with previously studied waste samples. The second objective was to lengthen the duration of the experiments to evaluate the role of slowing bubble growth on the retention and release behavior. Results were obtained for experiments lasting from a few hours to a few days

  1. Safety culture in Bayesian and legal contexts

    International Nuclear Information System (INIS)

    Krug, H.E.P. Jr.

    1992-01-01

    While contemplating the similarities between the law of torts and concepts of safety, the author realized that there was a close correspondence between the law of negligence and the way safety ought to be generally defined. This definition of safety is provided herein. A safety culture must have an adequate definition of safety in order to function most effectively. This paper provides a practical definition of safety that answers the question 'How safe is safe enough? The development rests on two bases: the subjectivistic-Bayesian definition of probability and certain legal definitions primarily from the tort law of negligence. The development also leads to the conclusion that one cannot generally expect greater specificity in determining how safe is safe enough than one finds in the legal definition of liability under the tort of negligence. It then follows that some of the public's aversion to complex technical undertakings is rooted in its typically intuitive and vague notions concerning safety

  2. Tank 241-SY-101 surface level rise remediation test and evaluation plan for transfer system

    International Nuclear Information System (INIS)

    BAUER, R.E.

    1999-01-01

    The purpose of this testing and evaluation plan (TEP) is to provide the high level guidance on testing requirements for ensuring that the equipment and systems to be implemented for remediation of the SY-101 waste level rise USQ are effective

  3. Patient safety is not elective: a debate at the NPSF Patient Safety Congress.

    Science.gov (United States)

    McTiernan, Patricia; Wachter, Robert M; Meyer, Gregg S; Gandhi, Tejal K

    2015-02-01

    The opening keynote session of the 16th Annual National Patient Safety Foundation Patient Safety Congress, held 14-16 May 2014, featured a debate addressing the merits and challenges of accountability with respect to key issues in patient safety. The specific resolution debated was: Certain safety practices should be inviolable, and transgressions should result in penalties, potentially including fines, suspensions, and firing. The themes discussed in the debate are issues that healthcare professionals and leaders commonly struggle with in their day-to-day work. How do we draw a line between systems problems and personal failings? When should clinicians and staff be penalised for failing to follow a known safety protocol? The majority of those who listened to the live debate agreed that it is time to begin holding health professionals accountable when they wilfully or repeatedly violate policies or protocols put in place by their institutions to protect the safety of patients. This article summarises the debate as well as the questions and discussion generated by each side. A video of the original debate can be found at http://bit.ly/Npsf_debate. 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.

  4. Clinical risk management and patient safety education for nurses: a critique.

    Science.gov (United States)

    Johnstone, Megan-Jane; Kanitsaki, Olga

    2007-04-01

    Nurses have a pivotal role to play in clinical risk management (CRM) and promoting patient safety in health care domains. Accordingly, nurses need to be prepared educationally to manage clinical risk effectively when delivering patient care. Just what form the CRM and safety education of nurses should take, however, remains an open question. A recent search of the literature has revealed a surprising lack of evidence substantiating models of effective CRM and safety education for nurses. In this paper, a critical discussion is advanced on the question of CRM and safety education for nurses and the need for nurse education in this area to be reviewed and systematically researched as a strategic priority, nationally and internationally. It is a key contention of this paper that without 'good' safety education research it will not be possible to ensure that the educational programs that are being offered to nurses in this area are evidence-based and designed in a manner that will enable nurses to develop the capabilities they need to respond effectively to the multifaceted and complex demands that are inherent in their ethical and professional responsibilities to promote and protect patient safety and quality care in health care domains.

  5. The Fukushima nuclear accident: insights on the safety aspects

    Energy Technology Data Exchange (ETDEWEB)

    Thome, Zieli D.; Vellozo, Sergio O., E-mail: zielithome@gmail.com, E-mail: vellozo@cbpf.br [Instituto Militar de Engenharia (IME), Rio de Janeiro, RJ (Brazil). Secao de Engenharia Nuclear; Gomes, Rogerio S., E-mail: rogeriog@cnen.gov.br [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil); Silva, Fernando C., E-mail: fernando@con.ufrj.br [Coordenacao do Programas de Pos-Graduacao em Engenharia (COPPE/UFRJ), Rio de Janeiro, RJ (Brazil)

    2013-07-01

    The Fukushima nuclear accident has generated doubts and questions which need to be properly understood and addressed. This scientific attitude became necessary to allow the use of the nuclear technology for electricity generation around the world. The nuclear stakeholders are working to obtain these technical answers for the Fukushima questions. We believe that, such challenges will be, certainly, implemented in the next reactor generation, following the technological evolution. The purpose of this work is to perform a critical analysis of the Fukushima nuclear accident, focusing at the common cause failures produced by tsunami, as well as an analysis of the main redundant systems. This work also assesses the mitigative procedures and the subsequent consequences of such actions, which gave results below expectations to avoid the progression of the accident, discussing the concept of sharing of structures, systems and components at multi-unit nuclear power plants, and its eventual inappropriate use in safety-related devices which can compromise the nuclear safety, as well as its consequent impact on the Fukushima accident scenario. The lessons from Fukushima must be better learned, aiming the development of new procedures and new safety systems. Thus, the nuclear technology could reach a higher evolution level in its safety requirements. This knowledge will establish a conceptual milestone in the safety system design, becoming necessary the review of the current acceptance criteria of safety-related systems. (author)

  6. The Fukushima nuclear accident: insights on the safety aspects

    International Nuclear Information System (INIS)

    Thome, Zieli D.; Vellozo, Sergio O.; Silva, Fernando C.

    2013-01-01

    The Fukushima nuclear accident has generated doubts and questions which need to be properly understood and addressed. This scientific attitude became necessary to allow the use of the nuclear technology for electricity generation around the world. The nuclear stakeholders are working to obtain these technical answers for the Fukushima questions. We believe that, such challenges will be, certainly, implemented in the next reactor generation, following the technological evolution. The purpose of this work is to perform a critical analysis of the Fukushima nuclear accident, focusing at the common cause failures produced by tsunami, as well as an analysis of the main redundant systems. This work also assesses the mitigative procedures and the subsequent consequences of such actions, which gave results below expectations to avoid the progression of the accident, discussing the concept of sharing of structures, systems and components at multi-unit nuclear power plants, and its eventual inappropriate use in safety-related devices which can compromise the nuclear safety, as well as its consequent impact on the Fukushima accident scenario. The lessons from Fukushima must be better learned, aiming the development of new procedures and new safety systems. Thus, the nuclear technology could reach a higher evolution level in its safety requirements. This knowledge will establish a conceptual milestone in the safety system design, becoming necessary the review of the current acceptance criteria of safety-related systems. (author)

  7. Health, safety and environmental research program

    International Nuclear Information System (INIS)

    Dinner, P.J.

    1983-01-01

    This report outlines the Health, Safety and Environmental Research Program being undertaken by the CFFTP. The Program objectives, relationship to other CFFTP programs, implementation plans and expected outputs are stated. Opportunities to build upon the knowledge and experience gained in safely managing tritium in the CANDU program, by addressing generic questions pertinent to tritium safety for fusion facilities, are identified. These opportunities exist across a broad spectrum of issues covering the anticipated behaviour of tritium in fusion facilities, the surrounding environment and in man

  8. Status of Safety Precautions in Science Laboratories in Enugu State ...

    African Journals Online (AJOL)

    This study was conducted to determine the status of safety precautions in science laboratories in Enugu State of Nigeria. Three research questions and two hypotheses guided the study. The research questions include: 1. What are the sources of hazards in school science laboratories? 2. What are the causes of accidents in ...

  9. 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.

  10. Chernobyl and the safety of nuclear reactors in OECD countries

    International Nuclear Information System (INIS)

    1987-01-01

    This report assesses the possible bearing of the Chernobyl accident on the safety of nuclear reactors in OECD countries. It discusses analyses of the accident performed in several countries as well as improvements to the safety of RBMK reactors announced by the USSR. Several remaining questions are identified. The report compares RBMK safety features with those of commercial reactors in OECD countries and evaluates a number of issues raised by the Chernobyl accident

  11. Safety and risk questions following the nuclear incidents and accidents in Japan. Summary final report

    International Nuclear Information System (INIS)

    Mildenberger, Oliver

    2015-03-01

    After the nuclear accidents in Japan, GRS has carried out in-depth investigations of the events. On the one hand, the accident sequences in the affected units have been analysed from various viewpoints. On the other hand, the transferability of the findings to German plants has been examined to possibly make recommendations for safety improvements. The accident sequences at Fukushima Daiichi have been traced with as much detail as possible based on all available information. Additional insights have been drawn from thermohydraulic analyses with the GRS code system ATHLET-CD/COCOSYS focusing on the events in units 2 and 3, e.g. with regard to core damage and the state of the containments in the first days of the accident sequence. In-depth investigations have also been carried out on topics such as natural external hazards, electrical power supply or organizational measures. In addition, methodological studies on further topics related with the accidents have been performed. Through a detailed analysis of the relevant data from the events in Japan, the basis for an in-depth examination of the transferability to German plants was created. It was found that an implementation of most of the insights gained from the investigations had already been initiated as part of the GRS information notice 2012/02. Further findings have been communicated to the federal government and introduced into other relevant bodies, e.g. the Nuclear Safety Standards Committee (KTA) or the Reactor Safety Commission (RSK).

  12. Are classical process safety concepts relevant to nanotechnology applications?

    International Nuclear Information System (INIS)

    Amyotte, Paul R

    2011-01-01

    The answer to the question posed by the title of this paper is yes - with adaptation to the specific hazards and challenges found in the field of nanotechnology. The validity of this affirmative response is demonstrated by relating key process safety concepts to various aspects of the nanotechnology industry in which these concepts are either already practised or could be further applied. This is accomplished by drawing on the current author's experience in process safety practice and education as well as a review of the relevant literature on the safety of nanomaterials and their production. The process safety concepts selected for analysis include: (i) risk management, (ii) inherently safer design, (iii) human error and human factors, (iv) safety management systems, and (v) safety culture.

  13. Perinatal safety: from concept to nursing practice.

    Science.gov (United States)

    Lyndon, Audrey; Kennedy, Holly Powell

    2010-01-01

    Communication and teamwork problems are leading causes of documented preventable adverse outcomes in perinatal care. An essential component of perinatal safety is the organizational culture in which clinicians work. Clinicians' individual and collective authority to question the plan of care and take action to change the direction of a clinical situation in the patient's best interest can be viewed as their "agency for safety." However, collective agency for safety and commitment to support nurses in their role of advocacy is missing in many perinatal care settings. This article draws from Organizational Accident Theory, High Reliability Theory, and Symbolic Interactionism to describe the nurse's role in maintaining safety during labor and birth in acute care settings and suggests actions for supporting the perinatal nurse at individual, group, and systems levels to achieve maximum safety in perinatal care.

  14. Perinatal Safety: From Concept to Nursing Practice

    Science.gov (United States)

    Kennedy, Holly Powell

    2010-01-01

    Communication and teamwork problems are leading causes of documented preventable adverse outcomes in perinatal care. An essential component of perinatal safety is the organizational culture in which clinicians work. Clinicians’ individual and collective authority to question the plan of care and take action to change the direction of a clinical situation in the patient’s best interest can be viewed as their “agency for safety.” However, collective agency for safety and commitment to support nurses in their advocacy role is missing in many perinatal care settings. This paper draws from Organizational Accident Theory, High Reliability Theory, and Symbolic Interactionism to describe the nurse’s role in maintaining safety during labor and birth in acute care settings, and suggests actions for supporting the perinatal nurse at individual, group, and systems levels to achieve maximum safety in perinatal care. PMID:20147827

  15. 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

  16. Safety and nuclear power

    International Nuclear Information System (INIS)

    Gittus, John; Gunning, Angela.

    1988-01-01

    Representatives of the supporters and opponents of civil nuclear power put forward the arguments they feel the public should consider when making up their mind about the nuclear industry. The main argument in favour of nuclear power is about the low risk in comparison with other risks and the amount of radiation received on average by the population in the United Kingdom from different sources. The aim is to show that the nuclear industry is fully committed to the cause of safety and this has resulted in a healthy workforce and a safe environment for the public. The arguments against are that the nuclear industry is deceitful, secretive and politically motivated and thus its arguments about safety, risks, etc, cannot be trusted. The question of safety is considered further - in particular the perceptions, definitions and responsibility. The economic case for nuclear electricity is not accepted. (U.K.)

  17. Risk analysis and safety rationale

    International Nuclear Information System (INIS)

    Bengtsson, G.

    1989-01-01

    Decision making with respect to safety is becoming more and more complex. The risk involved must be taken into account together with numerous other factors such as the benefits, the uncertainties and the public perception. Can the decision maker be aided by some kind of system, general rules of thumb, or broader perspective on similar decisions? This question has been addressed in a joint Nordic project relating to nuclear power. Modern techniques for risk assessment and management have been studied, and parallels drawn to such areas as offshore safety and management of toxic chemicals in the environment. The report summarises the finding of 5 major technical reports which have been published in the NORD-series. The topics includes developments, uncertainties and limitations in probabilistic safety assessments, negligible risks, risk-cost trade-offs, optimisation of nuclear safety and radiation protection, and the role of risks in the decision making process. (author) 84 refs

  18. Status of nuclear safety research - 2000

    International Nuclear Information System (INIS)

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

    2000-11-01

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

  19. Research on PWR safety in France

    International Nuclear Information System (INIS)

    Zammite, R.

    1988-07-01

    The French nuclear safety arrangements form a centralized system characterized by cooperation between the government authorities, their technical advisers and the operators of the installations, especially between the Commissariat a l'Energie Atomique (CEA) and Electricite de France (EDF). This cooperation in no way contradicts the respective responsibilities of the different parties, in particular those of EDF regarding the safety of its installations and those of CEA as the government's technical adviser and safety analyst. However, it considerably affects the research on reactor safety, which is mainly performed by the CEA Institute for Nuclear Safety and Protection (IPSN), in collaboration with EDF. For PWRs, the safety preoccupations concerning their development, commissioning and operation can be divided into the following three categories: A. Safety in design and construction, B. Safety in operation and the control of potential accidents, C. Maintaining safety - aging problems. The effort consecrated to each category has varied in the past and will continue to do so in the future. At the present stage, emphasis is being given to categories B and C. The appendix includes tables which indicate, for categories A, B and C, the relationship between the existing research programmes and the questions remaining open that they are intended to solve

  20. Software reliability for safety-critical applications

    International Nuclear Information System (INIS)

    Everett, B.; Musa, J.

    1994-01-01

    In this talk, the authors address the question open-quotes Can Software Reliability Engineering measurement and modeling techniques be applied to safety-critical applications?close quotes Quantitative techniques have long been applied in engineering hardware components of safety-critical applications. The authors have seen a growing acceptance and use of quantitative techniques in engineering software systems but a continuing reluctance in using such techniques in safety-critical applications. The general case posed against using quantitative techniques for software components runs along the following lines: safety-critical applications should be engineered such that catastrophic failures occur less frequently than one in a billion hours of operation; current software measurement/modeling techniques rely on using failure history data collected during testing; one would have to accumulate over a billion operational hours to verify failure rate objectives of about one per billion hours

  1. Maternal worries, home safety behaviors, and perceived difficulties.

    Science.gov (United States)

    Hendrickson, Sherry Garrett

    2008-01-01

    The aim of the study was to explore the worries, safety behaviors, and perceived difficulties in keeping children safe at home in a purposive sample of low-income, predominantly non-English speaking mothers as a foundation for later nursing interventions. This study was a qualitative, descriptive design with content analysis to identify maternal concerns, behaviors, and perceptions of home safety as part of a larger study. Eighty-two mothers, 64% of whom were monolingual Spanish-speakers, responded in writing to three semistructured interview questions. When mothers were unable to read and write the researcher wrote the responses, then read the content aloud for verification. A standardized probe for each question was posed to obtain richer responses. Data management included use of the software program NUD*IST and coding analyses following the Miles and Huberman guidelines (1994). Interpretations were translated into English for this report. The major worries were falling, health, kidnapping, and being hit by a car. The leading maternal behaviors were coded as being physically, verbally, and environmentally preventive. Mothers said that it was their role to provide safety, and that this role could be wearisome, such that constant supervision was difficult. Low-income mothers described their worries for their 1 to 4 year-old children, explored their behaviors for preventing injury, and discussed what made keeping children from harm difficult. Understanding how mothers keep children safe, the barriers to home safety, and effective safety behaviors are important to the health of children. The clinical relevance of this study includes building trust as clinicians plan assessment, intervention and evaluation of home safety to encourage dialog about concerns, safety behaviors, and barriers to keeping children from injury.

  2. Assessment of safety culture in isfahan hospitals (2010).

    Science.gov (United States)

    Raeisi, Ahmed Reza; Nazari, Maryam; Bahmanziari, Najme

    2013-01-01

    Many internal and external risk factors in health care organizations make safety important and it has caused the management to consider safety in their mission statement. One of the most important tools is to establish the appropriate organizational structure and safety culture. The goal of this research is to inform managers and staff about current safety culture status in hospitals in order to improve the efficiency and effectiveness of health services. This is a descriptive-survey research. The research population was selected hospitals of Isfahan, Iran. Research tool was a questionnaire (Cronbach alpha 0.75). The questionnaire including 93 questions (Likert scale) classified in 12 categories: Demographic questions, Individual attitude, management attitude, Safety Training, Induced stress, pressure and emotional conditions during work, Consultation and participation, Communications, Monitoring and control, work environment, Reporting, safety Rules, procedures and work instructions that distributed among 45 technicians, 208 Nurses and 62 Physicians. All data collected from the serve was analysis with statistical package of social science (SPSS). In this survey Friedman test, Spearman correlation, analysis of variance (ANOVA) and factor analysis have been used for data analyzing. The score of safety culture dimensions was 2.90 for Individual attitude, 3.12 for management attitude, 3.32 for Safety Training, 3.14 for Induced stress, pressure and emotional conditions during work, 3.31 for Consultation and participation, 2.93 for Communications, 3.28 for Monitoring and control, 3.19 for work environment, 3.36 for Reporting, 3.59 safety Rules, procedures and work instructions that Communication and individual attitude were in bad condition. Safety culture among different hospitals: governmental and educational, governmental and non-educational and non-governmental and different functional groups (physicians, nurses, diagnostic) of studied hospitals showed no

  3. Non-technical issues in safety assessments for nuclear disposal facilities

    International Nuclear Information System (INIS)

    Kallenbach-Herbert, Beate; Brohmann, Bettina

    2010-09-01

    The paper highlights that a comprehensive approach to safety affords the consideration of technology, organisation, personnel and social environment. In several safety relevant contexts of nuclear waste disposal these fields are closely interrelated. The approach for the consideration of socio-scientific aspects which is sketched in this paper supports the systematic treatment of safety relevant non-technical issues in the safety case or in safety assessments for a disposal project. Furthermore it may foster the dialogue among specialists from the technical, the natural- and the socio-scientific field on questions of disposal safety. In this way it may contribute to a better understanding among the affected scientific disciplines in nuclear waste disposal.

  4. [Training in patient safety in medical and nursing schools].

    Science.gov (United States)

    Mira, J J; Guilabert, M; Vitaller, J; Ignacio, E

    2016-01-01

    To compare the information on patient safety received by students of medicine and nursing. Cross-sectional study was conducted using a convenience sample of medical and nursing students of 3 Universities. The Latin Patient Safety Student Information and a test of 5 questions with 5 options were used. A sample of 79 students in each group was enrolled to detect differences of .3 units (bilateral estimation), considering 80% statistical power and 95% confidence interval. A total of 144 students replied (74 nursing and 70 medicine students). Nursing students achieved higher scores in the communication with patients factor (3.8 vs 3.2, P<.001) and proactive attitude to identify risks for patient safety (4.3 vs 3.8, P<.001). Medical students were more aware of the inevitability of adverse events (2.3 vs 3.1, P<.001). Ten (7%) students had only one fault in the test, and only one (1%) answered all questions correctly. The training in patient safety should be improved both in nursing and medicine, although nursing students receive more information. Copyright © 2015 SECA. Published by Elsevier Espana. All rights reserved.

  5. Nuclear-safety institution in France: emergence and development

    International Nuclear Information System (INIS)

    Vallet, B.M.

    1986-01-01

    This research work examines the social construction of the nuclear-safety institution in France, and the concurrent increased focus on the nuclear-risk issue. Emphasis on risk and safety, as primarily technical issues, can partly be seen as a strategy. Employed by power elites in the nuclear technostructure, this diverts emphasis away from controversial and normative questions regarding the political and social consequences of technology to questions of technology that appear to be absolute to the technology itself. Nuclear safety, which started from a preoccupation with risk related to the nuclear energy research and development process, is examined using the analytic concept of field. As a social arena patterned to achieve specific tasks, this field is dominated by a body of state engineers recognized to have high-level scientific and administrative competences. It is structured by procedures and administrative hierarchies as well as by technical rules, norms, and standards. These are formalized and rationalized through technical, economic, political, and social needs; over time; they consolidate the field into an institution. The study documents the nuclear-safety institution as an integral part of the nuclear technostructure, which has historically used the specificity of its expertise as a buffer against outside interference

  6. Socratic Questioning-Guided Discovery

    Directory of Open Access Journals (Sweden)

    M. Hakan Türkçapar

    2012-04-01

    Full Text Available “Socratic Method” is a way of teaching philosophical thinking and knowledge by asking questions which was used by antique period greek philosopher Socrates. Socrates was teaching knowledge to his followers by asking questions and the conversation between them was named “Socratic Dialogues”. In this meaning, no novel knowledge is taught to the individual but only what is formerly known is reminded and rediscovered. The form of socratic questioning which is used during the process of cognitive behavioral therapy is known as Guided Discovery. In this method it is aimed to make the client notice the piece of knowledge which he could notice but is not aware with a series of questions. Socratic method or guided discovery consists of several steps which are: Identifying the problem by listening to the client and making reflections, finding alternatives by examining and evaluating, reidentification by using the newly found information and questioning the old distorted belief and reaching to a conclusion and applying it. Question types used during these procedures are, questions for gaining information, questions revealing the meanings, questions revealing the beliefs, questions about behaviours during the similar past experiences, analyse questions and analytic synthesis questions. In order to make the patient feel understood it is important to be empathetic and summarising the problem during the interview. In this text, steps of Socratic Questioning-Guided Discovery will be reviewed with sample dialogues after eachstep. [JCBPR 2012; 1(1.000: 15-20

  7. Industry Leader Perceptions of Workplace Safety

    Science.gov (United States)

    Dunlap, Erik Scott

    2009-01-01

    This study investigated the perceptions of workplace safety held by industry leaders who were near completion of a Master of Business Administration (MBA) degree. This was a qualitative study that utilized interpretivism as the theoretical framework. The study sought to answer four research questions. (1) How do participants conceptualize…

  8. [Operating Room Nurses' Experiences of Securing for Patient Safety].

    Science.gov (United States)

    Park, Kwang Ok; Kim, Jong Kyung; Kim, Myoung Sook

    2015-10-01

    This study was done to evaluate the experience of securing patient safety in hospital operating rooms. Experiential data were collected from 15 operating room nurses through in-depth interviews. The main question was "Could you describe your experience with patient safety in the operating room?". Qualitative data from the field and transcribed notes were analyzed using Strauss and Corbin's grounded theory methodology. The core category of experience with patient safety in the operating room was 'trying to maintain principles of patient safety during high-risk surgical procedures'. The participants used two interactional strategies: 'attempt continuous improvement', 'immersion in operation with sharing issues of patient safety'. The results indicate that the important factors for ensuring the safety of patients in the operating room are manpower, education, and a system for patient safety. Successful and safe surgery requires communication, teamwork and recognition of the importance of patient safety by the surgical team.

  9. Evaluation of the Finnish nuclear safety research program 'SAFIR2010'

    International Nuclear Information System (INIS)

    2010-01-01

    A panel of three members has been asked by the Ministry of Employment and the Economy (MEE) to evaluate SAFIR2010, the Finnish research program on nuclear power plant safety. The program was established for the period 2007-2010 to help maintain expertise in nuclear safety, to integrate young people into the research in order to help assure the future availability of expertise, and to support international collaborations. The program is directed by a Steering Group, appointed by MEE, with representatives from all organizations involved with nuclear safety in Finland. SAFIR2010 has consisted of approximately 30 projects from year to year that fall into eight subject areas: 1. Organization and human factors 2. Automation and control room 3. Fuel and reactor physics 4. Thermal hydraulics 5. Severe accidents 6. Structural safety of reactor circuit 7. Construction safety 8. Probabilistic safety analysis (PSA) For each of these areas there are Reference Groups that provide oversight of the projects within their jurisdiction. The panel carried out its evaluation by reviewing copies of relevant documents and, during a one-week period 17-22 January 2010, meeting with key individuals. The results of the panel are provided as general conclusions, responses to questions posed by MEE, challenges and recommendations and comments on specific projects in each subject area. The general conclusions reflect the panel's view that SAFIR2010 is meeting its objectives and carrying out quality research. The questions addressed are: (a.) Are the achieved results in balance with the funding? Are the results exploited efficiently in practice? (b.) How well does the expertise cover the field? Is the entire SAFIR2010 programme balanced to all different fields in nuclear safety? Does it raise efficiently new experts? (c.) Have the 2006 evaluation results been implemented successfully into SAFIR2010 program? (d.) Challenges and recommendations. In general the panel was very positive about SAFIR

  10. Visitor Safety and Security in Barbados: Stakeholder Perceptions

    OpenAIRE

    Clifford Griffin

    2010-01-01

    Is information about the nature, location and incidence of crimes against tourists/visitors sufficient to develop meaningful visitor safety and security policy? Are the views of key tourism stakeholder groups useful in informing and enhancing visitor safety and security policy? To answer these questions, this study analyzes 24 years of recorded crime data against visitors to Barbados and survey data of key tourism stakeholder groups and concludes: 1) that information about the nature, locatio...

  11. Addressing Uniqueness and Unison of Reliability and Safety for a Better Integration

    Science.gov (United States)

    Huang, Zhaofeng; Safie, Fayssal

    2016-01-01

    Over time, it has been observed that Safety and Reliability have not been clearly differentiated, which leads to confusion, inefficiency, and, sometimes, counter-productive practices in executing each of these two disciplines. It is imperative to address this situation to help Reliability and Safety disciplines improve their effectiveness and efficiency. The paper poses an important question to address, "Safety and Reliability - Are they unique or unisonous?" To answer the question, the paper reviewed several most commonly used analyses from each of the disciplines, namely, FMEA, reliability allocation and prediction, reliability design involvement, system safety hazard analysis, Fault Tree Analysis, and Probabilistic Risk Assessment. The paper pointed out uniqueness and unison of Safety and Reliability in their respective roles, requirements, approaches, and tools, and presented some suggestions for enhancing and improving the individual disciplines, as well as promoting the integration of the two. The paper concludes that Safety and Reliability are unique, but compensating each other in many aspects, and need to be integrated. Particularly, the individual roles of Safety and Reliability need to be differentiated, that is, Safety is to ensure and assure the product meets safety requirements, goals, or desires, and Reliability is to ensure and assure maximum achievability of intended design functions. With the integration of Safety and Reliability, personnel can be shared, tools and analyses have to be integrated, and skill sets can be possessed by the same person with the purpose of providing the best value to a product development.

  12. Safety culture and accident analysis-A socio-management approach based on organizational safety social capital

    International Nuclear Information System (INIS)

    Rao, Suman

    2007-01-01

    One of the biggest challenges for organizations in today's competitive business environment is to create and preserve a self-sustaining safety culture. Typically, Key drivers of safety culture in many organizations are regulation, audits, safety training, various types of employee exhortations to comply with safety norms, etc. However, less evident factors like networking relationships and social trust amongst employees, as also extended networking relationships and social trust of organizations with external stakeholders like government, suppliers, regulators, etc., which constitute the safety social capital in the Organization-seem to also influence the sustenance of organizational safety culture. Can erosion in safety social capital cause deterioration in safety culture and contribute to accidents? If so, how does it contribute? As existing accident analysis models do not provide answers to these questions, CAMSoC (Curtailing Accidents by Managing Social Capital), an accident analysis model, is proposed. As an illustration, five accidents: Bhopal (India), Hyatt Regency (USA), Tenerife (Canary Islands), Westray (Canada) and Exxon Valdez (USA) have been analyzed using CAMSoC. This limited cross-industry analysis provides two key socio-management insights: the biggest source of motivation that causes deviant behavior leading to accidents is 'Faulty Value Systems'. The second biggest source is 'Enforceable Trust'. From a management control perspective, deterioration in safety culture and resultant accidents is more due to the 'action controls' rather than explicit 'cultural controls'. Future research directions to enhance the model's utility through layering are addressed briefly

  13. Safety evaluation of the nuclear power plant at Cattenom

    International Nuclear Information System (INIS)

    Anon.

    1987-01-01

    This is a systematic compilation of the material which was dealt with at the level of the German-French Commission (on questions of the safety of nuclear installations) in this discussions about the nuclear power plant at Cattenom. As a supplement to the report published already in 1982, the Commission has officially released its deliberation results on the subjects constructive safety measures, radiological effects, and precautions in case of an emergency. The allegations according to which the installation is wanting in safety are countered by the joint statement of the chairmen of GPR (Permanent Group on Reactors) and RSK (German Commission on Reactor Safety) of August 29, 1986. (HSCH) [de

  14. Beginning EFL Teachers' Beliefs about Quality Questions and Their Questioning Practices

    Science.gov (United States)

    Pham, Ly Ngoc Khanh; Hamid, M. Obaidul

    2013-01-01

    Motivated by the scarcity of research that examines the impact of teacher beliefs on their actual practices in Vietnam, this study investigated the relationship between teachers' beliefs about quality questions and their questioning behaviours in terms of questioning purposes, content focus, students' cognitive level, wording and syntax. Thirteen…

  15. 77 FR 20558 - Federal Motor Vehicle Safety Standards; Platform Lifts for Motor Vehicles; Platform Lift...

    Science.gov (United States)

    2012-04-05

    ... unrelated to the barrier's safety. Lift-U also questioned the agency's statement that it could be difficult... DEPARTMENT OF TRANSPORTATION National Highway Traffic Safety Administration 49 CFR Part 571 [Docket No. NHTSA-2012-0039] RIN 2127-AJ93 Federal Motor Vehicle Safety Standards; Platform Lifts for...

  16. Questioning the economic viability of nuclear power

    International Nuclear Information System (INIS)

    Murota, Takeshi

    1981-01-01

    In the United States, the pioneer in nuclear power generation, the economic aspect of nuclear power is now questioned. Its economy in Japan is supported by the entirely monopolistic nature of the power generating firms. The economy of the nuclear power generation in Japan is first examined in its original cost. It is then analyzed in legislative economics. In the conventional arguments, the authorities in favor of nuclear power stick to its practical safety, acknowledging its potential danger, while the people against it adheres to its danger. Thus both arguments go in parallel, never converging. It is attempted to elucidate through the atomic energy damage compensation system, on the boundary between legislation and economy, to whom nuclear power generation is safe, and to whom it is dangerous. (J.P.N.)

  17. Sex differences in principal farm operators' tractor driving safety beliefs and behaviors.

    Science.gov (United States)

    Cole, H P; Westneat, S C; Browning, S R; Piercy, L R; Struttmann, T

    2000-01-01

    To examine the widely accepted hypothesis that farm women are more concerned with safety issues and behaviors than their male counterparts are. A telephone survey was administered to a random sample of Kentucky principal farm operators, 90 of whom were women. Participants were questioned about their tractor safety beliefs and practices. No significant sex differences in tractor safety perceptions and behavior were observed. Socialization of women to the role of principal farm operator may override their typically greater sensitivity to safety issues, an important consideration when designing safety campaigns for this population.

  18. Reactor safety in the Netherlands

    International Nuclear Information System (INIS)

    Eendebak, B.Th.

    1983-01-01

    In this book, the author gives a survey of the most important safety aspects of the construction and operation of nuclear power plants in the Netherlands. It deals with concrete questions like how to choose appropriate sites for power plants; what are the risks for people living in their surroundings; what are the consequences of possible accidents; what to do with the nuclear wastes and what are the conseqences for new generations. For answering these questions, the author has presented a fairly well documented outline of the contemporary problems. So, the book is a useful tool for everybody who wants to become acquainted with the nuclear controversy (G.J.P.)

  19. Safety impacts of bicycle infrastructure: A critical review.

    Science.gov (United States)

    DiGioia, Jonathan; Watkins, Kari Edison; Xu, Yanzhi; Rodgers, Michael; Guensler, Randall

    2017-06-01

    This paper takes a critical look at the present state of bicycle infrastructure treatment safety research, highlighting data needs. Safety literature relating to 22 bicycle treatments is examined, including findings, study methodologies, and data sources used in the studies. Some preliminary conclusions related to research efficacy are drawn from the available data and findings in the research. While the current body of bicycle safety literature points toward some defensible conclusions regarding the safety and effectiveness of certain bicycle treatments, such as bike lanes and removal of on-street parking, the vast majority treatments are still in need of rigorous research. Fundamental questions arise regarding appropriate exposure measures, crash measures, and crash data sources. This research will aid transportation departments with regard to decisions about bicycle infrastructure and guide future research efforts toward understanding safety impacts of bicycle infrastructure. Copyright © 2017 Elsevier Ltd and National Safety Council. All rights reserved.

  20. Electronic Safety Resource Tools -- Supporting Hydrogen and Fuel Cell Commercialization

    Energy Technology Data Exchange (ETDEWEB)

    Barilo, Nick F.

    2014-09-29

    The Pacific Northwest National Laboratory (PNNL) Hydrogen Safety Program conducted a planning session in Los Angeles, CA on April 1, 2014 to consider what electronic safety tools would benefit the next phase of hydrogen and fuel cell commercialization. A diverse, 20-person team led by an experienced facilitator considered the question as it applied to the eight most relevant user groups. The results and subsequent evaluation activities revealed several possible resource tools that could greatly benefit users. The tool identified as having the greatest potential for impact is a hydrogen safety portal, which can be the central location for integrating and disseminating safety information (including most of the tools identified in this report). Such a tool can provide credible and reliable information from a trustworthy source. Other impactful tools identified include a codes and standards wizard to guide users through a series of questions relating to application and specific features of the requirements; a scenario-based virtual reality training for first responders; peer networking tools to bring users from focused groups together to discuss and collaborate on hydrogen safety issues; and a focused tool for training inspectors. Table ES.1 provides results of the planning session, including proposed new tools and changes to existing tools.

  1. Safety culture and quality management of Kartini research reactor

    International Nuclear Information System (INIS)

    Syarip; Hauptmanns, Ulrich

    1999-01-01

    The evaluation for assessing the safety culture and quality of safety management of Kartini research reactor is presented. The method is based on the concept of management control of safety (audit) as well as by using the developed method i.e. the questionnaires concerning areas of relevance which have to be answered with value statements. There are seven statements or qualifiers in answering the questions. Since such statements are vague, they are represented by fuzzy numbers. The weaknesses can be identified from the different areas contemplated. The evaluation result show that the quality of safety management of Kartini research reactor is globally rated as 'Average'. The operator behavior in the implementation of 'safety culture' concept is found as a weakness, therefore this area should be improved. (author)

  2. A word from the DG: Improved safety at CERN

    CERN Multimedia

    2006-01-01

    One of the important objectives of my term of office is improving safety at CERN. My consideration of safety issues over the last few months, in conjunction with the Safety Commission and the Heads of Department, has led me to define a new approach for the implementation of safety policy at CERN. It is not a question of changing the safety policy and the basic safety rules laid down in document 'Safety Policy at CERN' (SAPOCO 42) but, rather, of improving the way they are applied by clarifying the roles of everyone concerned. The existing safety policy and rules have yet to be fully implemented. Some people continue to think, for example, that safety implementation only concerns the Safety Commission (SC). In reality, as SAPOCO 42 clearly specifies, safety is the responsibility of each and every individual. This means that each person in charge of a task is also responsible for guaranteeing its safe completion by implementing all the necessary measures. To enhance the awareness of this responsibility and t...

  3. Comparison between Two Assessment Methods; Modified Essay Questions and Multiple Choice Questions

    Directory of Open Access Journals (Sweden)

    Assadi S.N.* MD

    2015-09-01

    Full Text Available Aims Using the best assessment methods is an important factor in educational development of health students. Modified essay questions and multiple choice questions are two prevalent methods of assessing the students. The aim of this study was to compare two methods of modified essay questions and multiple choice questions in occupational health engineering and work laws courses. Materials & Methods This semi-experimental study was performed during 2013 to 2014 on occupational health students of Mashhad University of Medical Sciences. The class of occupational health and work laws course in 2013 was considered as group A and the class of 2014 as group B. Each group had 50 students.The group A students were assessed by modified essay questions method and the group B by multiple choice questions method.Data were analyzed in SPSS 16 software by paired T test and odd’s ratio. Findings The mean grade of occupational health and work laws course was 18.68±0.91 in group A (modified essay questions and was 18.78±0.86 in group B (multiple choice questions which was not significantly different (t=-0.41; p=0.684. The mean grade of chemical chapter (p<0.001 in occupational health engineering and harmful work law (p<0.001 and other (p=0.015 chapters in work laws were significantly different between two groups. Conclusion Modified essay questions and multiple choice questions methods have nearly the same student assessing value for the occupational health engineering and work laws course.

  4. Formative student-authored question bank: perceptions, question quality and association with summative performance.

    Science.gov (United States)

    Walsh, Jason L; Harris, Benjamin H L; Denny, Paul; Smith, Phil

    2018-02-01

    There are few studies on the value of authoring questions as a study method, the quality of the questions produced by students and student perceptions of student-authored question banks. Here we evaluate PeerWise, a widely used and free online resource that allows students to author, answer and discuss multiple-choice questions. We introduced two undergraduate medical student cohorts to PeerWise (n=603). We looked at their patterns of PeerWise usage; identified associations between student engagement and summative exam performance; and used focus groups to assess student perceptions of the value of PeerWise for learning. We undertook item analysis to assess question difficulty and quality. Over two academic years, the two cohorts wrote 4671 questions, answered questions 606 658 times and posted 7735 comments. Question writing frequency correlated most strongly with summative performance (Spearman's rank: 0.24, p=<0.001). Student focus groups found that: (1) students valued curriculum specificity; and (2) students were concerned about student-authored question quality. Only two questions of the 300 'most-answered' questions analysed had an unacceptable discriminatory value (point-biserial correlation <0.2). Item analysis suggested acceptable question quality despite student concerns. Quantitative and qualitative methods indicated that PeerWise is a valuable study tool. © Article author(s) (or their employer(s) unless otherwise stated in the text of the article) 2018. All rights reserved. No commercial use is permitted unless otherwise expressly granted.

  5. Patient Safety Learning Systems: A Systematic Review and Qualitative Synthesis.

    Science.gov (United States)

    2017-01-01

    A patient safety learning system (sometimes called a critical incident reporting system) refers to structured reporting, collation, and analysis of critical incidents. To inform a provincial working group's recommendations for an Ontario Patient Safety Event Learning System, a systematic review was undertaken to determine design features that would optimize its adoption into the health care system and would inform implementation strategies. The objective of this review was to address two research questions: (a) what are the barriers to and facilitators of successful adoption of a patient safety learning system reported by health professionals and (b) what design components maximize successful adoption and implementation? To answer the first question, we used a published systematic review. To answer the second question, we used scoping study methodology. Common barriers reported in the literature by health care professionals included fear of blame, legal penalties, the perception that incident reporting does not improve patient safety, lack of organizational support, inadequate feedback, lack of knowledge about incident reporting systems, and lack of understanding about what constitutes an error. Common facilitators included a non-accusatory environment, the perception that incident reporting improves safety, clarification of the route of reporting and of how the system uses reports, enhanced feedback, role models (such as managers) using and promoting reporting, legislated protection of those who report, ability to report anonymously, education and training opportunities, and clear guidelines on what to report. Components of a patient safety learning system that increased successful adoption and implementation were emphasis on a blame-free culture that encourages reporting and learning, clear guidelines on how and what to report, making sure the system is user-friendly, organizational development support for data analysis to generate meaningful learning outcomes

  6. A Complete Security of Criminological Safety of Minors

    Directory of Open Access Journals (Sweden)

    Andrey I. Saveliev

    2016-11-01

    Full Text Available The article considers questions relating to the diversity of theoretical comprehension levels of criminological safety of minors. The Author analyzes the normative legal basis of activities of subjects of prevention and protection of children's rights

  7. Nuclear questions

    International Nuclear Information System (INIS)

    Berg, Eugene

    2012-01-01

    Civilian and military nuclear questions fill a multitude of publications these days, especially after the Japanese tsunami and the Fukushima disaster. The author analyses some of them and highlights the links between civil and military nuclear industries, the realities of the nuclear cycle and related industrial questions before concluding on the controversial issue of weapons and their proliferation potential

  8. Approaches to Exploring Category Information for Question Retrieval in Community Question-Answer Archives

    DEFF Research Database (Denmark)

    Cao, Xin; Cong, Gao; Cui, Bin

    2012-01-01

    , and it applies these approaches to existing question retrieval models, including a state-of-the-art question retrieval model. Experiments conducted on real CQA data demonstrate that the proposed techniques are effective and efficient and are capable of outperforming a variety of baseline methods significantly......Community Question Answering (CQA) is a popular type of service where users ask questions and where answers are obtained from other users or from historical question-answer pairs. CQA archives contain large volumes of questions organized into a hierarchy of categories. As an essential function...

  9. Questions and Advice to the Swedish Radiation Authority in their Current Work on Radiation Safety from Participants in Focus Group Discussions in the Municipalities of Oesthammar and Oskarshamn

    International Nuclear Information System (INIS)

    Drottz-Sjoeberg, Britt-Marie

    2003-01-01

    In connection to their work on developing a 'general advice document', based on the radiation protection law, the Swedish Radiation Authority (SSI) initiated a process in 2002 that welcomed comments and suggestions from the general public, specifically representatives and interested parties involved in the work related to a Swedish repository for high level nuclear wastes. The authority held a seminar in September, and presented the forthcoming task. The present paper summarises and exemplifies discussions in focus groups in October 2002, when participants from the municipalities of Oskarshamn and Oesthammar met to give their input to the authority's ongoing work. The questions and suggestions emerging from the focus groups are classified into three major areas in this presentation: 1. Issues related specifically to radiation and radioactivity. 2. Issues of comprehension of terminology, measurements, risk, and safety. 3. Issues concerning the information process and the transfer of knowledge. The discussion highlights that issues and comments raised by the public are not constrained to specific knowledge questions, e.g. on radiation or risk, but may relate to legal, strategic and political considerations, as well as the basics of the performed analyses and the related assumptions and evaluations. Ideas for improving public knowledge and for facilitating an exchange of information are outlined below

  10. Questioning ORACLE: An Assessment of ORACLE's Analysis of Teachers' Questions and [A Comment on "Questioning ORACLE"].

    Science.gov (United States)

    Scarth, John; And Others

    1986-01-01

    Analysis of teachers' questions, part of the ORACLE (Observation Research and Classroom Learning Evaluation) project research, is examined in detail. Scarth and Hammersley argue that the rules ORACLE uses for identifying different types of questions involve levels of ambiguity and inference that threaten reliability and validity of the study's…

  11. Visitor Safety and Security in Barbados: Stakeholder Perceptions

    Directory of Open Access Journals (Sweden)

    Clifford Griffin

    2010-12-01

    Full Text Available Is information about the nature, location and incidence of crimes against tourists/visitors sufficient to develop meaningful visitor safety and security policy? Are the views of key tourism stakeholder groups useful in informing and enhancing visitor safety and security policy? To answer these questions, this study analyzes 24 years of recorded crime data against visitors to Barbados and survey data of key tourism stakeholder groups and concludes: 1 that information about the nature, location and incidence of crimes against visitors is necessary but not sufficient to inform visitor safety and security policy; and 2 that the views and input of key stakeholders are essential if destinations are to become more effective in enhancing visitor safety and security.

  12. Creating safety by strengthening clinicians' capacity for reflexivity

    Science.gov (United States)

    2011-01-01

    This commentary explores the nature of creating safety in the here-and-now. Creating safety encompasses two dimensions: revisiting specific behaviours by focusing on substandard performance (reflection), and a more broad-ranging attention to everyday behaviours that are taken as given (reflexivity). The piece pays particular attention to this second dimension of creating safety. Two techniques that promote reflexivity are discussed: video-filming real-time, everyday clinical practice and inviting clinicians' feedback about their own footage, and reflecting on the knowledge and questions that patients and families have about their care, and about unexpected outcomes and clinical incidents. The piece concludes that feedback about everyday practice using these methods is critical to enhancing the safety of everyday activity. PMID:21450780

  13. Undergraduate medical students' perceptions and intentions regarding patient safety during clinical clerkship.

    Science.gov (United States)

    Lee, Hoo-Yeon; Hahm, Myung-Il; Lee, Sang Gyu

    2018-04-04

    The purpose of this study was to examine undergraduate medical students' perceptions and intentions regarding patient safety during clinical clerkships. Cross-sectional study administered in face-to-face interviews using modified the Medical Student Safety Attitudes and Professionalism Survey (MSSAPS) from three colleges of medicine in Korea. We assessed medical students' perceptions of the cultures ('safety', 'teamwork', and 'error disclosure'), 'behavioural intentions' concerning patient safety issues and 'overall patient safety'. Confirmatory factor analysis and Spearman's correlation analyses was performed. In total, 194(91.9%) of the 211 third-year undergraduate students participated. 78% of medical students reported that the quality of care received by patients was impacted by teamwork during clinical rotations. Regarding error disclosure, positive scores ranged from 10% to 74%. Except for one question asking whether the disclosure of medical errors was an important component of patient safety (74%), the percentages of positive scores for all the other questions were below 20%. 41.2% of medical students have intention to disclose it when they saw a medical error committed by another team member. Many students had difficulty speaking up about medical errors. Error disclosure guidelines and educational efforts aimed at developing sophisticated communication skills are needed. This study may serve as a reference for other institutions planning patient safety education in their curricula. Assessing student perceptions of safety culture can provide clerkship directors and clinical service chiefs with information that enhances the educational environment and promotes patient safety.

  14. Putting Safety in the Frame: Nurses' Sensemaking at Work.

    Science.gov (United States)

    O'Keeffe, Valerie Jean; Thompson, Kirrilly Rebecca; Tuckey, Michelle Rae; Blewett, Verna Lesley

    2015-01-01

    Current patient safety policy focuses nursing on patient care goals, often overriding nurses' safety. Without understanding how nurses construct work health and safety (WHS), patient and nurse safety cannot be reconciled. Using ethnography, we examine social contexts of safety, studying 72 nurses across five Australian hospitals making decisions during patient encounters. In enacting safe practice, nurses used "frames" built from their contextual experiences to guide their behavior. Frames are produced by nurses, and they structure how nurses make sense of their work. Using thematic analysis, we identify four frames that inform nurses' decisions about WHS: (a) communicating builds knowledge, (b) experiencing situations guides decisions, (c) adapting procedures streamlines work, and (d) team working promotes safe working. Nurses' frames question current policy and practice by challenging how nurses' safety is positioned relative to patient safety. Recognizing these frames can assist the design and implementation of effective WHS management.

  15. All aboard the Safety Train(ing)!

    CERN Multimedia

    Rosaria Marraffino

    2015-01-01

    Would you like to influence CERN’s safety courses? Do you want to help build better training courses? If your answer is yes to one or both of these questions: now is the time! The Safety Training section is looking for volunteers from the whole CERN community to test new courses before they go online for all members of the personnel.    The Safety Training section is redesigning the CERN e-learning package in order to adopt a more educational approach and to make the courses a more enjoyable experience. The section is now calling for volunteers. “We know we can do much more with testers’ help and feedback,” explains Christoph Balle, Safety Training section leader. “By having the end users actively involved in the process, we’ll achieve our goal of communicating safety in the best possible way. As the volunteers will play an active role in the development of the courses, they will be providing a service to the whole community.&am...

  16. Curiosity Questions

    Science.gov (United States)

    Nelsen, Jane; DeLorenzo, Chip

    2010-01-01

    Have you ever found yourself lecturing a child, with the best of intentions, in an attempt to help him or her learn a lesson or process a situation in a manner that you feel will be productive? Curiosity questions, which the authors also call What and How questions, help children process an experience, event, or natural consequence so that they…

  17. What Food is to be Kept Safe and for Whom? Food-Safety Governance in an Unsafe Food System

    Directory of Open Access Journals (Sweden)

    Martha McMahon

    2013-10-01

    Full Text Available This paper argues that discussion of new food-safety governance should be framed by the realization that the dominant food system within which food-safety governance is designed to makes food safe is itself a structural and systemic sources of food un-safety, poor health and a future of food insecurity for many. For some, an appropriate policy response lies in addressing the connections between the food system and diseases such as heart disease, obesity and diabetes. For others it means subsuming food-safety governance within food security governance. For yet others, safe food implies food sovereignty governance and the primacy of a climate change resilient food system. Conventional approaches to food-safety governance are typically framed within a liability model of responsibility that has limited usefulness for addressing institutional, structural or systemic sources of harm such as those critics increasingly attribute to the dominant food system and which are not amenable to remedy by food-safety governance as it is widely understood. One cannot identify critical hazard points where risk is to be managed. These are food-system safety challenges. Because food-safety governance is so deeply political there needs to be greater attention to issues of governance rather than the more usual focus on the technologies of food-safety. Feminist political theorists have much to contribute to re-thinking food-safety governance in the context of diversity and the complexities of power. One could usefully start with the simple questions, “what food is to be kept-safe, for whom and who is the subject of food-safety governance in a post-Westphalian political economic order?” These questions can help unpack both the narrow parochialism and the misleading universalism of food-safety talk. This paper answers that neither the citizens of a particular state (or network of states nor the falsely universalizing identity of ‘the consumer’ are adequate answers

  18. Effects and practices on nuclear safety convention promoting nuclear safety in China

    International Nuclear Information System (INIS)

    Zhang Wei; Cheng Jianxiu; Chen Maosong

    2010-01-01

    By the means of peer review and self-review, the Contracting Parties are reviewed on obligations under the Convention. In order to implementation these, the State Department established the specific group, under the efforts of departments together, the China fulfilled the obligations successfully. The international society affirmed the good practices on nuclear safety in China, at the same time, they pointed out some fields that China pay close attention to. On the basis of analyzing questions, we point out some aspects which are combined the common questions put forward by the International Atomic Energy Agency on the 4th reviewing meeting that the Chinese government pay close attention to on the next review meeting. Meanwhile, we also put forward some suggestions on how to do better on fulfilling the convention. (authors)

  19. System Design and the Safety Basis

    International Nuclear Information System (INIS)

    Ellingson, Darrel

    2008-01-01

    The objective of this paper is to present the Bechtel Jacobs Company, LLC (BJC) Lessons Learned for system design as it relates to safety basis documentation. BJC has had to reconcile incomplete or outdated system description information with current facility safety basis for a number of situations in recent months. This paper has relevance in multiple topical areas including documented safety analysis, decontamination and decommissioning (D and D), safety basis (SB) implementation, safety and design integration, potential inadequacy of the safety analysis (PISA), technical safety requirements (TSR), and unreviewed safety questions. BJC learned that nuclear safety compliance relies on adequate and well documented system design information. A number of PIS As and TSR violations occurred due to inadequate or erroneous system design information. As a corrective action, BJC assessed the occurrences caused by systems design-safety basis interface problems. Safety systems reviewed included the Molten Salt Reactor Experiment (MSRE) Fluorination System, K-1065 fire alarm system, and the K-25 Radiation Criticality Accident Alarm System. The conclusion was that an inadequate knowledge of system design could result in continuous non-compliance issues relating to nuclear safety. This was especially true with older facilities that lacked current as-built drawings coupled with the loss of 'historical knowledge' as personnel retired or moved on in their careers. Walkdown of systems and the updating of drawings are imperative for nuclear safety compliance. System design integration with safety basis has relevance in the Department of Energy (DOE) complex. This paper presents the BJC Lessons Learned in this area. It will be of benefit to DOE contractors that manage and operate an aging population of nuclear facilities

  20. CRITICALITY SAFETY LIMIT EVALUATION PROGRAM (CSLEP's) AND QUICK SCREENS: ANSWERS TO EXPEDITED PROCESSING LEGACY CRITICALITY SAFETY LIMITS AND EVALUATIONS

    International Nuclear Information System (INIS)

    TOFFER, H.

    2006-01-01

    Since the end of the cold war, the need for operating weapons production facilities has faded. Criticality Safety Limits and controls supporting production modes in these facilities became outdated and furthermore lacked the procedure based rigor dictated by present day requirements. In the past, in many instances, the formalism of present day criticality safety evaluations was not applied. Some of the safety evaluations amounted to a paragraph in a notebook with no safety basis and questionable arguments with respect to double contingency criteria. When material stabilization, clean out, and deactivation activities commenced, large numbers of these older criticality safety evaluations were uncovered with limits and controls backed up by tenuous arguments. A dilemma developed: on the one hand, cleanup activities were placed on very aggressive schedules; on the other hand, a highly structured approach to limits development was required and applied to the cleanup operations. Some creative approaches were needed to cope with the limits development process

  1. Management commitment to safety vs. employee perceived safety training and association with future injury.

    Science.gov (United States)

    Huang, Yueng-Hsiang; Verma, Santosh K; Chang, Wen-Ruey; Courtney, Theodore K; Lombardi, David A; Brennan, Melanye J; Perry, Melissa J

    2012-07-01

    The purpose of this study is to explore and examine, specific to the restaurant industry, two important constructs emerging from the safety climate literature: employee perceptions of safety training and management commitment to safety. Are these two separate constructs? Are there both individual- and shared group-level safety perceptions for these two constructs? What are the relationships between these two constructs and future injury outcomes? A total of 419 employees from 34 limited-service restaurants participated in a prospective cohort study. Employees' perceptions of management commitment to safety and safety training and demographic variables were collected at the baseline. The survey questions were made available in three languages: English, Spanish, and Portuguese. For the following 12 weeks, participants reported their injury experience and weekly work hours. A multivariate negative binomial generalized estimating equation model with compound symmetry covariance structure was used to assess the association between the rate of self-reported injuries and measures of safety perceptions. Even though results showed that the correlation between employees'perceived safety training and management commitment to safety was high, confirmatory factor analysis of measurement models showed that two separate factors fit the model better than as two dimensions of a single factor. Homogeneity tests showed that there was a shared perception of the factor of management commitment to safety for the restaurant workers but there was no consistent perception among them for the factor of perceived safety training. Both individual employees'perceived management commitment to safety and perceptions of safety training can predict employees' subsequent injuries above and beyond demographic variables. However, there was no significant relationship between future injury and employees' shared perception of management commitment to safety. Further, our results suggest that the

  2. Safety culture and accident analysis-A socio-management approach based on organizational safety social capital

    Energy Technology Data Exchange (ETDEWEB)

    Rao, Suman [Risk Analyst (India)]. E-mail: sumanashokrao@yahoo.co.in

    2007-04-11

    One of the biggest challenges for organizations in today's competitive business environment is to create and preserve a self-sustaining safety culture. Typically, Key drivers of safety culture in many organizations are regulation, audits, safety training, various types of employee exhortations to comply with safety norms, etc. However, less evident factors like networking relationships and social trust amongst employees, as also extended networking relationships and social trust of organizations with external stakeholders like government, suppliers, regulators, etc., which constitute the safety social capital in the Organization-seem to also influence the sustenance of organizational safety culture. Can erosion in safety social capital cause deterioration in safety culture and contribute to accidents? If so, how does it contribute? As existing accident analysis models do not provide answers to these questions, CAMSoC (Curtailing Accidents by Managing Social Capital), an accident analysis model, is proposed. As an illustration, five accidents: Bhopal (India), Hyatt Regency (USA), Tenerife (Canary Islands), Westray (Canada) and Exxon Valdez (USA) have been analyzed using CAMSoC. This limited cross-industry analysis provides two key socio-management insights: the biggest source of motivation that causes deviant behavior leading to accidents is 'Faulty Value Systems'. The second biggest source is 'Enforceable Trust'. From a management control perspective, deterioration in safety culture and resultant accidents is more due to the 'action controls' rather than explicit 'cultural controls'. Future research directions to enhance the model's utility through layering are addressed briefly.

  3. College Rampage Renews School Safety Concerns

    Science.gov (United States)

    Maxwell, Lesli A.

    2007-01-01

    Coming just four days before the anniversary of the Columbine school shootings, the mass slayings by a student gunman at Virginia Polytechnic Institute last week revived vexing questions and raised familiar fears for educators across the country who grapple daily with ensuring the safety of their students and staffs. The April 16 killings provoked…

  4. Deep Sludge Gas Release Event Analytical Evaluation

    International Nuclear Information System (INIS)

    Sams, Terry L.

    2013-01-01

    report is to (1) present and discuss current understandings of gas retention and release mechanisms for deep sludge in U.S. Department of Energy (DOE) complex waste storage tanks; and (2) to identify viable methods/criteria for demonstrating safety relative to deep sludge gas release events (DSGRE) in the near term to support the Hanford C-Farm retrieval mission. A secondary purpose is to identify viable methods/criteria for demonstrating safety relative to DSGREs in the longer term to support the mission to retrieve waste from the Hanford Tank Farms and deliver it to the Waste Treatment and Immobilization Plant (WTP). The potential DSGRE issue resulted in the declaration of a positive Unreviewed Safety Question (USQ). C-Farm retrievals are currently proceeding under a Justification for Continued Operation (JCO) that only allows tanks 241-AN-101 and 241-AN-106 sludge levels of 192 inches and 195 inches, respectively. C-Farm retrievals need deeper sludge levels (approximately 310 inches in 241-AN-101 and approximately 250 inches in 241-AN-106). This effort is to provide analytical data and justification to continue retrievals in a safe and efficient manner

  5. Safety culture and quality management of Kartini research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Syarip [Yogyakarta Nuclear Research Centre, Yogyakarta (Indonesia); Hauptmanns, Ulrich [Department of Plant Design and Safety, Otto-Von-Guericke-University, Magdeburg (Germany)

    1999-10-01

    The evaluation for assessing the safety culture and quality of safety management of Kartini research reactor is presented. The method is based on the concept of management control of safety (audit) as well as by using the developed method i.e. the questionnaires concerning areas of relevance which have to be answered with value statements. There are seven statements or qualifiers in answering the questions. Since such statements are vague, they are represented by fuzzy numbers. The weaknesses can be identified from the different areas contemplated. The evaluation result show that the quality of safety management of Kartini research reactor is globally rated as 'Average'. The operator behavior in the implementation of 'safety culture' concept is found as a weakness, therefore this area should be improved. (author)

  6. Guide for understanding and evaluation of safety culture

    International Nuclear Information System (INIS)

    2008-01-01

    This report was the guide of understanding and evaluation of safety culture. Operator's activities for enhancement of safety culture in nuclear installations became an object of safety regulation in the management system. Evaluation of operator's activities (including top management's involvement) to prevent degradation of safety culture and organization climate in daily works needed understanding of safety culture and diversity of operator's activities. This guide was prepared to check indications of degradation of safety culture and organization climate in operator's activities in daily works and encourage operator's activities to enhance safety culture improvement and good practice. Comprehensive evaluation of operator's activities to prevent degradation of safety culture and organization climate would be performed from the standpoints of 14 safety culture elements such as top management commitment, clear plan and implementation of upper manager, measures to avoid wrong decision making, questioning attitude, reporting culture, good communications, accountability and openness, compliance, learning system, activities to prevent accidents or incidents beforehand, self-assessment or third party evaluation, work management, change management and attitudes/motivation. Element-wise examples and targets for evaluation were attached with evaluation check tables. (T. Tanaka)

  7. International exchange of safety and licensing information

    International Nuclear Information System (INIS)

    Lafleur, J.D. Jr.; Hauber, R.D.; Chenier, D.M.

    1977-01-01

    A network of formal and informal bilateral arrangements for the exchange of nuclear safety information is being established by the U.S. Nuclear Regulatory Commission. For developing countries, such arrangements can provide ready access to the extensive, fully documented safety analyses and safety research results that NRC has accumulated. NRC has been receiving foreign visitors at a rate of about 500 per year, largely for discussions of safety and licensing questions related to light water reactors. Exchanges also are taking place on the safety of advanced reactors. A special interest of the NRC is in providing for reciprocal communicaion, at the earliest possible time, of important problems, decisions and other actions on nuclear safety matters. For example, it is essential that a newly-discovered problem in a nuclear reactor be brought immediately to the attention of other governments which are responsible for the safety of similar reactors. Definite progress has been made in the U.S. Freedom of Information Act. Certain exchanges have taken place on this basis. Experience in the establishment and operation of NRC's bilateral exchange arrangements is summarized. A typical exchange with the regulatory authority of country building its first power reactor is described

  8. THE EXPLICIT COMPREHENSION-STRATEGY INSTRUCTION: QUESTION-ANSWER RELATIONSHIP VS SELF-QUESTIONING

    Directory of Open Access Journals (Sweden)

    Lalu Thohir

    2017-12-01

    Full Text Available This study was aimed at examining and comparing the effectiveness of the Question-Answer Relationship (QAR and Self-Questioning (SQ strategies in improving the reading ability of the undergraduate students. This study was a quasi-experimental study in which two out of three classes of the third semester students at English department of Mataram University were selected randomly to receive either QAR strategy or SQ strategy instructions for ten weekly meetings. The findings of pre- and posttest with multiple-choice questions revealed that both comprehension strategies were effective in improving the undergraduate students‘ reading ability. The findings from the posttest with multiple-choice questions indicated the students who received SQ strategy instruction scored significantly higher than those students who received QAR strategy instruction. On the other hand, the students who received QAR strategy instruction scored slightly higher than those students who received SQ strategy instruction in the posttest with open-ended questions.

  9. Some safety considerations in laser-controlled thermonuclear reactors. Final report

    International Nuclear Information System (INIS)

    Botts, T.E.; Breton, D.; Chan, C.K.; Levy, S.I.; Sehnert, M.; Ullman, A.Z.

    1978-07-01

    A major objective of this study was to identify potential safety questions for laser controlled thermonuclear reactors. From the safety viewpoint, it does not appear that the actual laser controlled thermonuclear reactor conceptual designs present hazards very different than those of magnetically confined fusion reactors. Some aspects seem beneficial, such as small lithium inventories, and the absence of cryogenic devices, while other aspects are new, for example the explosion of pressure vessels and laser hazards themselves. Major aspects considered in this report include: (a) general safety considerations, (b) tritium inventories, (c) system behavior during loss of flow accidents, and (d) safety considerations of laser related penetrations

  10. Safety oriented LWR research. Annual report 1990

    International Nuclear Information System (INIS)

    1991-07-01

    The contributions describe phenomenons of severe fuel damage and aspects of core meltdown accidents. These accidents deal with aerosol behaviour and ventilation systems and the methods for assessing and reducing the radiological concequences of nuclear accidents. Other contributions describe selected questions of safety of HCLWR type reactors. (DG)

  11. 78 FR 17939 - Announcement of Funding Awards; Capital Fund Safety and Security Grants; Fiscal Year 2012

    Science.gov (United States)

    2013-03-25

    ...; Capital Fund Safety and Security Grants; Fiscal Year 2012 AGENCY: Office of the Assistant Secretary for... availability of the Safety and Security funds with PIH Notice 2012-38 (Notice), which was issued September 7... Fund Safety and Security grant program. FOR FURTHER INFORMATION CONTACT: For questions concerning the...

  12. 78 FR 56728 - Announcement of Funding Awards; Capital Fund Safety and Security Grants; Fiscal Year 2013

    Science.gov (United States)

    2013-09-13

    ...; Capital Fund Safety and Security Grants; Fiscal Year 2013 AGENCY: Office of the Assistant Secretary for... availability of the Safety and Security funds with PIH Notice 2013-10 (Notice), which was issued May 3, 2013... Fund Safety and Security grant program. FOR FURTHER INFORMATION CONTACT: For questions concerning the...

  13. 77 FR 14970 - Safety Zones; Sellwood Bridge Project, Willamette River; Portland, OR

    Science.gov (United States)

    2012-03-14

    ... upriver and downriver of the existing Sellwood Bridge, inward 375 feet from the Western side shoreline... times. These safety zones will ensure the safety of all vessels and crew that are working and transiting... against small entities that question or complain about this rule or any policy or action of the Coast...

  14. Improvement of Managers’ Safety Knowledge through Scientifically Reasonable Interviews

    Directory of Open Access Journals (Sweden)

    Paas Õnnela

    2015-11-01

    Full Text Available The safety management system has been analysed in 16 Estonian enterprises using the MISHA method (Method for Industrial Safety and Health Activity Assessment. The factor analysis (principal component analysis and varimax with Kaiser analysis has been implemented for the interpretation of the results on safety performance at the enterprises implementing OHSAS 18001 and the ones that do not implement OHSAS 18001. The division of the safety areas into four parts for a better understanding of the safety level and its improvement possibilities has been proven through the statistical analysis. The connections between the questions aimed to clarify the safety level and performance at the enterprises have been set based on the statistics. New learning package “training through the questionnaires” has been worked out in the current paper for the top and middle-level managers to improve their safety knowledge, where the MISHA questionnaire has been taken as the basis.

  15. Plan of Nordic research in nuclear safety 1994-97

    International Nuclear Information System (INIS)

    1993-04-01

    A new four-year Nordic research programme in the field of nuclear safety and radiation protection is to start in 1994 as a followup of several preceding Nordic programmes. It will include seven projects and a joint coordination function. The programme is intended to sustain a common understanding among safety authorities in the Nordic countries with respect to reactor safety and radiation protection. It mainly deals with questions that are actual within the Nordic region, but it may also include problems of concern to its eastern neighbours. Two of the projects deal with reactor safety, and one with radioactive waste. The other four projects are on environmental aspects: two of them deal with radioecology, and two with questions related to emergency preparedness. The programme is managed by the Nordic Committee for Safety Research, NKS, consisting of representatives from regulatory authorities, research bodies, and industry. Basic financing is provided by one consortium member from each of the five Nordic countries, whereby an annual budget of approximately 8 million Danish Kroner will be provided. Additional financing comes from sponsors interested in the programme as well as from those organizations taking part in the project work. Definite project plans are to be elaborated within the more general frames described in the present outline. The flexibility of the programme is enhanced by limiting the duration of individual activities to one or two years. This will make it possible to adjust the programme to actual needs in the Nordic countries. (au)

  16. The emphasis is on reactor safety research

    International Nuclear Information System (INIS)

    Anon.

    1982-01-01

    For the second time the Association for Reactor Safety mbH (GRS), Koeln, organised on behalf of the BMFT the conference 'Reactor safety research'. About 400 visitors took part. The public who were interested were given a review of the activities which are being undertaken by the BMFT in the programme 'Research and safety of light-water reactors'. The series of conference papers initiated by the BMFT is to be developed into a permanent information source which will be of interest to those working on nuclear questions such as official quarters, industry and high schools, and experts who have to give judgements. The most important statements by various research groups in industry, high schools and also associations of experts, are summarised. (orig.) [de

  17. Fall-Prone Older People's Attitudes towards the Use of Virtual Reality Technology for Fall Prevention.

    Science.gov (United States)

    Dockx, Kim; Alcock, Lisa; Bekkers, Esther; Ginis, Pieter; Reelick, Miriam; Pelosin, Elisa; Lagravinese, Giovanna; Hausdorff, Jeffrey M; Mirelman, Anat; Rochester, Lynn; Nieuwboer, Alice

    2017-01-01

    Virtual reality (VR) technology is a relatively new rehabilitation tool that can deliver a combination of cognitive and motor training for fall prevention. The attitudes of older people to such training are currently unclear. This study aimed to investigate: (1) the attitudes of fall-prone older people towards fall prevention exercise with and without VR; (2) attitudinal changes after intervention with and without VR; and (3) user satisfaction following fall prevention exercise with and without VR. A total of 281 fall-prone older people were randomly assigned to an experimental group receiving treadmill training augmented by VR (TT+VR, n = 144) or a control group receiving treadmill training alone (TT, n = 137). Two questionnaires were used to measure (1) attitudes towards fall prevention exercise with and without VR (AQ); and (2) user satisfaction (USQ). AQ was evaluated at baseline and after intervention. USQ was measured after intervention only. The AQ revealed that most participants had positive attitudes towards fall prevention exercise at baseline (82.2%) and after intervention (80.6%; p = 0.144). In contrast, only 53.6% were enthusiastic about fall prevention exercise with VR at baseline. These attitudes positively changed after intervention (83.1%; p < 0.001), and 99.2% indicated that they enjoyed TT+VR. Correlation analyses showed that postintervention attitudes were strongly related to user satisfaction (USQ: r = 0.503; p < 0.001). Older people's attitudes towards fall prevention exercise with VR were positively influenced by their experience. From the perspective of the user, VR is an attractive training mode, and thus improving service provision for older people is important. © 2017 S. Karger AG, Basel.

  18. A study on safety climate at nuclear power plants

    International Nuclear Information System (INIS)

    Fukui, Hirokazu; Yoshida, Michio; Yoshiyama, Naohiro

    2001-01-01

    In the current study, we define safety climate as an organizational environment that induces members of the organization to give consideration to safety or take safety actions. It is of utmost importance that people holding managerial positions in an organization have a good understanding of the characteristics of the safety climate of the organization and implement safety promotion activities effectively. In the current research, we studied the rating scales and the characteristics of a safety climate. A survey was conducted, targeting technical engineers who belong to the three power stations of Kansai Electric Power Co., Inc. The questionnaire mainly consisted of questions concerning safety measures taken by individuals and questions concerning safety measures taken by the organization, to which the individuals belong. As a result of a factor analysis of the responses, we extracted five factors, namely, 'confidence in knowledge and skill', attitude of supervisors,' 'safety education in workplace', 'clarity of tasks' and 'safety confirmation/report'. In studying the rating scales of the safety climate, we selected five items from each of the above five factors, and used the total scores of the ratings of the five items as scores of each factor. Then, we examined the correlation between scores of personal factors and scores of organizational environment factors. We treated the scores of safety confirmation/report' and 'confidence in knowledge and skill', which are personal factors, as criterion variables, and the scores of 'attitude of supervisors', 'safety education in workplace' and 'clarity of tasks', which are organizational environment factors, as predictor variables. As a result, we found that levels of 'safety confirmation/report' and 'confidence in knowledge and skill' can be deduced from the scores of 'attitude of supervisors', 'safety education in workplace' and 'clarity of tasks.' Hence, we have decided to use these three organizational environment

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

    OpenAIRE

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

    2015-01-01

    Background Small manufacturing businesses often lack important safety programs. Many reasons have been set forth on why this has remained a persistent problem. Methods The National Machine Guarding Program (NMGP) was a nationwide intervention conducted in partnership with two workers' compensation insurers. Insurance safety consultants collected baseline data in 221 business using a 33?question safety management audit. Audits were completed during an interview with the business owner or manag...

  20. Assessment of Safety Culture

    International Nuclear Information System (INIS)

    Bilic Zabric, T.; Kavsek, D.

    2006-01-01

    A strong safety culture leads to more effective conduct of work and a sense of accountability among managers and employees, who should be given the opportunity to expand skills by training. The resources expended would thus result in tangible improvements in working practices and skills, which encourage further improvement of safety culture. In promoting an improved safety culture, NEK has emphasized both national and organizational culture with an appropriate balance of behavioural sciences and quality management systems approaches. In recent years there has been particular emphasis put on an increasing awareness of the contribution that human behavioural sciences can make to develop good safety practices. The purpose of an assessment of safety culture is to increase the awareness of the present culture, to serve as a basis for improvement and to keep track of the effects of change or improvement over a longer period of time. There is, however, no single approach that is suitable for all purposes and which can measure, simultaneously, all the intangible aspects of safety culture, i.e. the norms, values, beliefs, attitudes or the behaviours reflecting the culture. Various methods have their strengths and weaknesses. To prevent significant performance problems, self-assessment is used. Self-assessment is the process of identifying opportunities for improvement actively or, in some cases, weaknesses that could cause more serious errors or events. Self-assessments are an important input to the corrective action programme. NEK has developed questionnaires for safety culture self-assessment to obtain information that is representative of the whole organization. Questionnaires ensure a greater degree of anonymity, and create a less stressful situation for the respondent. Answers to questions represent the more apparent and conscious values and attitudes of the respondent. NEK proactively co-operates with WANO, INPO, IAEA in the areas of Safety Culture and Human

  1. West Valley Reprocessing Plant. Safety analysis report, supplement 21

    International Nuclear Information System (INIS)

    1976-01-01

    Supplement No. 21 contains responses to USNRC questions on quality assurance contained in USNRC letter to NFS dated January 22, 1976, revised pages for the safety analysis report, and Appendix IX ''Quality Assurance Manual--West Valley Construction Projects.''

  2. 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.

  3. Patient safety: break the silence.

    Science.gov (United States)

    Johnson, Hope L; Kimsey, Diane

    2012-05-01

    A culture of patient safety requires commitment and full participation from all staff members. In 2008, results of a culture of patient safety survey conducted in the perioperative division of the Lehigh Valley Health Network in Pennsylvania revealed a lack of patient-centered focus, teamwork, and positive communication. As a result, perioperative leaders assembled a multidisciplinary team that designed a safety training program focusing on Crew Resource Management, TeamSTEPPS, and communication techniques. The team used video vignettes and an audience response system to engage learners and promote participation. Topics included using preprocedural briefings and postprocedural debriefings, conflict resolution, and assertiveness techniques. Postcourse evaluations showed that the majority of respondents believed they were better able to question the decisions or actions of someone with more authority. The facility has experienced a marked decrease in the number of incidents requiring a root cause analysis since the program was conducted. Copyright © 2012 AORN, Inc. Published by Elsevier Inc. All rights reserved.

  4. Asking Questions in Academia

    DEFF Research Database (Denmark)

    Hansen, Annette Skovsted

    2014-01-01

    Motivation for the activity In academia the most important skill is to ask academically relevant and sound questions. This is not easy and students need to practice asking questions orally and in writing before they write research papers.......Motivation for the activity In academia the most important skill is to ask academically relevant and sound questions. This is not easy and students need to practice asking questions orally and in writing before they write research papers....

  5. Principles and Practices of Occupational Safety and Health: Student Manual: Booklet One.

    Science.gov (United States)

    Occupational Safety and Health Administration, Washington, DC.

    The manual is the first of six student manuals for use in a course on occupational health and safety for supervisory personnel. The manual contains lessons 1-3 of the 15 consecutively-numbered lessons, each of which contains study questions (and answers) interwoven with the text and review questions at the end of each section. Lesson 1 (three…

  6. Principles and Practices of Occupational Safety and Health: Student Manual: Booklet Five.

    Science.gov (United States)

    Occupational Safety and Health Administration, Washington, DC.

    The manual is the fifth of six student manuals for use in a course on occupational health and safety for supervisory personnel. The manual contains lessons 14 and 15 of the 15 consecutively-numbered lessons, each of which contains study questions (and answers) interwoven with the text and review questions at the end of each section. Lesson 14…

  7. 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

  8. Assessment of regulations set up under public law concerning questions of safety technology

    International Nuclear Information System (INIS)

    Steiff, A.; Althaus, W.; Dietz, B.; Gross, H.J.; Stasiczek, M.; Salzwedel, J.; Reinhardt, M.

    1992-02-01

    A goal of the preliminary study was to assess the need for a data-processing system, to analyze the goals of such a system, to conceptualize it and examine possibilities for implementing it and to do a cost-benefit analysis of it. It serves as a means of assistance for - licensing and supervisory authorities, - the manufacturers and operators of plants, - the control institutions, - the communes, the governments of the Laender and the federal government, - trade associations and professional associations, - employers' organizations and employees' organizations in their efforts to solve problems and carry out tasks regarding safety technology. Such problems arise during the planning, construction, operation, alteration, closure and removal of plants as well as during the transport and storing of materials and goods. (orig./DG) [de

  9. A summary description of the flammable gas tank safety program

    International Nuclear Information System (INIS)

    Johnson, G.D.; Sherwood, D.J.

    1994-10-01

    Radioactive liquid waste may produce hydrogen as result of the interaction of gamma radiation and water. If the waste contains organic chelating agents, additional hydrogen as well as nitrous oxide and ammonia may be produced by thermal and radiolytic decomposition of these organics. Several high-level radioactive liquid waste storage tanks, located underground at the Hanford Site in Washington State, are on a Flammable Gas Watch List. Some contain waste that produces and retains gases until large quantities of gas are released rapidly to the tank vapor space. Tanks nearly-filled to capacity have relatively little vapor space; therefore if the waste suddenly releases a large amount of hydrogen and nitrous oxide, a flammable gas mixture could result. The most notable example of a Hanford waste tank with a flammable gas problem is tank 241-SY-101. Upon occasion waste stored in this tank has released enough flammable gas to burn if an ignition source had been present inside of the tank. Several, other Hanford waste tanks exhibit similar behavior although to a lesser magnitude. Because this behavior was hot adequately-addressed in safety analysis reports for the Hanford Tank Farms, an unreviewed safety question was declared, and in 1990 the Flammable Gas Tank Safety Program was established to address this problem. The purposes of the program are a follows: (1) Provide safety documents to fill gaps in the safety analysis reports, and (2) Resolve the safety issue by acquiring knowledge about gas retention and release from radioactive liquid waste and developing mitigation technology. This document provides the general logic and work activities required to resolve the unreviewed safety question and the safety issue of flammable gas mixtures in radioactive liquid waste storage tanks

  10. Use of agent based simulation for traffic safety assessment

    CSIR Research Space (South Africa)

    Conradie, Dirk CU

    2008-07-01

    Full Text Available This paper describes the development of an agent based Computational Building Simulation (CBS) tool, termed KRONOS that is being used to work on advanced research questions such as traffic safety assessment and user behaviour in buildings...

  11. Improving Student Question Classification

    Science.gov (United States)

    Heiner, Cecily; Zachary, Joseph L.

    2009-01-01

    Students in introductory programming classes often articulate their questions and information needs incompletely. Consequently, the automatic classification of student questions to provide automated tutorial responses is a challenging problem. This paper analyzes 411 questions from an introductory Java programming course by reducing the natural…

  12. Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. National Report from Norway

    International Nuclear Information System (INIS)

    2006-05-01

    This report is the Norwegian report to the second review meeting to the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. The comments, questions and remarks given to Norway's initial national report and Norway's presentation given at the first review meeting have been incorporated in this report. The second report is a full revision of the first report. This report concludes that Norway meets the obligations of the Joint Convention. However, Norwegian authorities will aim for development in the waste management policy and Norway will continue to improve its existing systems to further enhance safety, in line with the aims of the Joint Convention

  13. A cross-cultural survey of residents' perceived barriers in questioning/challenging authority.

    Science.gov (United States)

    Kobayashi, H; Pian-Smith, M; Sato, M; Sawa, R; Takeshita, T; Raemer, D

    2006-08-01

    To identify perceived barriers to residents' questioning or challenging their seniors, to determine how these barriers affect decisions, and to assess how these barriers differ across cultures. A written questionnaire was administered to residents in teaching hospitals in the US and Japan to assess factors affecting residents' willingness to question or challenge their superiors. The responses were analyzed for statistical significance of differences between the two cultures and to determine the importance of issues affecting decisions. Questionnaires were completed by 175 US and 65 Japanese residents, with an overall response rate of 71%. Trainees from both countries believe that questioning and challenging contribute to safety. The perceived importance of specific beliefs about the workplace differed across cultures in seven out of 22 questions. Residents' decisions to make a challenge were related to the relationships and perceived response of the superiors. There was no statistical difference between the US and Japanese residents in terms of the threshold for challenging their seniors. We have identified attributes of residents' beliefs of communication, including several cross-cultural differences in the importance of values and issues affecting one's decision to question or challenge. In contrast, there was no difference in the threshold for challenging seniors by the Japanese and US residents studied. Changes in organizational and professional culture may be as important, if not more so, than national culture to encourage "speaking up". Residents should be encouraged to overcome barriers to challenging, and training programs should foster improved relationships and communication between trainers and trainees.

  14. Contrast media. Safety issues and ESUR guidelines. 2. rev. ed.

    Energy Technology Data Exchange (ETDEWEB)

    Thomsen, Henrik S. [Copenhagen University Hospital, Herlev (Denmark). Dept. of Diagnostic Radiology; Copenhagen Univ., Herlev (Denmark). Dept. of Diagnostic Sciences; Webb, Judith A.W. (eds.) [St. Bartholomew' s Hospital London Univ. (United Kingdom). Dept. of Radiology

    2009-07-01

    In 1994 the European Society of Urogenital Radiology (ESUR) set up a committee to consider the safety of contrast media used for diagnostic imaging. Subsequently the committee questioned members, reviewed the literature, proposed guidelines and discussed these proposals with participants at the annual symposia of the society. The end result of this work was the successful first edition of this book, published in 2006. This second edition not only updates the previous edition, but also contains some completely new chapters, for example on gadolinium-based contrast agents, meta-analyses in contrast media research and various regulatory issues. Comprehensive consideration is given to the many different safety issues relating to iodinated, MR, ultrasound and barium contrast media. The text includes chapters on both acute and delayed non-renal adverse reactions and on renal adverse reactions. All those questions frequently raised in radiological practice are addressed, and the well-known ESUR guidelines on contrast media are included. This book, presented in a handy, easy to use format, provides an invaluable, unique and unparalleled source of information on the safety issues relating to contrast media. (orig.)

  15. Contrast media. Safety issues and ESUR guidelines. 2. rev. ed.

    International Nuclear Information System (INIS)

    Thomsen, Henrik S.; Copenhagen Univ., Herlev; Webb, Judith A.W.

    2009-01-01

    In 1994 the European Society of Urogenital Radiology (ESUR) set up a committee to consider the safety of contrast media used for diagnostic imaging. Subsequently the committee questioned members, reviewed the literature, proposed guidelines and discussed these proposals with participants at the annual symposia of the society. The end result of this work was the successful first edition of this book, published in 2006. This second edition not only updates the previous edition, but also contains some completely new chapters, for example on gadolinium-based contrast agents, meta-analyses in contrast media research and various regulatory issues. Comprehensive consideration is given to the many different safety issues relating to iodinated, MR, ultrasound and barium contrast media. The text includes chapters on both acute and delayed non-renal adverse reactions and on renal adverse reactions. All those questions frequently raised in radiological practice are addressed, and the well-known ESUR guidelines on contrast media are included. This book, presented in a handy, easy to use format, provides an invaluable, unique and unparalleled source of information on the safety issues relating to contrast media. (orig.)

  16. Implications of passive safety based on historical industrial experience

    International Nuclear Information System (INIS)

    Forsberg, C.W.

    1988-01-01

    In the past decade, there have been multiple proposals for applying different technologies to achieve passively safe light water reactors (LWRs). A key question for all such concepts is, ''What are the gains in safety, costs, and reliability for passive safety systems.'' Using several types of historical data, estimates have been made of gains from passive safety and operating systems, which are independent of technology. Proposals for passive safety in reactors usually have three characteristics: (1) Passive systems with no moving mechanical parts, (2) systems with far fewer components and (3) more stringent design criteria for safety-related and process systems. Each characteristic reduces the potential for an accident and may increase plant reliability. This paper addresses gains from items (1) and (2). Passive systems often allow adoption of more rigorous design criteria which would be either impossible or economically unfeasible for active systems. This important characteristic of passive safety systems cannot be easily addressed using historical industrial experience

  17. Public requirement to demonstrate safety

    International Nuclear Information System (INIS)

    Green, P.

    1991-01-01

    To many working within Government or industry, public concern over the disposal of radioactive waste is misplaced and has arisen out of an irrational and unscientific fear of technology, or even science in general. Members of the public, it is argued, are concerned because they do not understand the size of the risk in question. From the industry's point of view, the risk arising from the disposal of radioactive waste is ''negligible when compared to other everyday risks of life. Furthermore, any public exposure that may arise, either soon after closure of a facility or in the far future would comply with internationally accepted safety standards. In this context, the continuing concern over disposal of radioactive waste is viewed as evidence of the irrational and unscientific attitude of the public. The assessment and regulation of risk from waste disposal therefore is presented as a purely scientific question. Some of these issues are examined and public concern is shown not to be irrational but to be based upon legitimate questions over current waste management policy. An important question is not just ''how safe is safe, but who decides and how?''. (Author)

  18. Occupational health and safety in the Moroccan construction sites: preliminary diagnosis

    Science.gov (United States)

    Tarik, Bakeli; Adil, Hafidi Alaoui

    2018-05-01

    Managing occupational health and safety on Moroccan construction sector represents the first step for projects' success. In fact, by avoiding accidents, all the related direct and indirect costs and delays can be prevented. That leads to an important question always asked by any project manager: what are the factors responsible for accidents? How can they be avoided? Through this research, the aim is to go through these questions, to contribute in occupational health and safety principles understanding, to identify construction accidentology and risk management opportunities and to approach the case of Moroccan construction sites by an accurate diagnosis. The approach is to make researchers, managers, stakeholders and deciders aware about the criticality of construction sites health and safety situation. And, to do the first step for a scientific research project in relation with health and safety in the Moroccan construction sector. For this, the paper will study the related state of art namely about construction sites accidents causation, and will focus on Reason's `Swiss cheese' model and its utilization for Moroccan construction sites health and safety diagnosis. The research will end with an estimation of an accidents fatality rate in the Moroccan construction sector and a benchmarking with the international rates. Finally, conclusions will be presented about the necessity of Occupational Health and Safety Management System (OHSMS) implementation, which shall cover all risk levels, and insure, at the same time, that the necessary defenses against accidents are on place.

  19. Guided Discovery with Socratic Questioning

    Directory of Open Access Journals (Sweden)

    M. Hakan Türkçapar

    2015-04-01

    Full Text Available “The Socratic method” is a way of teaching philosophical thinking and knowledge by asking questions. It was first used by in ancient times by the Greek philosopher Socrates who taught his followers by asking questions; these conversations between them are known as “Socratic dialogues”. In this methodology, no new knowledge is taught to the individual; rather, the individual is guided to remember and rediscover what was formerly known through this process. The main method used in cognitive therapy is guided discovery. There are various methods of guided discovery in cognitive therapy. The form of verbal exchange between the therapist and client which is used during the process of cognitive behavioral therapy is known as “socratic questioning”. In this method the goal is to make the client rediscover, with a series of questions, a piece of knowledge which he could otherwise know but is not presently conscious of. The Socratic Questioning consists of several steps, including: identifying the problem by listening to the client and making reflections, finding alternatives by examining and evaluating, reidentification by using the newly rediscovered information and questioning the old distorted belief, and reaching a new conclusion and applying it. Question types used during these procedures are: questions for collecting information, questions revealing meanings, questions revealing beliefs, questions about behaviours during similar past experiences, analytic questions and analytic synthesis questions. In order to make the patient feel understood, it is important to be empathetic and summarize the problem during the interview. In this text, steps of Socratic Questioning-Guided Discovery will be reviewed with sample dialogues provided for each step. [JCBPR 2015; 4(1.000: 47-53

  20. International conference on the strengthening of nuclear safety in Eastern Europe. Keynote papers. Regulatory aspects of NPP safety, status of safety improvements, status of safety analysis report

    International Nuclear Information System (INIS)

    1999-06-01

    The Objective of the Conference was to assess the past decade of nuclear safety efforts in countries operating WWER and RBMK nuclear reactors and to address remaining safety issues which require further work. A particular focus of the Conference was on international co-operation and assistance and where such efforts should be focused in the future. All Eastern European countries that operate RBMK or WWER reactors participated in the Conference, and presented papers on three key areas of nuclear safety: Regulatory Aspects of Nuclear Power Plant Safety; Status of Safety Improvements; and Status of Safety Analysis Reports. In addition, representatives from 18 additional countries that provide financial and/or technical assistance and co-operation in the area of WWER and RBMK safety offered the most extensive commentary. Key international (IAEA, World Association of Nuclear Operators, the Nuclear Energy Agency, the G-24 NUSAC, the European Commission, and the EBRD) organizations that provide nuclear safety assistance for WWER and RBMK reactors also made presentations. There is no question that considerable progress on nuclear safety has been made in Eastern Europe. Special mention should be made of successful efforts to strengthen the independence and technical competence of the nuclear regulatory authorities. Efforts should now concentrate on improving the depth and scope of the technical abilities of the regulatory authorities. More attention by governments is needed to ensure that the regulatory authorities have the financial resources and enforcement authority to fully execute their missions. In respect to the operators of the nuclear power plants, they have demonstrated clear progress in operational safety improvements. Significant additional efforts are required to maintain and enhance an effective safety culture. Design safety improvement programmes are in place in all countries. Implementation of these programmes has varied and is particularly affected by

  1. VERIFICATION OF THE FOOD SAFETY MANAGEMENT SYSTEM IN DEEP FROZEN FOOD PRODUCTION PLANT

    Directory of Open Access Journals (Sweden)

    Peter Zajác

    2010-07-01

    Full Text Available In work is presented verification of food safety management system of deep frozen food. Main emphasis is on creating set of verification questions within articles of standard STN EN ISO 22000:2006 and on searching of effectiveness in food safety management system. Information were acquired from scientific literature sources and they pointed out importance of implementation and upkeep of effective food safety management system. doi:10.5219/28

  2. Epistemology: 5 Questions

    DEFF Research Database (Denmark)

    Epistemology: 5 Questions is a collection of short interviews based on 5 questions presented to some of the most influential and prominent scholars in epistemology. We hear their views on epistemology with particular emphasis on the intersection between mainstream and formal approaches to the field...

  3. Donor's understanding of the definition of sex as applied to predonation screening questions.

    Science.gov (United States)

    O'Brien, S F; Ram, S S; Yi, Q-L; Goldman, M

    2008-05-01

    Predonation screening questions about sexual risk factors should provide an extra layer of safety from recently acquired infections that may be too early to be detected by testing. Donors are required to read a definition of sex as it applies to predonation screening questions each time they come to donate, but how well donors apply such definitions has not been evaluated. We aimed to determine how donors define sex when answering screening questions. In total, 1297 whole blood donors were asked in a private interview to select from a list of sexual activities which ones they believed were being asked about in sexual background questions. Donors' definitions were coded as under-inclusive, correct or over-inclusive in relation to the blood services' definition. Qualitative interviews were carried out with 21 donors to understand reasoning behind definitions. Most donors had an over-inclusive definition (58.7%) or the correct definition (31.9%). Of the 9.4% of donors who had an under-inclusive definition, 95% included both vaginal and anal sex, but not oral sex. About 9% in each group were first-time donors (P > 0.05) who had never read the definition. The qualitative interviews indicated that donors reason their definition based on their own concept of transmissible disease risk. Donors apply a range of definitions of sex when answering questions about their sexual background. This may be due to different concepts of risk activities, and required reading of the definition has little impact.

  4. Anthropology in Agricultural Health and Safety Research and Intervention.

    Science.gov (United States)

    Arcury, Thomas

    2017-01-01

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

  5. Risk Perceptions That Effect Behavior and Attitudes in Safety Programs

    Science.gov (United States)

    2004-01-01

    Turner, B.A. (1978), Man-made Disasters. London, Wykeham. Van Manen , Max. 1990. Reasearching lived experience: Human Science for an Action Sensitive Pedagogy. New York: State University of New York. ...question guided the study: (1) what factors determine a successful safety program? METHOD In my approach I used Phenomenological inquiry...method employed tried to capture the “essence” of lived experiences, which may have an impact on aviation safety. In Max Van Manen’s book

  6. [Food safety of GMOs].

    Science.gov (United States)

    Joudrier, P

    2009-01-01

    In this presentation, we review the complexity of the different biological events which occur during life cell cycles. Indeed transgenesis is not an unknown event for cells. In the second part of this article, the complex and complete evaluation process destined to assure the food safety of GMOs, before they are released on the market, is describd. Some ansers to questions frequently asked about the GMOs are given. It is concludedthat GMOs are probably more safe than their conventional non-GM counterpart.

  7. Putting road safety awareness into practice

    CERN Multimedia

    2003-01-01

    To round off the series of articles and posters published as part of its road safety awareness campaign, CERN is organising two information and demonstration open days on 23 and 25 September. Can you brake in time ? Did you know that you are 21 times more at risk of being killed if you are not wearing a seat belt in the event of your car rolling over? All your questions on road safety will be answered at two special days that are being organized on 23 and 25 September. You will also be able to test your reflexes and your knowledge by taking part in demonstrations. The CERN Management attaches high priority to an improvement in safety standards on the Laboratory's roads. These two open days have been arranged to round off the road safety awareness and highway courtesy campaign which was launched last year. They are intended to provide us with an opportunity, through a more "hands-on" approach, of heightening our awareness of the risks associated with road traffic, of the legislation in force, and above all t...

  8. Occupational radiation protection. Safety guide

    International Nuclear Information System (INIS)

    2002-01-01

    Guides together reflect the current internationally accepted principles and recommended practices in occupational radiation protection, with account taken of the major changes that have occurred over the past decade. The three Safety Guides on occupational radiation protection are jointly sponsored by the IAEA and the International Labour Office. The present Safety Guide provides general guidance on the establishment of an effective radiation protection programme for occupational exposure, in accordance with the requirements of the Basic Safety Standards and appropriate for the sources of radiation likely to be encountered in the workplaces in question

  9. Occupational radiation protection. Safety guide

    International Nuclear Information System (INIS)

    2006-01-01

    Guides together reflect the current internationally accepted principles and recommended practices in occupational radiation protection, with account taken of the major changes that have occurred over the past decade. The three Safety Guides on occupational radiation protection are jointly sponsored by the IAEA and the International Labour Office. The present Safety Guide provides general guidance on the establishment of an effective radiation protection programme for occupational exposure, in accordance with the requirements of the Basic Safety Standards and appropriate for the sources of radiation likely to be encountered in the workplaces in question

  10. Occupational radiation protection. Safety guide

    International Nuclear Information System (INIS)

    1999-01-01

    Guides together reflect the current internationally accepted principles and recommended practices in occupational radiation protection, with account taken of the major changes that have occurred over the past decade. The three Safety Guides on occupational radiation protection are jointly sponsored by the IAEA and the International Labour Office. The present Safety Guide provides general guidance on the establishment of an effective radiation protection programme for occupational exposure, in accordance with the requirements of the Basic Safety Standards and appropriate for the sources of radiation likely to be encountered in the workplaces in question

  11. Occupational radiation protection. Safety guide

    International Nuclear Information System (INIS)

    2004-01-01

    Guides together reflect the current internationally accepted principles and recommended practices in occupational radiation protection, with account taken of the major changes that have occurred over the past decade. The three Safety Guides on occupational radiation protection are jointly sponsored by the IAEA and the International Labour Office. The present Safety Guide provides general guidance on the establishment of an effective radiation protection programme for occupational exposure, in accordance with the requirements of the Basic Safety Standards and appropriate for the sources of radiation likely to be encountered in the workplaces in question

  12. Teacher's Questions in Reading Classes

    Directory of Open Access Journals (Sweden)

    Zuliati Rohmah

    2002-01-01

    Full Text Available Abstract: The present paper discusses an English teacher's questions in Reading classes at MAN Malang III. Types of questions, functions of teacher's questions, question levels and the strategies applied by the teacher were put as the research problems. Non-participant observa­tion was applied to collect the data with the researcher as the main in­strument aided by field-notes and a tape recorder. It was found that the distribution of the questions did not allow the students to talk longer and to think more analytically. Meanwhile, the strategies applied by the teacher helped the students to respond to the questions previously unanswered. The teacher is suggested to produce more open and refer­ential question as well as inference and evaluation questions as to give more chances for the students to think aloud more.

  13. WANO Actions to Reinforce the Operators’ Safety Culture Worldwide

    Energy Technology Data Exchange (ETDEWEB)

    Regaldo, J., E-mail: jacques.regaldo@edf.fr [WANO, London (United Kingdom)

    2014-10-15

    Full text: WANO’s mission is to maximize the safety and reliability of nuclear power plants worldwide by working together to assess, to benchmark and improve performance through mutual support, exchange of information and emulation of best practices. Fukushima accident strongly impacted the nuclear community and it also brought WANO to question its positioning and scope of activities. Five strategic actions have hence been decided to strengthen WANO’s role, aiming to bring a more consistent, transparent and integrated response to the nuclear operators. WANO peer review process, which constitutes its core-business, has been intensified including corporate and pre start up peer reviews and, for Japanese plants, restart reviews. WANO also decided to expand its scope of activity to include elements of design, based on the principle that the role of a nuclear operator is not only to operate safely, but also to be sure that the plant he is operating is safe. WANO aims to cooperate strongly at both regional and international levels with all international safety organizations, being convinced that trust can be recovered with a strong safety commitment and credibility of both regulators and operators. All operators, without exception, are WANO members; if membership is voluntary, members have to fulfil strict obligations. Safety supposes that no operator feels isolated, or refuses openness and permanent self-questioning; it requests as well for WANO to ensure that cultural and sometimes political barriers do not hinder safety culture – the accident of Fukushima is from this perspective rich in teachings. In WANO, we believe that management system and practices are at the centre of safety culture, and a full involvement of top management (CEOs) of our members is absolutely requested. Through its commitments and rules, WANO pressures its members and help them reaching the highest possible standard of safety. We consider that we rely on each other to improve safety

  14. The Priority of the Question: Focus Questions for Sustained Reasoning in Science

    Science.gov (United States)

    Lustick, David

    2010-08-01

    Science education standards place a high priority on promoting the skills and dispositions associated with inquiry at all levels of learning. Yet, the questions teachers employ to foster sustained reasoning are most likely borrowed from a textbook, lab manual, or worksheet. Such generic questions generated for a mass audience, lack authenticity and contextual cues that allow learners to immediately appreciate a question’s relevance. Teacher queries intended to motivate, guide, and foster learning through inquiry are known as focus questions. This theoretical article draws upon science education research to present a typology and conceptual framework intended to support science teacher educators as they identify, develop, and evaluate focus questions with their students.

  15. A Methodology for Evaluating Quantitative Nuclear Safety Culture Impact

    Energy Technology Data Exchange (ETDEWEB)

    Han, Kiyoon; Jae, Moosung [Hanyang University, Seoul (Korea, Republic of)

    2015-05-15

    Through several accidents of NPPs including the Fukushima Daiichi in 2011 and Chernobyl accidents in 1986, nuclear safety culture has been emphasized in reactor safety world-widely. In Korea, KHNP evaluates the safety culture of NPP itself. KHNP developed the principles of the safety culture in consideration of the international standards. A questionnaire and interview questions are also developed based on these principles and it is used for evaluating the safety culture. However, existing methodology to evaluate the safety culture has some disadvantages. First, it is difficult to maintain the consistency of the assessment. Second, the period of safety culture assessment is too long (every two years) so it has limitations in preventing accidents occurred by a lack of safety culture. Third, it is not possible to measure the change in the risk of NPPs by weak safety culture since it is not clearly explains the effect of safety culture on the safety of NPPs. In this study, Safety Culture Impact Assessment Model (SCIAM) is developed overcoming these disadvantages. In this study, SCIAM which overcoming disadvantages of exiting safety culture assessment method is developed. SCIAM uses SCII to monitor the statues of the safety culture periodically and also uses RCDF to quantify the safety culture impact on NPP's safety. It is significant that SCIAM represents the standard of the healthy nuclear safety culture, while the exiting safety culture assessment presented only vulnerability of the safety culture of organization. SCIAM might contribute to monitoring the level of safety culture periodically and, to improving the safety of NPP.

  16. A Methodology for Evaluating Quantitative Nuclear Safety Culture Impact

    International Nuclear Information System (INIS)

    Han, Kiyoon; Jae, Moosung

    2015-01-01

    Through several accidents of NPPs including the Fukushima Daiichi in 2011 and Chernobyl accidents in 1986, nuclear safety culture has been emphasized in reactor safety world-widely. In Korea, KHNP evaluates the safety culture of NPP itself. KHNP developed the principles of the safety culture in consideration of the international standards. A questionnaire and interview questions are also developed based on these principles and it is used for evaluating the safety culture. However, existing methodology to evaluate the safety culture has some disadvantages. First, it is difficult to maintain the consistency of the assessment. Second, the period of safety culture assessment is too long (every two years) so it has limitations in preventing accidents occurred by a lack of safety culture. Third, it is not possible to measure the change in the risk of NPPs by weak safety culture since it is not clearly explains the effect of safety culture on the safety of NPPs. In this study, Safety Culture Impact Assessment Model (SCIAM) is developed overcoming these disadvantages. In this study, SCIAM which overcoming disadvantages of exiting safety culture assessment method is developed. SCIAM uses SCII to monitor the statues of the safety culture periodically and also uses RCDF to quantify the safety culture impact on NPP's safety. It is significant that SCIAM represents the standard of the healthy nuclear safety culture, while the exiting safety culture assessment presented only vulnerability of the safety culture of organization. SCIAM might contribute to monitoring the level of safety culture periodically and, to improving the safety of NPP

  17. A study on safety climate at nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Fukui, Hirokazu [Institute of Nuclear Safety System Inc., Mihama, Fukui (Japan); Yoshida, Michio; Yoshiyama, Naohiro [Japan Institute for Group Dynamics, Fukuoka (Japan)

    2001-09-01

    In the current study, we define safety climate as an organizational environment that induces members of the organization to give consideration to safety or take safety actions. It is of utmost importance that people holding managerial positions in an organization have a good understanding of the characteristics of the safety climate of the organization and implement safety promotion activities effectively. In the current research, we studied the rating scales and the characteristics of a safety climate. A survey was conducted, targeting technical engineers who belong to the three power stations of Kansai Electric Power Co., Inc. The questionnaire mainly consisted of questions concerning safety measures taken by individuals and questions concerning safety measures taken by the organization, to which the individuals belong. As a result of a factor analysis of the responses, we extracted five factors, namely, 'confidence in knowledge and skill', attitude of supervisors,' 'safety education in workplace', 'clarity of tasks' and 'safety confirmation/report'. In studying the rating scales of the safety climate, we selected five items from each of the above five factors, and used the total scores of the ratings of the five items as scores of each factor. Then, we examined the correlation between scores of personal factors and scores of organizational environment factors. We treated the scores of safety confirmation/report' and 'confidence in knowledge and skill', which are personal factors, as criterion variables, and the scores of 'attitude of supervisors', 'safety education in workplace' and 'clarity of tasks', which are organizational environment factors, as predictor variables. As a result, we found that levels of 'safety confirmation/report' and 'confidence in knowledge and skill' can be deduced from the scores of 'attitude of supervisors', 'safety

  18. Safety evaluation review of the prototype license application safety analysis report

    International Nuclear Information System (INIS)

    1991-08-01

    The US Nuclear Regulatory Commission (NRC) staff and consultants reviewed a Prototype License Application Safety Analysis Report (PLASAR) submitted by the US Department of Energy (DOE) for the belowground vault (BGV) alternative method of low-level radioactive waste disposal. In Volume 1 of NUREG-1375, the NRC staff provided the safety review results for an earth-mounded concrete bunker PLASAR. In the current report, the staff focused its review on the design, construction, and operational aspects of the BGV PLASAR. The staff developed review comments and questions using the Standard Review Plan (SRP), Rev. 1 (NUREG-1200) as the basis for evaluating the acceptability of the information provided in the BGV PLASAR. The detailed review comments provided in this report are intended to be useful guidance to facility developers and State regulators in addressing issues likely to be encountered in the review of a license application for a low-level-waste disposal facility. 44 refs

  19. 76 FR 58112 - Safety Zone; M/V DAVY CROCKETT, Columbia River

    Science.gov (United States)

    2011-09-20

    ... Silvestre Suga, Waterways Management Division, Marine Safety Unit Portland, Coast Guard; telephone 503-240- 9319, e-mail Silvestre[email protected] . If you have questions on viewing the docket, call Renee V...

  20. Using the Job Demands-Resources model to investigate risk perception, safety climate and job satisfaction in safety critical organizations.

    Science.gov (United States)

    Nielsen, Morten Birkeland; Mearns, Kathryn; Matthiesen, Stig Berge; Eid, Jarle

    2011-10-01

    Using the Job Demands-Resources model (JD-R) as a theoretical framework, this study investigated the relationship between risk perception as a job demand and psychological safety climate as a job resource with regard to job satisfaction in safety critical organizations. In line with the JD-R model, it was hypothesized that high levels of risk perception is related to low job satisfaction and that a positive perception of safety climate is related to high job satisfaction. In addition, it was hypothesized that safety climate moderates the relationship between risk perception and job satisfaction. Using a sample of Norwegian offshore workers (N = 986), all three hypotheses were supported. In summary, workers who perceived high levels of risk reported lower levels of job satisfaction, whereas this effect diminished when workers perceived their safety climate as positive. Follow-up analyses revealed that this interaction was dependent on the type of risks in question. The results of this study supports the JD-R model, and provides further evidence for relationships between safety-related concepts and work-related outcomes indicating that organizations should not only develop and implement sound safety procedures to reduce the effects of risks and hazards on workers, but can also enhance other areas of organizational life through a focus on safety. © 2011 The Authors. Scandinavian Journal of Psychology © 2011 The Scandinavian Psychological Associations.

  1. On the fundamentals of nuclear reactor safety assessment. Inherent threats and their implications

    Energy Technology Data Exchange (ETDEWEB)

    Hyvaerinen, J. [Finnish Centre for Radiation and Nuclear Safety, Helsinki (Finland). Nuclear Safety Dept.

    1996-12-01

    The thesis addresses some fundamental questions related to implementation and assessment of nuclear safety. The safety principles and assessment methods are described, followed by descriptions of selected novel technical challenges to nuclear safety. The novel challenges encompass a wide variety of technical issues, thus providing insights on the limitations of conventional safety assessment methods. Study of the limitations suggests means to improve nuclear reactor design criteria and safety assessment practices. The novel safety challenges discussed are (1) inherent boron dilution in PWRs, (2) metallic insulation performance with respect to total loss of emergency cooling systems in a loss-of-coolant accident, and (3) horizontal steam generator heat transfer performance at natural circulation conditions. (50 refs.).

  2. On the fundamentals of nuclear reactor safety assessment. Inherent threats and their implications

    International Nuclear Information System (INIS)

    Hyvaerinen, J.

    1996-12-01

    The thesis addresses some fundamental questions related to implementation and assessment of nuclear safety. The safety principles and assessment methods are described, followed by descriptions of selected novel technical challenges to nuclear safety. The novel challenges encompass a wide variety of technical issues, thus providing insights on the limitations of conventional safety assessment methods. Study of the limitations suggests means to improve nuclear reactor design criteria and safety assessment practices. The novel safety challenges discussed are (1) inherent boron dilution in PWRs, (2) metallic insulation performance with respect to total loss of emergency cooling systems in a loss-of-coolant accident, and (3) horizontal steam generator heat transfer performance at natural circulation conditions. (50 refs.)

  3. Desenvolvimento e reprodutibilidade de questionário para avaliar práticas e conhecimentos em segurança alimentar de nutricionistas da área clínica Development and reliability of a questionnaire to assess clinical dietitians' practices and knowledge of food safety

    Directory of Open Access Journals (Sweden)

    Luísa Helena Maia Leite

    2007-08-01

    Full Text Available OBJETIVO: Os propósitos deste estudo foram desenvolver um questionário para avaliar práticas e conhecimentos em segurança sanitária alimentar, de nutricionistas da área clínica, e medir o nível de reprodutibilidade deste questionário. MÉTODOS: O questionário foi desenvolvido a partir de seis áreas temáticas: prevenção da contaminação cruzada; higiene pessoal/ambiental; controle de temperaturas e de alimentos de alto risco e segurança alimentar para indivíduos portadores do vírus da imunodeficiência humana/síndrome da imunodeficiência adquirida. Para medir o nível de reprodutibilidade, utilizou-se o procedimento de teste e re-teste e a estatística kappa simples. RESULTADOS: Os resultados mostraram os níveis de reprodutibilidade: >0,61 para 95,0%; entre 0,60-0,40 para 2,5% e 0,61, sugerindo que o mesmo representa uma boa opção para avaliar as práticas e os conhecimentos em segurança alimentar de nutricionistas da área clínica, visando ao planejamento de estratégias educativas.OBJECTIVE: The purposes of this study were to develop a questionnaire to assess clinical dietitians´ practices and knowledge of food safety and determine the reliability of this instrument. METHODS: The questionnaire was developed around six areas: prevention of cross contamination, personal and environmental hygiene; control of temperature and high-risk foods and food safety for individuals with human immunodeficiency virus/acquired immunodeficiency syndrome. The reliability of the questionnaire was determined by the test-retest method and simple Kappa statistics. RESULTS: The results showed the reliability levels: >0.61 for 95.0%, from 0.60 to 0.40 for 2.5% and 0.61, suggesting that it is a good device to assess clinical dietitians´ practices and knowledge of food safety, which allows for the planning of educational strategies.

  4. 76 FR 73511 - Safety Zone; M/V DAVY CROCKETT, Columbia River

    Science.gov (United States)

    2011-11-29

    ... INFORMATION CONTACT: If you have questions on this temporary rule, call or email BM1 Silvestre Suga, Waterways Management Division, Marine Safety Unit Portland, Coast Guard; telephone (503) 240-9319, email Silvestre.G...

  5. Occupational safety and health textbook for radiological personnel employed in structural material testing

    International Nuclear Information System (INIS)

    Abraham, J.

    1981-01-01

    The comprehensive textbook for X-ray and radiological testing personnel includes requirements and rules of occupational safety and health on the basis of Hungarian and international (mainly German) literature. In the chapter Fundamentals, X-ray and radioactive radiations, their measurements and biological effects, doses etc are described. In the chapter Occupational safety and health, the jobs representing radiation hazards are listed and safety regulations for them are reported. Finally, information for prevention and first aid is presented. Control questions are added to each part. The Appendix contains safety standards and regulations, information on legal aspects of safety and radiation protection as well as recommendations. (Sz.J.)

  6. Parental Knowledge of Trampoline Safety in Children.

    Science.gov (United States)

    Beno, Suzanne; Ackery, Alun; Colaco, Keith; Boutis, Kathy

    2018-03-01

    Recreational trampoline use is increasing in popularity, with a resulting increase in significant trampoline-related injuries in children. Parents are the best advocates for the safety of their children during recreational trampoline use. Our primary objective was to determine the proportion of parents who were aware of 5 key recommendations for safer recreational trampoline use in children. This was a cross-sectional survey of parents whose children presented to a tertiary care pediatric emergency department with an extremity injury. Survey questions were derived and validated using expert opinion, available literature, and pre- and pilot testing of questions on the target audience. Of the 1415 enrolled parents, 654 (46.2%) had regular access to a trampoline and 125 (8.8%) of their children had a history of trampoline injury. A total of 116 (8.2%; 95% confidence interval, 6.8-9.6) parents were aware of all 5 key safety recommendations for home trampoline use. Specifically, the proportion of parents who reported knowledge of the requirement for active supervision, regularly inspected safety equipment, avoiding stunts, multiple jumpers, and use by children 6 years of age and older was 89.0%, 77.2%, 44.3%, 41.6%, and 18.3%, respectively. Trampoline safety knowledge of the 5 key recommendations among parents was low, specifically with respect to recommended age, number of jumpers, and stunts. Because it is unlikely that use of recreational trampolines will decrease, a harm reduction approach that includes a public knowledge translation strategy of recommendations for safer home use of trampolines is necessary. Copyright © 2017 Academic Pediatric Association. Published by Elsevier Inc. All rights reserved.

  7. Applicability and feasibility of systematic review for performing evidence-based risk assessment in food and feed safety

    DEFF Research Database (Denmark)

    Aiassa, E.; Higgins, J.P.T.; Frampton, G. K.

    2015-01-01

    for answering questions in health care, and can be implemented to minimise biases in food and feed safety risk assessment. However, no methodological frameworks exist for refining risk assessment multi-parameter models into questions suitable for systematic review, and use of meta-analysis to estimate all......Food and feed safety risk assessment uses multi-parameter models to evaluate the likelihood of adverse events associated with exposure to hazards in human health, plant health, animal health, animal welfare and the environment. Systematic review and meta-analysis are established methods...... parameters in the risk model. This approach to planning and prioritising systematic review seems to have useful implications for producing evidence-based food and feed safety risk assessment....

  8. Joint statement by the chairmen of the Standing Committee on Reactors and the Reactor Safety Commission on safety-related documents drawn up under the Franco-German Commission on Safety Questions for Nuclear Installations (DFK). August 29, 1986

    International Nuclear Information System (INIS)

    1986-01-01

    The report contains: 1. The present situation regarding hints and recommendations in the safety declaration by the TUEV Baden on the subject of Cattenom nuclear power station in June 1982. 2. The present situation regarding hints and recommendations in the declaration by the TUEV Rhineland in February 1982 on the subject of radiological aspects and features of the Cattenom site for the nuclear power plant. 3. Answers to press allegations about the safety of Cattenom NPP: scram system, safety cooling system, heat sink for after-heat removal, emergency power supplies, load-follow operation, air crashes, susceptibility to failures. (orig./HP) [de

  9. 76 FR 49664 - Safety Zone; M/V DAVY CROCKETT, Columbia River

    Science.gov (United States)

    2011-08-11

    ... questions on this temporary rule, call or e-mail BM1 Silvestre Suga, Waterways Management Division, Marine Safety Unit Portland, Coast Guard; telephone 503-240- 9319, e-mail Silvestre[email protected] . If you...

  10. The French nuclear safety authority, an independent administrative body

    International Nuclear Information System (INIS)

    Lacoste, A.C.

    2007-01-01

    The Nuclear Safety Authority (ASN) is officially responsible for controlling safety and radioactivity in France so as to protect wage-earners, patients, the public and the environment from nuclear-related risks. It draws on the work done by the Institute of Radioprotection and Nuclear Safety (IRSN), and provides information to the public on these questions. The Authority's goal is to ensure an effective, legitimate, impartial and creditable control recognized by the public and serving as an international reference mark. ASN is led by a board of 5 commissaries, has a staff of 420 employees most of them civil servants, has an annual budget of 50 million euros and relies on 11 regional departments

  11. Asking a Great Question: A Librarian Teaches Questioning Skills to First-Year Medical Students.

    Science.gov (United States)

    Adams, Nancy E

    2015-01-01

    In a single one-hour session, first-year medical students were taught a framework for differentiating between lower-order questions that lead to knowledge of facts and higher-order questions that lead to integration of concepts and deeper learning, thereby preparing them for problem-based learning (PBL). Students generated lists of questions in response to an assertion prompt and categorized them according to Bloom's Taxonomy. These data were analyzed in addition to data from the course exam, which asked them to formulate a higher-level question in response to a prompt. Categorizing questions according to Bloom's Taxonomy was a more difficult task for students than was formulating higher-order questions. Students reported that the skills that they learned were used in subsequent PBL sessions to formulate higher-order learning objectives that integrated new and previously-learned concepts.

  12. Lightning safety awareness of visitors in three California national parks.

    Science.gov (United States)

    Weichenthal, Lori; Allen, Jacoby; Davis, Kyle P; Campagne, Danielle; Snowden, Brandy; Hughes, Susan

    2011-09-01

    To assess the level of lightning safety awareness among visitors at 3 national parks in the Sierra Nevada Mountains of California. A 12-question, short answer convenience sample survey was administered to participants 18 years of age and over concerning popular trails and points of interest with known lightning activity. There were 6 identifying questions and 5 knowledge-based questions pertaining to lightning that were scored on a binary value of 0 or 1 for a total of 10 points for the survey instrument. Volunteers in Fresno, California, were used as a control group. Participants were categorized as Sequoia and Kings Canyon National Park (SEKI), frontcountry (FC), or backcountry (BC); Yosemite National Park (YNP) FC or BC; and Fresno. Analysis of variance (ANOVA) was used to test for differences between groups. 467 surveys were included for analysis: 77 in Fresno, 192 in SEKI, and 198 in YNP. National park participants demonstrated greater familiarity with lightning safety than individuals from the metropolitan community (YNP 5.84 and SEKI 5.65 vs Fresno 5.14, P = .0032). There were also differences noted between the BC and FC subgroups (YNP FC 6.07 vs YNP BC 5.62, P = .02; YNP FC 6.07 vs SEKI FC 5.58, P = .02). Overall results showed that participants had certain basic lightning knowledge but lacked familiarity with other key lightning safety recommendations. While there are statistically significant differences in lightning safety awareness between national parks and metropolitan participants, the clinical impact of these findings are debatable. This study provides a starting point for providing educational outreach to visitors in these national parks. Copyright © 2011 Wilderness Medical Society. Published by Elsevier Inc. All rights reserved.

  13. IAEA Director General's concluding remarks. Meeting of the Contracting Parties to the Convention on Nuclear Safety. Vienna, 26 April 2002

    International Nuclear Information System (INIS)

    ElBaradei, M.

    2002-01-01

    The Convention on Nuclear Safety is considered as a part of the overall nuclear safety regime. That regime has many components, but they all have one single objective - to make sure that safety is at as high a level as possible. The Convention is a living process, a process which should eventually lead to increasingly greater safety. The Meting has focused on a number of issues that are also priorities for the Agency; one such issue is safety culture. The effectiveness and transparency are key issues. A second issue which is highlighted is management of nuclear knowledge. Other high priority issues which were identified include: planned life extension; the need during life extension to look into the ageing of equipment and structures; deregulation and its impact on safety; and the question of periodic safety reviews. The question of co-operation between regulatory bodies is one that was given emphasis to over the last few years. It is very important that there be exchange of experience and exchange of expertise between regulatory bodies, and between the manufacturers of power reactors and the countries where the reactors are operated. Also of importance in terms of international co-operation is the development of adequate emergency response everywhere. A major point that which is left to the participating countries is that although safety is a national responsibility - there is absolutely no question about that -many issues need international co-operation

  14. International conference on the strengthening of nuclear safety in Eastern Europe. Keynote papers. Regulatory aspects of NPP safety, status of safety improvements, status of safety analysis report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-06-01

    The Objective of the Conference was to assess the past decade of nuclear safety efforts in countries operating WWER and RBMK nuclear reactors and to address remaining safety issues which require further work. A particular focus of the Conference was on international co-operation and assistance and where such efforts should be focused in the future. All Eastern European countries that operate RBMK or WWER reactors participated in the Conference, and presented papers on three key areas of nuclear safety: Regulatory Aspects of Nuclear Power Plant Safety; Status of Safety Improvements; and Status of Safety Analysis Reports. In addition, representatives from 18 additional countries that provide financial and/or technical assistance and co-operation in the area of WWER and RBMK safety offered the most extensive commentary. Key international (IAEA, World Association of Nuclear Operators, the Nuclear Energy Agency, the G-24 NUSAC, the European Commission, and the EBRD) organizations that provide nuclear safety assistance for WWER and RBMK reactors also made presentations. There is no question that considerable progress on nuclear safety has been made in Eastern Europe. Special mention should be made of successful efforts to strengthen the independence and technical competence of the nuclear regulatory authorities. Efforts should now concentrate on improving the depth and scope of the technical abilities of the regulatory authorities. More attention by governments is needed to ensure that the regulatory authorities have the financial resources and enforcement authority to fully execute their missions. In respect to the operators of the nuclear power plants, they have demonstrated clear progress in operational safety improvements. Significant additional efforts are required to maintain and enhance an effective safety culture. Design safety improvement programmes are in place in all countries. Implementation of these programmes has varied and is particularly affected by

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

    International Nuclear Information System (INIS)

    Corcoran, W.R.

    1992-01-01

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

  16. Assessment of Electrical Safety Beliefs and Practices: A Case Study

    Directory of Open Access Journals (Sweden)

    S. Boubaker

    2017-12-01

    Full Text Available In this paper, the electrical safety beliefs and practices in Hail region, Saudi Arabia, have been assessed. Based on legislative recommendations and rules applied in Saudi Arabia, on official statistics regarding the electricity-caused accidents and on the analysis of more than 200 photos captured in Hail (related to electrical safety, a questionnaire composed of 36 questions (10 for the respondents information, 16 for the home safety culture and 10 for the electrical devices purchasing culture has been devised and distributed to residents. 228 responses have been collected and analyzed. Using a scale similar to the one adopted for a university student GPA calculation, the electrical safety level (ESL in Hail region has been found to be 0.76 (in a scale of 4 points which is a very low score and indicates a poor electrical safety culture. Several recommendations involving different competent authorities have been proposed. Future work will concern the assessment of safety in industrial companies in Hail region.

  17. Impact of delays on customers' safety perceptions and behavioral intentions

    Directory of Open Access Journals (Sweden)

    Paulo Rocha e Oliveira

    2012-10-01

    Full Text Available Purpose: The main objective of this paper is to examine how the customers' perceptions of delays and safety relate to each other and to behavioral intentions.Design/methodology/approach: We modified a customer satisfaction questionnaire to include questions relating to the constructs we wanted to examine and collaborated with a major international airline to collect data from 797 customers through in-flight surveys.Findings: We obtain three key original findings. First, perceived safety exerts a direct positive effect on behavioral intentions. Second, perceived delays exert an indirect effect mediated by perceived safety. Finally, customers believe operational practices affect both delay and safety.Originality/value: This is the first paper that examines the customer's perspective on two of the most important aspects of airline operations management: delays and safety. Our findings are of great value to managers who want to evaluate the impact of delays and safety on customers and to researches interested in the theoretical relationships between these two constructs.

  18. Efficient question answering with question decomposition and multiple answer streams

    OpenAIRE

    Hartrumpf, Sven; Glöckner, Ingo; Leveling, Johannes

    2009-01-01

    The German question answering (QA) system IRSAW (formerly: InSicht) participated in QA@CLEF for the fth time. IRSAW was introduced in 2007 by integrating the deep answer producer InSicht, several shallow answer producers, and a logical validator. InSicht builds on a deep QA approach: it transforms documents to semantic representations using a parser, draws inferences on semantic representations with rules, and matches semantic representations derived from questions and documents. InS...

  19. Chiropractic care and public health : answering difficult questions about safety, care through the lifespan, and community action

    NARCIS (Netherlands)

    Johnson, Claire; Rubinstein, Sidney M; Côté, Pierre; Hestbaek, Lise; Injeyan, H Stephen; Puhl, Aaron; Green, Bart; Napuli, Jason G; Dunn, Andrew S; Dougherty, Paul; Killinger, Lisa Zaynab; Page, Stacey A; Stites, John S; Ramcharan, Michael; Leach, Robert A; Byrd, Lori D; Redwood, Daniel; Kopansky-Giles, Deborah R

    The purpose of this collaborative summary is to document current chiropractic involvement in the public health movement, reflect on social ecological levels of influence as a profession, and summarize the relationship of chiropractic to the current public health topics of: safety, health issues

  20. International exchange of safety and licensing information

    International Nuclear Information System (INIS)

    Lafleur, J.D. Jr.; Hauber, R.D.; Chenier, D.M.

    1977-01-01

    A network of formal and informal bilateral arrangements for the exchange of nuclear safety information is being established by the US Nuclear Regulatory Commission. For developing countries such arrangements can provide ready access to the extensive, fully documented safety analyses and safety research results that USNRC has accumulated. USNRC has been receiving foreign visitors at a rate of about 500 per year, largely for discussions of safety and licensing questions related to light water reactors. Exchanges also are taking place on the safety of advanced reactors. A special interest of the USNRC is in providing for reciprocal communication, at the earliest possible time, of important problems, decisions and other actions on nuclear safety matters. For example, it is essential that a newly discovered problem in a nuclear reactor be brought immediately to the attention of other governments that are responsible for the safety of similar reactors. Definite progress has been made in the USA in defining categories of information that USNRC can receive in confidence from foreign countries, and can protect from disclosure under the US Freedom of Information Act. Certain exchanges have taken place on this basis. Experience in the establishment and operation of USNRC's bilateral exchange arrangements is summarized. A typical exchange with the regulatory authority of a country building its first power reactor is described. (author)

  1. Optimal safety is the philosophy

    International Nuclear Information System (INIS)

    Anon.

    1990-01-01

    In order to promote international sharing of knowledge of radiation dose reduction at nuclear plants, the OECD's Paris-based Nuclear Energy Agency (NEA) has launched plans and preparations for a new institution, the Information System on Occupational Exposure (ISOE). Eight OECD countries are evaluating a pilot project and the NEA is discussing the establishment of a permanent ISOE. The aim is to have instant answers to varied questions on effective dose-reduction techniques, typical doses for particular jobs, dose rates at standard points in plants and the way they are being affected by dose-reduction techniques. With answers based on data from all OECD countries with experience in nuclear power plant operations. At the centre of the nuclear industry's radiological protection is the principle that all radiation doses should be kept as low as reasonably achievable (alara), economic and social factors being taken into account. If this principle were applied beyond radiological protection to safety in general, for example, road safety, it, would lead to much better overall safety. (UK)

  2. Safety issues at the defense production reactors

    International Nuclear Information System (INIS)

    1987-01-01

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

  3. Effective education in radiation safety for nurses

    International Nuclear Information System (INIS)

    Ohno, K.; Kaori, T.

    2011-01-01

    In order to establish an efficient training program of radiation safety for nurses, studies have been carried out on the basis of questionnaires. Collaboration of nurses, who are usually standing closest to the patient, is necessary in order to offer safe radiological diagnostics/treatment. The authors distributed the questionnaire to 134 nurses in five polyclinic hospitals in Japan. Important questions were: fear of radiation exposure, knowledge on the radiation treatment, understanding the impact on pregnancy, and so on. Most of the nurses feel themselves uneasy against exposure to radiation. They do not have enough knowledge of radiological treatment. They do not know exactly what is the impact of the radiation on pregnant women. Such tendency is more pronounced, when nurses spend less time working in the radiological department. Nurses play important roles in radiological diagnostics/treatment. Therefore, a well-developed education system for radiation safety is essential. The training for the radiation safety in medicine should be done in the context of general safety in medicine. Education programs in undergraduate school and at the working place should be coordinated efficiently in order to ensure that both nurses and patients are informed about the meaning of radiation safety. (authors)

  4. Safety evaluation of the ESP sludge washing baselines runs. Revision 2

    International Nuclear Information System (INIS)

    Gupta, M.K.

    1993-01-01

    Purpose is to provide the technical basis for evaluation of unreviewed safety question for the Extended Sludge Processing (ESP) Sludge Washing Baseline Runs, which are necessary to resolve technical questions associated with process control (sludge suspension, sludge settling, heat transfer, temperature control). The sludge is currently stored in below-ground tanks and will be prepared for processing at the Defense Waste Processing Facility as part of the Integrated Waste Removal Program for Savannah River Site

  5. Toward Question-Asking Machines: The Logic of Questions and the Inquiry Calculus

    Science.gov (United States)

    Knuth,Kevin H.

    2005-01-01

    For over a century, the study of logic has focused on the algebra of logical statements. This work, first performed by George Boole, has led to the development of modern computers, and was shown by Richard T. Cox to be the foundation of Bayesian inference. Meanwhile the logic of questions has been much neglected. For our computing machines to be truly intelligent, they need to be able to ask relevant questions. In this paper I will show how the Boolean lattice of logical statements gives rise to the free distributive lattice of questions thus defining their algebra. Furthermore, there exists a quantity analogous to probability, called relevance, which quantifies the degree to which one question answers another. I will show that relevance is not only a natural generalization of information theory, but also forms its foundation.

  6. Chemical plant innovative safety investments decision-support methodology.

    Science.gov (United States)

    Reniers, G L L; Audenaert, A

    2009-01-01

    This article examines the extent to which investing in safety during the creation of a new chemical installation proves profitable. The authors propose a management supporting cost-benefit model that identifies and evaluates investments in safety within a chemical company. This innovative model differentiates between serious accidents and less serious accidents, thus providing an authentic image of prevention-related costs and benefits. In classic cost-benefit analyses, which do not make such differentiations, only a rudimentary image of potential profitability resulting from investments in safety is obtained. The resulting management conclusions that can be drawn from such classical analyses are of a very limited nature. The proposed model, however, is applied to a real case study and the proposed investments in safety at an appointed chemical installation are weighed against the estimated hypothetical benefits resulting from the preventive measures to be installed at the installation. In the case-study carried out in question, it would appear that the proposed prevention investments are justified. Such an economic exercise may be very important to chemical corporations trying to (further) improve their safety investments.

  7. Canadian Consumer Food Safety Practices and Knowledge: Foodbook Study.

    Science.gov (United States)

    Murray, Regan; Glass-Kaastra, Shiona; Gardhouse, Christine; Marshall, Barbara; Ciampa, Nadia; Franklin, Kristyn; Hurst, Matt; Thomas, M Kate; Nesbitt, Andrea

    2017-10-01

    Understanding consumers' food safety practices and knowledge supports food safety education for the prevention of foodborne illness. The objective of this study was to describe Canadian consumer food safety practices and knowledge. This study identifies demographic groups for targeted food safety education messaging and establishes a baseline measurement to assess the effectiveness of food safety interventions over time. Questions regarding consumer food safety practices and knowledge were included in a population-based telephone survey, Foodbook, conducted from November 2014 to March 2015. The results were analyzed nationally by age group and by gender. The results showed that approximately 90% of Canadians reported taking the recommended cleaning and separating precautions when handling raw meat to prevent foodborne illness. Only 29% of respondents reported using a food thermometer when cooking any meat, and even fewer (12%) reported using a food thermometer for small cuts of meat such as chicken pieces. The majority (>80%) of Canadians were aware of the foodborne illness risks related to chicken and hamburger, but fewer (poultry.

  8. Continuing the Conversation: Development of the U.S. NRC's Definition of Safety Culture and its Traits

    International Nuclear Information System (INIS)

    Barnes, Valerie; Koves, Ken

    2012-01-01

    Val Barnes gave a presentation on behalf of the US NRC and INPO. She summarised the work done by the US NRC to develop the US NRC Policy on Safety Culture. Stakeholder representatives were involved in panel sessions to develop a common definition of safety culture and define the traits of a positive safety culture. A survey-based validation study of the eight traits identified through the panel sessions was then conducted across the 63 US nuclear sites by INPO. The INPO study also examined the correlations between the safety culture traits and safety performance. Strong correlations were found for some factors (for example, the number of unplanned scrams correlated strongly with perceptions on management responsibility). The results of the survey supported the inclusion of an additional safety culture trait (questioning attitude) resulting in the following nine traits: - Leadership Safety Values and Actions. - Problem Identification and Resolution. - Personal Accountability. - Work Process. - Continuous Learning. - Environment for Raising Concerns. - Effective Safety Communication. - Respectful Work Environment. - Questioning Attitude. The US NRC has also issued a safety culture policy statement which provides the following definition: 'Nuclear safety culture is the core values and behaviors resulting from a collective commitment by leaders and individuals to emphasize safety over competing goals to ensure protection of people and the environment'. The US NRC and its regulated communities are now working on implementing the policy statement. It was concluded that the work carried out to develop the safety culture policy statement has helped to develop a common language and understanding amongst stakeholders

  9. New Innovative Ethical Principles in Increasing Road Safety

    Directory of Open Access Journals (Sweden)

    Igor Miletić

    2013-06-01

    Full Text Available Research Question (RQ: Future managers are faced daily with a variety of ethical dilemmas in traffic that need to be balanced by the interests of all participants. The question is whether a new innovative model of ethical principles could be developed that would increase road safety.Purpose: The a im is to raise the level of social responsibility and relationship of participants in traffic as well as warn all participants on the importance of safety. In addition, the purpose is to share suggestions to other researchers for further research studies in the area of increasing traffic safety.Method: We carried out a quantitative study (survey among first year post-graduate students studying at a higher education school focused on quality management in south-eastern Slovenia. The article presents five different ethical scenarios.Results: The participants have very similar views on judging individual ethical dilemmas. The desire to increase road safety, have led to new useful suggestions for further study of innovative new ethical principles in the field of safety, such as: no death victims annually, adequate road infrastructure, improved vehicle technology, video surveillance systems, and so on.Organization: Relevant authorities should promote models of ethical thinking and the introduction of codes of conduct at an early age. As such, the state, police, rescuers, fire departments, hospitals, and so on, would have fewer deaths due to serious traffic accidents.Society: By taking these results and further research suggestions into account, society would gain a new model that would be based on zero accidents annually.Originality: Research in the field of ethics and innovative ethical principles of traffic safety is limited. The article presents practical examples of ethical and moral decision-making that we encounter in daily traffic. But nothing much is done to make it better ("every day the same story".Limitations/Future Research: The research study

  10. 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.

  11. Asking the Right Questions

    DEFF Research Database (Denmark)

    Richter, Line

    Based on fieldwork in Mali this paper discusses the role of anthropology (and the anthropologist) in a large public health research project on children's health. In the uncertainty and disquiet that comes with the battle to combat and avoid diseases in a setting where poverty and abysmal diseases......, is the ability to move beyond even the best hidden assumptions and question our own questions, thereby enabling us to ask the right questions....

  12. Okla. Tornado Renews Debate on Storm Safety

    Science.gov (United States)

    Shah, Nirvi

    2013-01-01

    As soon as the winds that left seven students in Moore, Okla., dead last month had calmed, and more storms blew through the same area less than two weeks later, questions about the safety of schools in a region labeled Tornado Alley rose amid the rubble. While better design of new schools and thorough emergency training and practice may be in…

  13. K-effective as a measure of criticality safety

    International Nuclear Information System (INIS)

    Venner, J.; Haley, R.M.; Bowden, R.L.

    2003-01-01

    This paper considers the relation between the neutron multiplication of a system, k-effective, and critical parameters. It aims to investigate whether k-effective is always the most appropriate measure of safety. For simple systems handbook data can be effectively utilized, applying a safety factor to critical masses. In such situations, the criticality safety margin is readily apparent. However, more complex systems may use the calculated value of neutron multiplication to assess the criticality safety of the system under investigation. A problem arises because there is no exact consistency between k-effective and the physical margin of subcriticality, in terms of parameters such as mass. In the UK, commonly accepted safety criteria are applied to limit the k-effective of the system being assessed. These margins of subcriticality have no definitive justification to support the values chosen and might be considered rather arbitrary in nature. This paper aims to answer this question of suitability by investigating the relation between k-effective and the physical critical parameters for a wide range of systems. It concludes that the safety criteria currently applied in the UK are valid, but some difference exists between safety factors applied to the mass of fissile material present and the corresponding value of k-effective. (author)

  14. Culture of safety. Indicators of culture of safety. Stage of culture of safety. Optimization of radiating protection. Principle of precaution. Principle ALARA. Procedure ALARA

    International Nuclear Information System (INIS)

    Mursa, E.

    2006-01-01

    Object of research: is the theory and practice of optimization of radiating protection according to recommendations of the international organizations, realization of principle ALARA and maintenance of culture of safety (SC) on the nuclear power plant. The purpose of work - to consider the general aspects of realization of principle ALARA, conceptual bases of culture of safety, as principle of management, and practice of their introduction on the nuclear power plant. The work has the experts' report character in which the following questions are presented: The recommendations materials of the IAEA and other international organizations have been assembled, systematized and analyzed. The definitions, characteristics and universal SC features, and also indicators as a problem of parameters and quantitative SC measurements are described in details advanced. The ALARA principles - principle of precaution; not acceptance of zero risk; choice of a principle ALARA; model of acceptable radiation risk are described. The methodology of an estimation of culture of safety level and practical realization of the ALARA principle in separate organization is shown on a practical example. The SC general estimation at a national level in Republic of Moldova have been done. Taking into consideration that now Safety Culture politics are introduced only in relation to APS, in this paper the attempt of application of Safety Culture methodology to Radiological Objects have been made (Oncological Institute of the Republic of Moldova and Special Objects No.5101 and 5102 for a long time Storage of the Radioactive Waste). (authors)

  15. The status of safety in the public high school chemistry laboratories in Mississippi

    Science.gov (United States)

    Lacy, Sarah Louise Trotman

    Since laboratory-based science courses have become an essential element of any science curriculum and are required by the Mississippi Department of Education for graduation, the chemistry laboratories in the public high schools in Mississippi must be safe. The purpose of this study was to determine: the safety characteristics of a high school chemistry laboratory; the perceived safety characteristics of the chemistry laboratories in public high schools in Mississippi; the basic safety knowledge of chemistry teachers in public high schools in Mississippi, where chemistry teachers in Mississippi gain knowledge about laboratory safety and instruction; if public high school chemistry laboratories in Mississippi adhere to recommended class size, laboratory floor space per student, safety education, safety equipment, and chemical storage; and the relationship between teacher knowledge of chemistry laboratory safety and the safety status of the laboratory in which they teach. The survey instrument was composed of three parts. Part I Teacher Knowledge consisted of 23 questions concerning high school chemistry laboratory safety. Part II Chemistry Laboratory Safety Information consisted of 40 items divided into four areas of interest concerning safety in high school chemistry laboratories. Part III Demographics consisted of 11 questions relating to teacher certification, experience, education, and safety training. The survey was mailed to a designated chemistry teacher in every public high school in Mississippi. The responses to Part I of the survey indicated that the majority of the teachers have a good understanding of knowledge about chemistry laboratory safety but need more instruction on the requirements for a safe high school chemistry laboratory. Less than 50% of the responding teachers thought they had received adequate preparation from their college classes to conduct a safe chemistry laboratory. According to the responses of the teachers, most of their high school

  16. The safety-incentive theory of liability

    International Nuclear Information System (INIS)

    Marshall, J.M.

    1977-11-01

    The use of liability law to improve incentives for safety is supported by certain recent theoretical results. The main ideas and the key argumants are summarized. Basic weaknesses of the theory are discussed, namely: (1) the simple model of Calabresi does not generalize; (2) the more complex systems of J.P. Brown, P. Diamond, and J. Green require that courts possess a great deal of information and use it to set appropriate standards of due care; (3) in practice safety incentives also depend upon fear of criminal penalties and the sense of social responsibility. The questions whether and when liability rules can significantly affect incentives are addressed. It is concluded that the theory in its present state can hardly serve as a basis for altering liability rules

  17. High safety in the mining industry

    Energy Technology Data Exchange (ETDEWEB)

    1987-08-01

    Presents an interview in question and answer format with the deputy chairman of Gosgortekhnadzor (Committee for Supervision of Industrial Work Safety and Mining Supervision) in which he discusses two recent fatal accidents in the Yasinovskaya-Glubokaya and Chaikino coal mines and identifies areas where safety needs to be improved (more automation, protective devices, ventilation etc.). Discusses the particular problems involved with deep mining (20% of mines are now deeper than 700 m and 27 mines are deeper than 1000 m), such as fires, dust, methane, rock falls, insufficient maintenance and strata control and poor ventilation. Confirms that a large number of accidents is due to poor organization and stresses the fact the coal industry must be subjected to perestroika (restructuring) as much as other areas of society.

  18. Implementing and measuring safety goals and safety culture. 4. Utility's Activities for Better Safety Culture After the JCO Accident

    International Nuclear Information System (INIS)

    Omoto, Akira

    2001-01-01

    three activities described below. As a part of self-diagnosis of organizational behavior and an individual's factors influencing safety, measurement was carried out by asking questions to every employee at the station, i.e., 21 questions asking if we are appropriately implementing safety culture 'standards' as set forth in INSAG-4 (Ref. 2). The purpose was twofold: to educate about INSAG-4 and to find areas for improvement. The results indicated that employees want to learn more about (a) the background for the specific actions required/prescribed in the procedures/guidelines and (b) how things go wrong if they do not strictly follow the procedures/guidelines. These were important findings, which led to the reconstruction of the on-site education and training. Considering that employees should be well informed on safety culture; management's policy; and lessons learned from incidents, domestic or international, we started the bimonthly magazine Safety Culture. The first publication included articles on 'Lessons Learned from JCO', 'The Results from the Self- Diagnosis', 'Lessons from an Incident at Hunterston NPS (LOOP Followed by Operator Actions for Safe Shutdown)', and others. The on-site training system has two elements: on-the-job training and off-the-job study with classroom and hands-on training. Most of the employees are trained at the On-Site Training Center with equipment and are qualified for specific job categories. Training of operators has its own lengthy program. Given the foregoing findings, we (a) started lectures on JCO lessons learned, (b) modified the educational system at the On-Site Training Center to nurture the employees with well-balanced knowledge and thinking (Fig. 1), and (c) prepared documents that describe the background and reasons for the actions required/prescribed in the procedures/guidelines for use in on-the-job training. The important point to be remembered about the JCO accident is that the criticality safety at this facility

  19. Semantic annotation of consumer health questions.

    Science.gov (United States)

    Kilicoglu, Halil; Ben Abacha, Asma; Mrabet, Yassine; Shooshan, Sonya E; Rodriguez, Laritza; Masterton, Kate; Demner-Fushman, Dina

    2018-02-06

    Consumers increasingly use online resources for their health information needs. While current search engines can address these needs to some extent, they generally do not take into account that most health information needs are complex and can only fully be expressed in natural language. Consumer health question answering (QA) systems aim to fill this gap. A major challenge in developing consumer health QA systems is extracting relevant semantic content from the natural language questions (question understanding). To develop effective question understanding tools, question corpora semantically annotated for relevant question elements are needed. In this paper, we present a two-part consumer health question corpus annotated with several semantic categories: named entities, question triggers/types, question frames, and question topic. The first part (CHQA-email) consists of relatively long email requests received by the U.S. National Library of Medicine (NLM) customer service, while the second part (CHQA-web) consists of shorter questions posed to MedlinePlus search engine as queries. Each question has been annotated by two annotators. The annotation methodology is largely the same between the two parts of the corpus; however, we also explain and justify the differences between them. Additionally, we provide information about corpus characteristics, inter-annotator agreement, and our attempts to measure annotation confidence in the absence of adjudication of annotations. The resulting corpus consists of 2614 questions (CHQA-email: 1740, CHQA-web: 874). Problems are the most frequent named entities, while treatment and general information questions are the most common question types. Inter-annotator agreement was generally modest: question types and topics yielded highest agreement, while the agreement for more complex frame annotations was lower. Agreement in CHQA-web was consistently higher than that in CHQA-email. Pairwise inter-annotator agreement proved most

  20. Unreviewed Disposal Question: A Discipline Process to Manage Change in LLW Disposal

    International Nuclear Information System (INIS)

    Goldston, W.T.

    2000-01-01

    The Department of Energy's waste management Order, DOE O 435.1, requires that low--level waste disposal facilities develop and maintain a radiological performance assessment to ensure that disposal operations are within a performance envelope defined by performance objectives for long-term protection of the public and the environment. The Order also requires that a radiological composite analysis be developed and maintained to ensure that the disposal facility, in combination with other sources of radioactive material that may remain when all DOE activities have ceased, will not compromise future radiological protection of the public and the environment. The Order further requires that a Disposal Authorization Statement (DAS) be obtained from DOE Headquarters and that the disposal facility be operated within the performance assessment, composite analysis, and DAS. Maintenance of the performance assessment and composite analysis includes conducting test, research, and monitoring activities to increase confidence in the results of the analyses. It also includes updating the analyses as changes are proposed in the disposal operations, or other information requiring an update, becomes available. Personnel at the Savannah River Site have developed and implemented an innovative process for reviewing proposed or discovered changes in low-level radioactive waste disposal operations. The process is a graded approach to determine, in a disciplined manner, whether changes are within the existing performance envelope, as defined by the performance assessment, composite analysis, and DAS, or whether additional analysis is required to authorize the change. This process is called the Unreviewed Disposal Question (UDQ) process. It has been developed to be analogous to the Unreviewed Safety Question (UDQ) process that has been in use within DOE for many years. This is the first formalized system implemented in the DOE complex to examine low-level waste disposal changes the way the

  1. Live your questions now

    OpenAIRE

    Brownrigg, Jenny

    2016-01-01

    'Live Your Questions Now' is a case study for Cubitt Education's publication 'Aging in Public: creative practice in ageing and the public realm from across the UK', edited by Daniel Baker and published by Cubitt Gallery, Studios and Education, London in 2016. The publication was linked to Cubitt's programme 'Public Wisdom' (2011-2015). My case study is about 'Live your questions now', a group exhibition I curated in 2011 for Mackintosh Museum, The Glasgow School of Art. 'Live your questions n...

  2. Safety upgrading of the PAKS Nuclear Plant

    International Nuclear Information System (INIS)

    Vamos, G.; Vigassy, J.

    1993-01-01

    In the last several years the net electricity from the Paks NPP represents almost half of the Hungarian total. The 4 units of Paks belong to the latest generation of the VVER-440 units, the small-sized Russian designed PWRs. Reviewing the main design features of them, the safety merits and safety concerns are summarized. Due to the conservative design and the extensive operating experience the safety merits appear to be more significant than generally believed. The VVER-440 type has two models, the 230 and 213, which have a large number of distinctive safety features. These are highlighted in the section comparisons. A quality assurance program was initiated in Paks very early. A long-term safety upgrading program was also initiated, originating from vendor recommendations, regulatory decisions, in-house operating experience and safety concerns, and independent reviews. The main areas and some examples of the measures are described. This program, like all other activities related to nuclear safety, has been under regulatory control. The specific features of the Hungarian regulatory system are described. For advanced, general and new evaluation of the safety of the units in Paks in accordance with the internationally recommended criteria of the 90's, the project AGNES has been launched with international participation. The scope of this project is summarized. International efforts as the IAEA Regional Project on safety assessment of VVER-440/213 and VVER-440/230 units are underway. Since safety is not only a question of design, but it can be significantly influenced by operations and maintenance practices, the Paks NPP has invited LAEA's OSART and ASSET missions, WANO's Pilot Peer Review

  3. Nuclear safety. Living up to high expectations today, tomorrow

    International Nuclear Information System (INIS)

    Jennekens, J.H.

    1986-10-01

    How safe is safe enough? In the nuclear energy field, whenever government, the nuclear industry, or independent researchers have presented the public with an answer to this question it has been met with a demand for more safety-related controls on the industry. It is doubtful whether doubling the $25 million budget of the Canadian Atomic Energy Control Board (AECB) would result in twice as much nuclear safety. It is disturbing that people feel there is not enough information; the much of the information the AECB makes available has been ignored. In the long term it is important that the public become confident in nuclear safety. It may be that some day all toxic waste will have to be managed as safely as nuclear waste

  4. Patient safety and infection control: bases for curricular integration.

    Science.gov (United States)

    Silva, Andréa Mara Bernardes da; Bim, Lucas Lazarini; Bim, Felipe Lazarini; Sousa, Alvaro Francisco Lopes; Domingues, Pedro Castania Amadio; Nicolussi, Adriana Cristina; Andrade, Denise de

    2018-05-01

    To analyze curricular integration between teaching of patient safety and good infection prevention and control practices. Integrative review, designed to answer the question: "How does curricular integration of content about 'patient safety teaching' and content about 'infection prevention and control practices' occur in undergraduate courses in the health field?". The following databases were searched for primary studies: CINAHL, LILACS, ScienceDirect, Web of Science, Scopus, Europe PMC and MEDLINE. The final sample consisted of 13 studies. After content analysis, primary studies were grouped into two subject categories: "Innovative teaching practices" and "Curricular evaluation. Patient safety related to infection prevention and control practices is present in the curriculum of health undergraduate courses, but is not coordinated with other themes, is taught sporadically, and focuses mainly on hand hygiene.

  5. Study on European Nuclear Safety Practices during Planned Outages at Nuclear Power Plants

    International Nuclear Information System (INIS)

    2001-12-01

    The present project was aimed at providing: a description of the current status of nuclear safety practices during planned outages at nuclear power plants followed in Europe; the criteria for the safety analysis of future reactors at the design stage; proposing a set of recommendations on good practices and criteria leading to the improvement of nuclear safety during those conditions. The work was organised in 3 phases: Collecting data on current practices; Analysis of questionnaire answers and drawing up of safety good practices references and recommendations; Collecting relevant ideas related to the future reactors at design stage (European Pressurised Water Reactor, European Passive Plant project, European Utilities Requirements and Utilities Requirement Document project). The key element of the performed work was the detailed questionnaire, based on bibliographical review, expert experience and outage practices available in the working team. Different safety areas and activities were covered: outage context; nuclear safety; outage strategy, organisation and control; operating feedback; use of Probabilistic Safety Assessment. The questionnaire was answered by 12 European nuclear power plants, representing 9 different European countries and three different types of reactors (Pressurised Water Reactor, Boiling Water Reactor and Water Water Energy Reactor). Conclusions were drawn under the following headers: Organisational survey and generalities Organisational effectiveness Quality of maintenance Quality of operation Engineering support, management of modification Specific aspects Each analysed subject includes the following topics: Questions background with a summary and the aim of the questions. Current status, that describes common practices, as derived from the answers to the questionnaire, and some examples of good specific practices. Identified good practices. (author)

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

    Science.gov (United States)

    Pfeiffer, Yvonne; Schwappach, David

    2016-01-01

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

  7. Global Chance's notebooks Nr 33 - March 2013. Questions which grieve. Contribution to the national debate on energy transition

    International Nuclear Information System (INIS)

    Ruedinger, Andreas; Laponche, Bernard; Guillemette, Andre; Zerbib, Jean-Claude; Dessus, Benjamin; Riedacker, Arthur; Marquet, Andre

    2013-03-01

    The first articles propose respectively an overview of the energy situation in France and in Germany. Then, two articles address the issue of safety and MOX in the nuclear sector: arguments and questions regarding accidents and safety of nuclear power plants, assessments for 2011 for the production and storages of EDF's MOX fuels. The next part proposes a discussion of the issue of shale gas, and a discussion on the issue of climate change. The last part proposes a discussion of an alternate scenario for the renewal of hydroelectric concessions or how to organise the mutual complementary nature of renewable energies and consumption management

  8. A Technique Socratic Questioning-Guided Discovery

    Directory of Open Access Journals (Sweden)

    M. Hakan Türkçapar

    2012-03-01

    Full Text Available “Socratic Method” is a way of teaching philosophical thinking and knowledge by asking questions which was used by antique period greek philosopher Socrates. Socrates was teaching knowledge to his followers by asking questions and the conversation between them was named “Socratic Dialogues”. In this meaning, no novel knowledge is taught to the individual but only what is formerly known is reminded and rediscovered. The form of socratic questioning which is used during the process of cognitive behavioral therapy is known as Guided Discovery. In this method it is aimed to make the client notice the piece of knowledge which he could notice but is not aware with a series of questions. Socratic method or guided discovery consists of several steps which are: Identifying the problem by listening to the client and making reflections, finding alternatives by examining and evaluating, reidentification by using the newly found information and questioning the old distorted belief and reaching to a conclusion and applying it. Question types used during these procedures are, questions for gaining information, questions revealing the meanings, questions revealing the beliefs, questions about behaviours during the similar past experiences, analyse questions and analytic synthesis questions. In order to make the patient feel understood it is important to be empathetic and summarising the problem during the interview. In this text, steps of Socratic Questioning-Guided Discovery will be reviewed with sample dialogues after each step

  9. Methodological issues and pitfalls of short safety culture questionnaires

    NARCIS (Netherlands)

    Jagtman, H.M.; Koornneef, F.; Akselsson, R.; Stewart, S.

    2013-01-01

    Safety culture surveys have been fielded in many different sectors of industrial activities. Many of these surveys consist of a long list of questions which is time consuming for the respondents. As part of the FP6 HILAS project a shorter survey has been developed, which aimed at getting a high

  10. Need to increase public awareness of the safety of radioactive materials transport

    International Nuclear Information System (INIS)

    Bishop, R.W.

    1983-01-01

    There are two aspects to the problem of the public perception of radioactive materials transport: the first is a lack of knowledge on the part of the public about the facts, and the second is the distorted presentation by the media. These two problems are obviously interrelated - the more unaware the public is of the actual safety of radioactive materials transport, the more it is likely to be influenced, and frightened, by inaccurate reporting. The obvious question is, what can we as an industry do to educate the public and to facilitate more neutral reporting about the facts involving radioactive materials transport. This question is answered by describing an excellent example of a situation where the industry acted cohesively and effectively to respond to fallacious allegations concerning the safety of the transportation of radioactive materials

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

    Science.gov (United States)

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

    2015-11-01

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

  12. Mass Media vs. Public and National Safety

    Directory of Open Access Journals (Sweden)

    Andrzej Adamski

    2012-12-01

    Full Text Available The media have become an integral part of social life. They have an enormous impact on it. However, they occasionally may be harmful or even―more or less consciously―their actions may lead to various distortions of the public and national safety. Under what circumstances would be such a situation possible to occur? How to prevent it? This article contains answers to those questions.

  13. US nuclear safety review and experience

    International Nuclear Information System (INIS)

    Gilinsky, V.

    1977-01-01

    U.S. nuclear safety review process. Now, however, is the time when we must focus on one of the principal safety questions of our time: How safe is safe enough where nuclear power plants are concerned

  14. Proving autonomous vehicle and advanced driver assistance systems safety : final research report.

    Science.gov (United States)

    2016-02-15

    The main objective of this project was to provide technology for answering : crucial safety and correctness questions about verification of autonomous : vehicle and advanced driver assistance systems based on logic. : In synergistic activities, we ha...

  15. Containment-emergency-sump performance. Technical findings related to Unresolved Safety Issue A-43

    International Nuclear Information System (INIS)

    1983-04-01

    This report summarizes key technical findings related to the Unresolved Safety Issue A-43, Containment Emergency Sump Performance, and provides recommendations for resolution of attendant safety issues. The key safety questions relate to: (a) effects of insulation debris on sump performance; (b) sump hydraulic performance as determined by design features, submergence, and plant induced effects, and (c) recirculation pump performance wherein air and/or particulate ingestion can occur. The technical findings presented in this report provide information relevant to the design and performance evaluation of the containment emergency sump

  16. Frequent Questions on Recycling

    Science.gov (United States)

    This is a list of frequent questions on recycling, broken down into five categories. These are answers to common questions that EPA has received from press and web inquiries. This list is located on the Reduce, Reuse, Recycle website.

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

    International Nuclear Information System (INIS)

    Sugawara, Shin-etsu; Inamura, Tomoaki

    2016-01-01

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

  18. Test Plan for Radioactive Testing of a Vertical Direct Denitration Calciner

    International Nuclear Information System (INIS)

    COMPTON, J.A.

    1999-01-01

    The prototype Vertical Denitration Calciner (VDC) is installed in glovebox 188 in the Plutonium Process Support Laboratory (PPSL). Safety analysis contained in WHC-SD-CP-SAR-021 (FSAR) Rev. 0-L and Addendum to WHC-SD-CP-SAR-021, ''Laboratory Prototype Calciner'' establishes the prototype VDC needs to be shut down if a seismic event of greater than 0.07 g occurs. Shut down is to be automatic upon detection of the seismic event. This requires tie-in of various valves and power for the prototype VDC into the existing Seismic Shutdown System for the Ventilation Supply Fans described in FSAR 5.4.1.2.4. The proposed changes covered by this USQ evaluation include: (1) the physical tie-in modifications, including drawings and Engineering Change Notice (ECN), (2) the work package for accomplishing the modifications, (3) the changes to the System Description Documents, (4) the changes to the Safety Equipment List necessitated by the modifications, and (5) the changes to the failure modes and effects analysis. WHC-SDCP-OSR-010, Plutonium Finishing Plant Operational Safety Requirements Limiting Condition for Operation (LCO) 3.2.3 has been revised to include the requirement for the existing seismic shutdown system to also shut down the laboratory calciner in the event of detection of a greater than 0.07 g seismic event

  19. Test plan for radioactive testing of a vertical direct denitration calciner

    Energy Technology Data Exchange (ETDEWEB)

    COMPTON, J.A.

    1999-08-31

    The prototype Vertical Denitration Calciner (VDC) is installed in glovebox 188 in the Plutonium Process Support Laboratory (PPSL). Safety analysis contained in WHC-SD-CP-SAR-021 (FSAR) Rev. 0-L and Addendum to WHC-SD-CP-SAR-021, ''Laboratory Prototype Calciner'' establishes the prototype VDC needs to be shut down if a seismic event of greater than 0.07 g occurs. Shut down is to be automatic upon detection of the seismic event. This requires tie-in of various valves and power for the prototype VDC into the existing Seismic Shutdown System for the Ventilation Supply Fans described in FSAR 5.4.1.2.4. The proposed changes covered by this USQ evaluation include: (1) the physical tie-in modifications, including drawings and Engineering Change Notice (ECN), (2) the work package for accomplishing the modifications, (3) the changes to the System Description Documents, (4) the changes to the Safety Equipment List necessitated by the modifications, and (5) the changes to the failure modes and effects analysis. WHC-SDCP-OSR-010, Plutonium Finishing Plant Operational Safety Requirements Limiting Condition for Operation (LCO) 3.2.3 has been revised to include the requirement for the existing seismic shutdown system to also shut down the laboratory calciner in the event of detection of a greater than 0.07 g seismic event.

  20. Test Plan for Radioactive Testing of a Vertical Direct Denitration Calciner

    Energy Technology Data Exchange (ETDEWEB)

    COMPTON, J.A.

    1999-08-31

    The prototype Vertical Denitration Calciner (VDC) is installed in glovebox 188 in the Plutonium Process Support Laboratory (PPSL). Safety analysis contained in WHC-SD-CP-SAR-021 (FSAR) Rev. 0-L and Addendum to WHC-SD-CP-SAR-021, ''Laboratory Prototype Calciner'' establishes the prototype VDC needs to be shut down if a seismic event of greater than 0.07 g occurs. Shut down is to be automatic upon detection of the seismic event. This requires tie-in of various valves and power for the prototype VDC into the existing Seismic Shutdown System for the Ventilation Supply Fans described in FSAR 5.4.1.2.4. The proposed changes covered by this USQ evaluation include: (1) the physical tie-in modifications, including drawings and Engineering Change Notice (ECN), (2) the work package for accomplishing the modifications, (3) the changes to the System Description Documents, (4) the changes to the Safety Equipment List necessitated by the modifications, and (5) the changes to the failure modes and effects analysis. WHC-SDCP-OSR-010, Plutonium Finishing Plant Operational Safety Requirements Limiting Condition for Operation (LCO) 3.2.3 has been revised to include the requirement for the existing seismic shutdown system to also shut down the laboratory calciner in the event of detection of a greater than 0.07 g seismic event.

  1. Test Plan for Radioactive Testing of a Vertical Direct Denitration Calciner

    Energy Technology Data Exchange (ETDEWEB)

    COMPTON, J.A.

    1999-08-13

    The prototype Vertical Denitration Calciner (VDC) is installed in glovebox 188 in the Plutonium Process Support Laboratory (PPSL). Safety analysis contained in WHC-SD-CP-SAR-021 (FSAR) Rev. 0-L and Addendum to WHC-SD-CP-SAR-021, ''Laboratory Prototype Calciner'' establishes the prototype VDC needs to be shut down if a seismic event of greater than 0.07 g occurs. Shut down is to be automatic upon detection of the seismic event. This requires tie-in of various valves and power for the prototype VDC into the existing Seismic Shutdown System for the Ventilation Supply Fans described in FSAR 5.4.1.2.4. The proposed changes covered by this USQ evaluation include: (1) the physical tie-in modifications, including drawings and Engineering Change Notice (ECN), (2) the work package for accomplishing the modifications, (3) the changes to the System Description Documents, (4) the changes to the Safety Equipment List necessitated by the modifications, and (5) the changes to the failure modes and effects analysis. WHC-SDCP-OSR-010, Plutonium Finishing Plant Operational Safety Requirements Limiting Condition for Operation (LCO) 3.2.3 has been revised to include the requirement for the existing seismic shutdown system to also shut down the laboratory calciner in the event of detection of a greater than 0.07 g seismic event.

  2. Safety management of Ethernet broadband access based on VLAN aggregation

    Science.gov (United States)

    Wang, Li

    2004-04-01

    With broadband access network development, the Ethernet technology is more and more applied access network now. It is different from the private network -LAN. The differences lie in four points: customer management, safety management, service management and count-fee management. This paper mainly discusses the safety management related questions. Safety management means that the access network must secure the customer data safety, isolate the broad message which brings the customer private information, such as ARP, DHCP, and protect key equipment from attack. Virtue LAN (VLAN) technology can restrict network broadcast flow. We can config each customer port with a VLAN, so each customer is isolated with others. The IP address bound with VLAN ID can be routed rightly. But this technology brings another question: IP address shortage. VLAN aggregation technology can solve this problem well. Such a mechanism provides several advantages over traditional IPv4 addressing architectures employed in large switched LANs today. With VLAN aggregation technology, we introduce the notion of sub-VLANs and super-VLANs, a much more optimal approach to IP addressing can be realized. This paper will expatiate the VLAN aggregation model and its implementation in Ethernet access network. It is obvious that the customers in different sub-VLANs can not communication to each other because the ARP packet is isolated. Proxy ARP can enable the communication among them. This paper will also expatiate the proxy ARP model and its implementation in Ethernet access network.

  3. Wanted! Possible links between religious coping and safety

    DEFF Research Database (Denmark)

    Knudsen, Fabienne; Grøn, Sisse

    . The injuries, though, are not evenly distributed and seem to depend on a range of factors, of which the type of ship and the nationality of the seafarer are critical. Statistics show that Filipino seafarers working on Danish ships have less than 50% reported accidents compared to Danes - the Danes having...... lower risk of occupational accidents than seafarers from Western Europe. Therefore, the project will seek to identify relevant aspects of both reporting practice and safety culture in Danish seafaring.   The objective of the project is to identify causes behind the registered difference in numbers...... of injuries among Danish seafarers and their foreign colleagues, in order to direct future safety initiative towards the relevant factors. The research questions are as follows: How is safety learnt, conceived of, communicated and practiced, within the national groupings, and between the national groupings...

  4. Examining the Impact of Question Surface Features on Students’ Answers to Constructed-Response Questions on Photosynthesis

    Science.gov (United States)

    Weston, Michele; Haudek, Kevin C.; Prevost, Luanna; Urban-Lurain, Mark; Merrill, John

    2015-01-01

    One challenge in science education assessment is that students often focus on surface features of questions rather than the underlying scientific principles. We investigated how student written responses to constructed-response questions about photosynthesis vary based on two surface features of the question: the species of plant and the order of two question prompts. We asked four versions of the question with different combinations of the two plant species and order of prompts in an introductory cell biology course. We found that there was not a significant difference in the content of student responses to versions of the question stem with different species or order of prompts, using both computerized lexical analysis and expert scoring. We conducted 20 face-to-face interviews with students to further probe the effects of question wording on student responses. During the interviews, we found that students thought that the plant species was neither relevant nor confusing when answering the question. Students identified the prompts as both relevant and confusing. However, this confusion was not specific to a single version. PMID:25999312

  5. Knowledge and practices of food hygiene and safety among camel ...

    African Journals Online (AJOL)

    The respondents showed low knowledge in answering questions regarding spoilage microorganisms and effective cleaning of containers. About 53% of women retailers used rejected/spoiled milk for household consumption. This could result in a high food safety risk. Therefore, training of actors along the camel milk value ...

  6. Biology Question Generation from a Semantic Network

    Science.gov (United States)

    Zhang, Lishan

    Science instructors need questions for use in exams, homework assignments, class discussions, reviews, and other instructional activities. Textbooks never have enough questions, so instructors must find them from other sources or generate their own questions. In order to supply instructors with biology questions, a semantic network approach was developed for generating open response biology questions. The generated questions were compared to professional authorized questions. To boost students' learning experience, adaptive selection was built on the generated questions. Bayesian Knowledge Tracing was used as embedded assessment of the student's current competence so that a suitable question could be selected based on the student's previous performance. A between-subjects experiment with 42 participants was performed, where half of the participants studied with adaptive selected questions and the rest studied with mal-adaptive order of questions. Both groups significantly improved their test scores, and the participants in adaptive group registered larger learning gains than participants in the control group. To explore the possibility of generating rich instructional feedback for machine-generated questions, a question-paragraph mapping task was identified. Given a set of questions and a list of paragraphs for a textbook, the goal of the task was to map the related paragraphs to each question. An algorithm was developed whose performance was comparable to human annotators. A multiple-choice question with high quality distractors (incorrect answers) can be pedagogically valuable as well as being much easier to grade than open-response questions. Thus, an algorithm was developed to generate good distractors for multiple-choice questions. The machine-generated multiple-choice questions were compared to human-generated questions in terms of three measures: question difficulty, question discrimination and distractor usefulness. By recruiting 200 participants from

  7. Commonly asked questions: thrombolytic therapy in the management of acute stroke.

    Science.gov (United States)

    Block, H Steven; Biller, José

    2013-02-01

    Questions about thrombolytic management arise frequently, often with the intent of ascertaining safety and efficacy in specific situations. Thrombolytic therapy is generally safe, even if a nonruptured intracranial aneurysm is present. The risk of cardiac rupture with tamponade is low, except for the first 7 weeks following myocardial infarction. Over this duration, there is an increased risk of intravenous thrombolytic therapy in specific patient groups. Stroke infrequently occurs during cardiac catheterization. Its infrequent occurrence has limited large treatment trials. Basilar artery occlusion management will be reviewed. Thrombolytic therapy is generally safe in the context of pre-existing cerebral microhemorrhages and cervical artery dissections. Additionally, the role of multimodal penumbral imaging in planning stroke therapy will be reviewed.

  8. [Does simulator-based team training improve patient safety?].

    Science.gov (United States)

    Trentzsch, H; Urban, B; Sandmeyer, B; Hammer, T; Strohm, P C; Lazarovici, M

    2013-10-01

    Patient safety became paramount in medicine as well as in emergency medicine after it was recognized that preventable, adverse events significantly contributed to morbidity and mortality during hospital stay. The underlying errors cannot usually be explained by medical technical inadequacies only but are more due to difficulties in the transition of theoretical knowledge into tasks under the conditions of clinical reality. Crew Resource Management and Human Factors which determine safety and efficiency of humans in complex situations are suitable to control such sources of error. Simulation significantly improved safety in high reliability organizations, such as the aerospace industry.Thus, simulator-based team training has also been proposed for medical areas. As such training is consuming in cost, time and human resources, the question of the cost-benefit ratio obviously arises. This review outlines the effects of simulator-based team training on patient safety. Such course formats are not only capable of creating awareness and improvements in safety culture but also improve technical team performance and emphasize team performance as a clinical competence. A few studies even indicated improvement of patient-centered outcome, such as a reduced rate of adverse events but further studies are required in this respect. In summary, simulator-based team training should be accepted as a suitable strategy to improve patient safety.

  9. An NEA contribution to the safety of nuclear ships

    International Nuclear Information System (INIS)

    Stadie, K.B.; Thomas, R.A.

    1978-01-01

    The civil nuclear ships put into service so far have performed well and have an excellent safety record. There are substantial differences however between these experimental vessels and a free-ranging fleet of nuclear-powered merchant ships development of which will require satisfactory solutions to certain technical questions, an international consensus on safety requirements, and some form of international arrangement for regulation and surveillance. The paper describes the work sponsored by the OECD Nuclear Energy Agency in this field, and points out areas where future effort should be focussed, as a prerequisite for such future developments

  10. Industrial safety and fire protection during the construction phase

    International Nuclear Information System (INIS)

    Zimmer, K.

    1977-01-01

    The questions and problems of industrial safety and fire prevention have to be treated like the activities planning, developing, assembly, etc. This statement is illustrated by statistics of the fire insurance companies, from which it can be seen that the number of fire accidents has decreased but that the damage caused has greatly increased. The sooner the fire prevention and industrial safety measures are integrated in the planning phase, the better for the total costs. Preventive measures that possibly have to be introduced at a later stage are not only generally much more expensive but are also seldom as effective. (orig./HK) [de

  11. 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.

  12. Nuclear power systems: Their safety

    International Nuclear Information System (INIS)

    Myers, L.C.

    1993-01-01

    Mankind utilizes energy in many forms and from a variety of sources. Canada is one of a growing number of countries which have chosen to embrace nuclear-electric generation as a component of their energy systems. As of August 1992 there were 433 power reactors operating in 35 countries and accounting for more than 15% of the world's production of electricity. In 1992, thirteen countries derived at least 25% of their electricity from nuclear units, with France leading at nearly 70%. In the same year, Canada produced about 16% of its electricity from nuclear units. Some 68 power reactors are under construction in 16 countries, enough to expand present generating capacity by close to 20%. No human endeavour carries the guarantee of perfect safety and the question of whether or not nuclear-electric generation represents an 'acceptable' risk to society has long been vigorously debated. Until the events of late April 1986, nuclear safety had indeed been an issue for discussion, for some concern, but not for alarm. The accident at the Chernobyl reactor in the USSR has irrevocably changed all that. This disaster brought the matter of nuclear safety back into the public mind in a dramatic fashion. This paper discusses the issue of safety in complex energy systems and provides brief accounts of some of the most serious reactor accidents which have occurred to date. (author). 7 refs

  13. Safety Profile of Cough and Cold Medication Use in Pediatrics.

    Science.gov (United States)

    Green, Jody L; Wang, George Sam; Reynolds, Kate M; Banner, William; Bond, G Randall; Kauffman, Ralph E; Palmer, Robert B; Paul, Ian M; Dart, Richard C

    2017-06-01

    The safety of cough and cold medication (CCM) use in children has been questioned. We describe the safety profile of CCMs in children pediatric (75.5%), and single-ingredient (77.5%) formulations were most commonly involved. AEs occurring in >20% of all cases included tachycardia, somnolence, hallucinations, ataxia, mydriasis, and agitation. Twenty cases (0.6%) resulted in death; most were in children pediatric liquid formulations were the most commonly reported products. These characteristics present an opportunity for targeted prevention efforts. Copyright © 2017 by the American Academy of Pediatrics.

  14. 2013 Bike safety campaign: outcome and feedback

    CERN Multimedia

    HSE Unit

    2013-01-01

    From 3 to 17 June, the HSE Unit, in collaboration with the Reception and Access Control Service, led a campaign targeting CERN cyclists.   Photo: Laëtitia Wohlgemuth. In exchange for vouchers distributed by the security guards, 195 persons received a helmet and a reflective vest as well as documents on safety issues (ex: how to adjust one’s safety helmet properly; how to avoid blind spots; what is the required equipment for bikes and bike users, etc.). These persons also took part in a survey that contained questions on their cycling habits and level of knowledge on bike safety issues. It appeared that, for instance, 43% of the participants were aware that wearing a reflective vest is mandatory whenever visibility is poor (in France). 95% gave particular attention to the need to protect their heads (by assuming that wearing a helmet is either “mandatory” or “highly recommended”). The HSE Unit provided the participants with further i...

  15. Questions for Music Education Research

    Science.gov (United States)

    Jorgensen, Estelle R.

    2008-01-01

    In addressing the question-set "What questions do music education researchers need to address?", an illustrative list of juxtaposed descriptive and normative questions is sketched as follows: What are and should be the dimensions of music education? What are and should be the institutional agencies of music education? What are and should be the…

  16. Dynamic Question Ordering in Online Surveys

    Directory of Open Access Journals (Sweden)

    Early Kirstin

    2017-09-01

    Full Text Available Online surveys have the potential to support adaptive questions, where later questions depend on earlier responses. Past work has taken a rule-based approach, uniformly across all respondents. We envision a richer interpretation of adaptive questions, which we call Dynamic Question Ordering (DQO, where question order is personalized. Such an approach could increase engagement, and therefore response rate, as well as imputation quality. We present a DQO framework to improve survey completion and imputation. In the general survey-taking setting, we want to maximize survey completion, and so we focus on ordering questions to engage the respondent and collect hopefully all information, or at least the information that most characterizes the respondent, for accurate imputations. In another scenario, our goal is to provide a personalized prediction. Since it is possible to give reasonable predictions with only a subset of questions, we are not concerned with motivating users to answer all questions. Instead, we want to order questions to get information that reduces prediction uncertainty, while not being too burdensome. We illustrate this framework with two case studies, for the prediction and survey-taking settings. We also discuss DQO for national surveys and consider connections between our statistics-based question-ordering approach and cognitive survey methodology.

  17. Integration of safety in management tasks in onshore transport SME´s

    DEFF Research Database (Denmark)

    Jørgensen, Kirsten

    2015-01-01

    with animals and the risk of violence and robbery. To create a high level of safety in an enterprise is a difficult task that demands a great degree of management engagement. It is not only a question of having the right equipment, procedures and organization etc.; it is also necessary for everyone...... in the enterprise to have an understanding of safety and feel obligated to take responsibility for safety in all work at all times. Accident research shows that safety must be integrated in the whole enterprise and function on all levels of management, while it must also involve all employees in their daily work...... prevention. The result is a realistic strategy for integration safety, quality and environmental factors in an SME and procedures for how to go from strategy to action. Different tools were developed to fulfil the strategy ranging from risk identification, involvement of the employee and motivational...

  18. Annual report 1986 of Society for Reactor Safety (GRS)

    International Nuclear Information System (INIS)

    1987-01-01

    The overall development of Society for Reactor Safety (GRS) is indicated by its annual volume of achievement. After initially high growth rates that achievement has come to stand at some 62 million marks or so over the last years. GRS today employs some 450 staff, of which 325 are scientific-technical experts representing altogether nearly 4000 man-years of experience in nuclear technology. The report presents essential results from the main points of activity of GRS over 10 years. In accordance with the aim of the institution they primarily cover projects in the sectors safety and radiation protection for nuclear facilities. Since 1985, since the extension of its contract of associates, GRS has also increasingly been concerned with safety questions in non-nuclear technology, concentrating mainly on the transfer of existing methods. (orig./DG) [de

  19. Seismic safety in nuclear-waste disposal

    International Nuclear Information System (INIS)

    Carpenter, D.W.; Towse, D.

    1979-01-01

    Seismic safety is one of the factors that must be considered in the disposal of nuclear waste in deep geologic media. This report reviews the data on damage to underground equipment and structures from earthquakes, the record of associated motions, and the conventional methods of seismic safety-analysis and engineering. Safety considerations may be divided into two classes: those during the operational life of a disposal facility, and those pertinent to the post-decommissioning life of the facility. Operational hazards may be mitigated by conventional construction practices and site selection criteria. Events that would materially affect the long-term integrity of a decommissioned facility appear to be highly unlikely and can be substantially avoided by conservative site selection and facility design. These events include substantial fault movement within the disposal facility and severe ground shaking in an earthquake epicentral region. Techniques need to be developed to address the question of long-term earthquake probability in relatively aseismic regions, and for discriminating between active and extinct faults in regions where earthquake activity does not result in surface ruptures

  20. Seismic safety in nuclear-waste disposal

    Energy Technology Data Exchange (ETDEWEB)

    Carpenter, D.W.; Towse, D.

    1979-04-26

    Seismic safety is one of the factors that must be considered in the disposal of nuclear waste in deep geologic media. This report reviews the data on damage to underground equipment and structures from earthquakes, the record of associated motions, and the conventional methods of seismic safety-analysis and engineering. Safety considerations may be divided into two classes: those during the operational life of a disposal facility, and those pertinent to the post-decommissioning life of the facility. Operational hazards may be mitigated by conventional construction practices and site selection criteria. Events that would materially affect the long-term integrity of a decommissioned facility appear to be highly unlikely and can be substantially avoided by conservative site selection and facility design. These events include substantial fault movement within the disposal facility and severe ground shaking in an earthquake epicentral region. Techniques need to be developed to address the question of long-term earthquake probability in relatively aseismic regions, and for discriminating between active and extinct faults in regions where earthquake activity does not result in surface ruptures.

  1. Long-term Safety of a Geologic Repository: What does the public want to know?

    International Nuclear Information System (INIS)

    Kotra, Janet

    2008-01-01

    Janet Kotra of the U.S. NRC recounted the questions most frequently asked of the Commission's staff, concerning the long-term safety of the planned Yucca Mountain repository. The first question was related to who would decide whether the facility is safe enough. The next question linked to it is if regulatory staff is sufficiently qualified, and if they have access to independent sources of information or depend merely on the information provided by the implementer. The subsequent questions were about what criteria the regulator used and whether they were comprehensive enough. A separate group of questions addressed the safety of the technology, including the geologic features of the site, the engineered structures and the packaging of waste. Issues of documentation, operational control, long-term monitoring, oversight, and enforcement were also raised, along with the transparency of such processes and the accessibility of documents to the public. In addition, several questions were related to the fairness of decision making, public involvement, and the flexibility of the implementation process with regard to future knowledge and RD and D. Ms Kotra propounded that a single question was behind those cited above, namely whether one could rely on the regulator or not. Since it is not realistic to expect an overall consensus on the decision of the regulator agency, the goal should rather be to build confidence in the decision-making process. Key factors of confidence include openness on the part of the regulator and other decision-making institutions, and access to trustworthy representatives of these organisations

  2. Pressure Safety: Advanced Self-Study 30120

    Energy Technology Data Exchange (ETDEWEB)

    Glass, George [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-02-29

    Pressure Safety Advance Self-Study (Course 30120) consists of an introduction, five modules, and a quiz. To receive credit in UTrain for completing this course, you must score 80% or better on the 15-question quiz (check UTrain). Directions for initiating the quiz are appended to the end of this training manual. This course contains several links to LANL websites. UTrain might not support active links, so please copy links into the address line in your browser.

  3. Safety related aspects of ultimate disposal of radioactive wastes

    International Nuclear Information System (INIS)

    Goemmel, R.

    1992-01-01

    Solutions and questions related to nuclear waste management are presented. In particular, long-term safety of repositories in Germany and Sweden is considered, with special attention being paid to methods of detection, geotechnical barriers and post-operational phase of salt dome repositories, and conditioning of wastes to make them fit for ultimate disposal. (DG) [de

  4. Communication of geo-scientific safety arguments

    International Nuclear Information System (INIS)

    Flavelle, P.; Goodwin, B.; Jensen, M.; Linden, R.; Mazurek, M.; Srivastave, M.; Strom, A.; Sudicky, E.; Voinis, S.

    2007-01-01

    Working Group B addressed the communication of geo-scientific safety arguments through a discussion of practical experience as it related to the methods, types of information and specific arguments found to best communicate geo-scientific concepts and notions of safety with broad audiences including, colleagues, authorities and regulators, political decision makers, academics, and the general public. The following questions were suggested by the programme committee of the AMIGO-2 workshop for discussion by Working Group B with respect to the communication of geo-scientific information and safety arguments: - What is the place of geo-scientific arguments in relation to quantitative and qualitative topics like scenario and FEPs (features, events, processes) assessment, simulated repository evolution, calculated dose or risk impacts, engineering tests of materials, etc., when presenting a safety case to different audiences and with respect to the various stages of the repository programme? (see section 3). - Would we be better off focusing messages to the public on time scales of a few hundred years or a few generations? (see section 4). - How do you handle the fact that geoscience interpretations seldom are unique and data often are open to various interpretations? (see section 5). - How do you handle expert controversy on a specific topic? (see section 6). (authors)

  5. Advanced Test Reactor Safety Basis Upgrade Lessons Learned Relative to Design Basis Verification and Safety Basis Management

    International Nuclear Information System (INIS)

    G. L. Sharp; R. T. McCracken

    2004-01-01

    The Advanced Test Reactor (ATR) is a pressurized light-water reactor with a design thermal power of 250 MW. The principal function of the ATR is to provide a high neutron flux for testing reactor fuels and other materials. The reactor also provides other irradiation services such as radioisotope production. The ATR and its support facilities are located at the Test Reactor Area of the Idaho National Engineering and Environmental Laboratory (INEEL). An audit conducted by the Department of Energy's Office of Independent Oversight and Performance Assurance (DOE OA) raised concerns that design conditions at the ATR were not adequately analyzed in the safety analysis and that legacy design basis management practices had the potential to further impact safe operation of the facility.1 The concerns identified by the audit team, and issues raised during additional reviews performed by ATR safety analysts, were evaluated through the unreviewed safety question process resulting in shutdown of the ATR for more than three months while these concerns were resolved. Past management of the ATR safety basis, relative to facility design basis management and change control, led to concerns that discrepancies in the safety basis may have developed. Although not required by DOE orders or regulations, not performing design basis verification in conjunction with development of the 10 CFR 830 Subpart B upgraded safety basis allowed these potential weaknesses to be carried forward. Configuration management and a clear definition of the existing facility design basis have a direct relation to developing and maintaining a high quality safety basis which properly identifies and mitigates all hazards and postulated accident conditions. These relations and the impact of past safety basis management practices have been reviewed in order to identify lessons learned from the safety basis upgrade process and appropriate actions to resolve possible concerns with respect to the current ATR safety

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

    International Nuclear Information System (INIS)

    Besnus, F.; Gay, D.

    2002-01-01

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

  7. The role of cooperatives in food safety management of fresh produce chains: Case studies in four strawberry cooperatives

    NARCIS (Netherlands)

    Kirezieva, K.K.; Bijman, J.; Jacxsens, L.; Luning, P.A.

    2016-01-01

    Recent outbreaks with fresh produce have raised questions regarding management of quality and safety in the complex supply chains, where cooperatives play a central role. The overall objective of this article was to investigate the role of cooperatives in food quality and safety management in the

  8. Patient Drug Safety Reporting: Diabetes Patients' Perceptions of Drug Safety and How to Improve Reporting of Adverse Events and Product Complaints.

    Science.gov (United States)

    Patel, Puja; Spears, David; Eriksen, Betina Østergaard; Lollike, Karsten; Sacco, Michael

    2018-03-01

    Global health care manufacturer Novo Nordisk commissioned research regarding awareness of drug safety department activities and potential to increase patient feedback. Objectives were to examine patients' knowledge of pharmaceutical manufacturers' responsibilities and efforts regarding drug safety, their perceptions and experiences related to these efforts, and how these factors influence their thoughts and behaviors. Data were collected before and after respondents read a description of a drug safety department and its practices. We conducted quantitative survey research across 608 health care consumers receiving treatment for diabetes in the United States, Germany, United Kingdom, and Italy. This research validated initial, exploratory qualitative research (across 40 comparable consumers from the same countries) which served to guide design of the larger study. Before reading a drug safety department description, 55% of respondents were unaware these departments collect safety information on products and patients. After reading the description, 34% reported the department does more than they expected to ensure drug safety, and 56% reported "more confidence" in the industry as a whole. Further, 66% reported themselves more likely to report an adverse event or product complaint, and 60% reported that they were more likely to contact a drug safety department with questions. The most preferred communication methods were websites/online forums (39%), email (27%), and telephone (25%). Learning about drug safety departments elevates consumers' confidence in manufacturers' safety efforts and establishes potential for patients to engage in increased self-monitoring and reporting. Study results reveal potentially actionable insights for the industry across patient and physician programs and communications.

  9. Improving the effectiveness of road safety campaigns : current and new practices.

    NARCIS (Netherlands)

    Hoekstra, A.T.G. & Wegman, F.C.M.

    2015-01-01

    The evaluation of campaigns aimed at improving road safety is still the exception rather than the rule. Because of this, ineffective campaigns and campaign techniques are allowed to continue to be utilised without question, while new methods of behaviour modification are often ignored. Therefore,

  10. Improving the effectiveness of road safety campaigns : Current and new practices

    NARCIS (Netherlands)

    Hoekstra, T.; Wegman, F.C.M.

    2011-01-01

    The evaluation of campaigns aimed at improving road safety is still the exception rather than the rule. Because of this, ineffective campaigns and campaign techniques are allowed to continue to be utilised without question, while new methods of behaviour modification are often ignored. Therefore,

  11. Atomic Questions Group peer review mission to Bulgaria

    International Nuclear Information System (INIS)

    Vapirev, E.; Georgiev, J.; Sabinov, S.

    2004-01-01

    The objective of the Atomic Questions Group (AQG) peer review mission (17-19 Nov 2003) was to monitor the status of the recommendations contained in the 2001 Report on Nuclear Safety in the Context of Enlargement focusing specifically those recommendations identified in the 2002 Peer Review Status Report as requiring further attention or monitoring. Most AQG/WPNS 2001 recommendations were found as adequately addressed with the exception of the following to which Bulgaria was expected to devote further attention: 2nd General Recommendation NPP type I regarding Safety Analysis Reports (SARs); 1st Specific Recommendation NPP type I regarding the new nuclear legislation; 1st General Recommendation Other Nuclear Installations type II regarding the storage of radioactive waste. In addition WPNS recommended further monitoring of the following commitments: 1st General Recommendation NPP type I regarding the plant specific safety improvement programmes - to ensure that the programmes are completed in accordance with the plans; 2nd General Recommendation NPP type I regarding Safety Analysis Reports (SARs) - to ensure that the SARs are completed in accordance with the plans; 2nd General Recommendation NPP type I regarding Emergency Operating Procedures (EOPs) - to ensure the completion of work on EOPs in accordance with the plans and so that these provide for the development of appropriate guidance on the management of beyond design basis accidents; 2nd Specific Recommendation NPP type I regarding the resources of the regulator - to ensure that adequate human and financial resources will be provided according to the developed plan; 5th Specific Recommendation NPP type I regarding the implementation of specific upgrading improvements at Kozloduy units 3 and 4- to specifically follow these items during the monitoring associated with 1st General recommendation NPP type I, Upgrading programme; 6th Specific Recommendation NPP type I regarding high-energy pipe breaks at Kozloduy

  12. Public perception of drinking water safety in South Africa 2002-2009: a repeated cross-sectional study.

    Science.gov (United States)

    Wright, Jim A; Yang, Hong; Rivett, Ulrike; Gundry, Stephen W

    2012-07-27

    In low and middle income countries, public perceptions of drinking water safety are relevant to promotion of household water treatment and to household choices over drinking water sources. However, most studies of this topic have been cross-sectional and not considered temporal variation in drinking water safety perceptions. The objective of this study is to explore trends in perceived drinking water safety in South Africa and its association with disease outbreaks, water supply and household characteristics. This repeated cross-sectional study draws on General Household Surveys from 2002-2009, a series of annual nationally representative surveys of South African households, which include a question about perceived drinking water safety. Trends in responses to this question were examined from 2002-2009 in relation to reported cholera cases. The relationship between perceived drinking water safety and organoleptic qualities of drinking water, supply characteristics, and socio-economic and demographic household characteristics was explored in 2002 and 2008 using hierarchical stepwise logistic regression. The results suggest that perceived drinking water safety has remained relatively stable over time in South Africa, once the expansion of improved supplies is controlled for. A large cholera outbreak in 2000-02 had no apparent effect on public perception of drinking water safety in 2002. Perceived drinking water safety is primarily related to water taste, odour, and clarity rather than socio-economic or demographic characteristics. This suggests that household perceptions of drinking water safety in South Africa follow similar patterns to those observed in studies in developed countries. The stability over time in public perception of drinking water safety is particularly surprising, given the large cholera outbreak that took place at the start of this period.

  13. Gay-Straight Alliances: Understanding Their Impact on the Academic and Social Experiences of Lesbian, Gay, Bisexual, Transgender, and Questioning High School Students

    Science.gov (United States)

    McCormick, Adam; Schmidt, Kathryn; Clifton, Emily

    2015-01-01

    Few studies have examined the effectiveness of gay-straight alliances (GSAs) on the social and academic experiences of lesbian, gay, bisexual, transgender, and questioning (LGBTQ) youths. The limited research on GSAs suggests that they are associated with positive youth development and increased safety; however, little qualitative information…

  14. The Question Complexity Rubric: Development and Application for a National Archive of Astro 101 Multiple-Choice Questions

    Science.gov (United States)

    Cormier, Sebastien; Prather, E. E.; Brissenden, G.; Collaboration of Astronomy Teaching Scholars CATS

    2011-01-01

    For the last two years we have been developing an online national archive of multiple-choice questions for use in the Astro 101 classroom. These questions are intended to either supplement an instructor's implementation of Think-Pair-Share or be used for assessment purposes (i.e. exams and homework). In this talk we will describe the development, testing and implementation of the Question Complexity Rubric (QCR), which is designed to guide the ranking of questions in this archive based on their conceptual complexity. Using the QCR, a score is assigned to differentiate each question based on the cognitive steps necessary to comprehensively explain the reasoning pathway to the correct answer. The lowest QCR score is given to questions with a reasoning pathway requiring only declarative knowledge whereas the highest QCR score is given to questions that require multiple pathways of multi-step reasoning. When completed, the online question archive will provide users with the utility to 1) search for and download questions based on subject and average QCR score, 2) use the QCR to score questions, and 3) add their own questions to the archive. We will also discuss other potential applications of the QCR, such as how it informs our work in developing and testing of survey instruments by allowing us to calibrate the range of question complexity. This material is based upon work supported by the National Science Foundation under Grant No. 0715517, a CCLI Phase III Grant for the Collaboration of Astronomy Teaching Scholars (CATS). Any opinions, findings, and conclusions or recommendations expressed in this material are those of the authors and do not necessarily reflect the views of the National Science Foundation.

  15. Personal, Family and School Influences on Secondary Pupils' Feelings of Safety at School, in the School Surroundings and at Home

    Science.gov (United States)

    Mooij, Ton

    2012-01-01

    Different types of variables seem to influence school safety and a pupil's feelings of safety at school. The research question asks which risk and promotive variables should be integrated in a theoretical model to predict a pupil's feelings of safety at school, in the school surroundings and at home; what the outcomes are of an empirical check of…

  16. The Value Question in Metaphysics

    Science.gov (United States)

    Kahane, Guy

    2012-01-01

    Much seems to be at stake in metaphysical questions about, for example, God, free will or morality. One thing that could be at stake is the value of the universe we inhabit—how good or bad it is. We can think of competing philosophical positions as describing possibilities, ways the world might turn out to be, and to which value can be assigned. When, for example, people hope that God exists, or fear that we do not possess free will, they express attitudes towards these possibilities, attitudes that presuppose answers to questions about their comparative value. My aim in this paper is to distinguish these evaluative questions from related questions with which they can be confused, to identify structural constraints on their proper pursuit, and to address objections to their very coherence. Answers to such evaluative questions offer one measure of the importance of philosophical disputes. PMID:23024399

  17. The Value Question in Metaphysics.

    Science.gov (United States)

    Kahane, Guy

    2012-07-01

    Much seems to be at stake in metaphysical questions about, for example, God, free will or morality. One thing that could be at stake is the value of the universe we inhabit-how good or bad it is. We can think of competing philosophical positions as describing possibilities, ways the world might turn out to be, and to which value can be assigned. When, for example, people hope that God exists, or fear that we do not possess free will, they express attitudes towards these possibilities, attitudes that presuppose answers to questions about their comparative value. My aim in this paper is to distinguish these evaluative questions from related questions with which they can be confused, to identify structural constraints on their proper pursuit, and to address objections to their very coherence. Answers to such evaluative questions offer one measure of the importance of philosophical disputes.

  18. Aspects of operational safety and long-term structural stability of the Morsleben repository for radioactive wastes (ERAM)

    International Nuclear Information System (INIS)

    Wernicke, R.S.

    1997-01-01

    The results of safety evaluations and safety reports reveal undoubtedly, that the Morsleben final repository operations is safe and responsible. On the basis of safety-technical evaluations some need was identified for locally optimizing the repository operations and possibly also some geotechnical features of the mine. However, this does not raise safety-related questions for man and the environment. In addition to the control exercised by the supervisory body, continuing evaluations of the repository operations assure, that changes of the safety status will be recognized in a timely manner and that competent action may be taken if necessary. (orig.) [de

  19. Nuclear safety and public debate

    International Nuclear Information System (INIS)

    Tanguy, P.

    1997-01-01

    In this article are evoked the question of nuclear safety and the public opinion, from the beginning of nuclear power plants in 1954 where a peaceful use of nuclear energy is developed in minds. If the aim was to avoid any important accident, the Three Miles Island accident and more recently the Chernobyl accident provoked a shock in public opinion and marked a peak of nuclear controversy. From this point, the policy of transparence and a best information of the public taken as a partner are necessary to maintain the dialogue. (N.C.)

  20. Legal Philosophy - Five Questions

    DEFF Research Database (Denmark)

    This collection gathers together a host of the most eminent contemporary legal philosophers, who writes about their take on legal philosophy, its fundamental questions and potential.......This collection gathers together a host of the most eminent contemporary legal philosophers, who writes about their take on legal philosophy, its fundamental questions and potential....

  1. Positive, negative, and bipolar questions: The effect of question polarity on ratings of text readability

    Directory of Open Access Journals (Sweden)

    Naomi Kamoen

    2013-12-01

    Full Text Available For decades, survey researchers have known that respondents give different answers to attitude questions worded positively (X is good. Agree-Disagree, negatively (X is bad. Agree-Disagree or on a bipolar scale (X is bad-good. This makes survey answers hard to interpret, especially since findings on exactly how the answers are affected are conflicting. In the current paper, we present twelve studies in which the effect of question polarity was measured for a set of thirteen contrastive adjectives. In each study, the same adjectives were used so the generalizability of wording effects across studies could be examined for each word pair. Results show that for five of the word pairs an effect of question wording can be generalized. The direction of these effects are largely consistent: respondents generally give the same answers to positive and bipolar questions, but they are more likely to disagree with negative questions than to agree with positive questions or to choose the positive side of the bipolar scale. In other words, respondents express their opinions more positively when the question is worded negatively. Even though answers to the three wording alternatives sometimes differ, results also show that reliable answers can be obtained with all three wording alternatives. So, for survey practice, these results suggest that all three wording alternatives may be used for attitude measurement.

  2. Analysis on Occupants’ Satisfaction for Safety Performance Assessment in Low Cost Housing

    Directory of Open Access Journals (Sweden)

    Husin Husrul Nizam

    2014-01-01

    Full Text Available The delivery performance of the low cost housing is questioned since the occupants are prone towards safety hazards in the housing complex, such as structural instability and falling building fragments. Without defining the occupants’ requirements for the development of low cost housing, the prevailing safety factors are hard to be determined. This paper explores the rationale of safety performance assessment in the low cost housing by considering the occupants’ participation to achieve a better safety provision during occupancy period. Questionnaire survey was distributed to 380 occupants of the low cost housing in Kuala Lumpur and Selangor, Malaysia. The result shows that 80.8% of the respondents had expressed their dissatisfaction with the safety performance of the lift. By referring to the mode of ranking level, the most significant aspect rated by the respondents is Building Safety Features, with 51.6% respondents. The attained aspects can be fundamental parameters which can be considered in the future development of low cost housing.

  3. U.S. Food System Working Conditions as an Issue of Food Safety.

    Science.gov (United States)

    Clayton, Megan L; Smith, Katherine C; Pollack, Keshia M; Neff, Roni A; Rutkow, Lainie

    2017-02-01

    Food workers' health and hygiene are common pathways to foodborne disease outbreaks. Improving food system jobs is important to food safety because working conditions impact workers' health, hygiene, and safe food handling. Stakeholders from key industries have advanced working conditions as an issue of public safety in the United States. Yet, for the food industry, stakeholder engagement with this topic is seemingly limited. To understand this lack of action, we interviewed key informants from organizations recognized for their agenda-setting role on food-worker issues. Findings suggest that participants recognize the work standards/food safety connection, yet perceived barriers limit adoption of a food safety frame, including more pressing priorities (e.g., occupational safety); poor fit with organizational strategies and mission; and questionable utility, including potential negative consequences. Using these findings, we consider how public health advocates may connect food working conditions to food and public safety and elevate it to the public policy agenda.

  4. Thousand Questions

    DEFF Research Database (Denmark)

    2012-01-01

    (perhaps as an expanded Turing test) on its listeners. These questions are extracted in real-time from Twitter with the keyword search of the ‘?’ symbol to create a spatio-temporal experience. The computerized voice the audience hears is a collective one, an entanglement of humans and non-humans......In this work the network asks “If I wrote you a love letter would you write back?” Like the love letters which appeared mysteriously on the noticeboards of Manchester University’s Computer Department in the 1950s, thousands of texts circulate as computational processes perform the questions......, that circulates across networks. If I wrote you a love letter would you write back? (and thousands of other questions’ ) (封不回的情書?千言萬語無人回 was commissioned by the Microwave International New Media Festival 2012....

  5. Waste Tank Organic Safety Project: Analysis of liquid samples from Hanford waste tank 241-C-103

    International Nuclear Information System (INIS)

    Pool, K.H.; Bean, R.M.

    1994-03-01

    A suite of physical and chemical analyses has been performed in support of activities directed toward the resolution of an Unreviewed Safety Question concerning the potential for a floating organic layer in Hanford waste tank 241-C-103 to sustain a pool fire. The analysis program was the result of a Data Quality Objectives exercise conducted jointly with staff from Westinghouse Hanford Company and Pacific Northwest Laboratory (PNL). The organic layer has been analyzed for flash point, organic composition including volatile organics, inorganic anions and cations, radionuclides, and other physical and chemical parameters needed for a safety assessment leading to the resolution of the Unreviewed Safety Question. The aqueous layer underlying the floating organic material was also analyzed for inorganic, organic, and radionuclide composition, as well as other physical and chemical properties. This work was conducted to PNL Quality Assurance impact level III standards (Good Laboratory Practices)

  6. Outstanding Questions In First Amendment Law Related To Food Labeling Disclosure Requirements For Health.

    Science.gov (United States)

    Pomeranz, Jennifer L

    2015-11-01

    The federal and state governments are increasingly focusing on food labeling as a method to support good health. Many such laws are opposed by the food industry and may be challenged in court, raising the question of what is legally feasible. This article analyzes outstanding questions in First Amendment law related to commercial disclosure requirements and conducts legal analysis and policy evaluation for three current policies. These include the Food and Drug Administration's draft regulation requiring an added sugar disclosure on the Nutrition Facts panel, California's proposed sugar-sweetened beverage safety warning label bill, and Vermont's law requiring labels of genetically engineered food to disclose this information. I recommend several methods for policy makers to enact food labeling laws within First Amendment parameters, including imposing factual commercial disclosure requirements, disclosing the government entity issuing a warning, collecting evidence, and identifying legitimate governmental interests. Project HOPE—The People-to-People Health Foundation, Inc.

  7. Problems in the assessment of inherent safety characteristics of nuclear reactors

    International Nuclear Information System (INIS)

    Garribba, S.F.; Vivante, C.

    1988-01-01

    A number of proposals are being made for an increased RD and D effort on advanced nuclear power reactors that would display outstanding safety performance. A common characteristic of the different reactor concepts would be their limited reliance upon active engineered systems under major accident conditions. However, when submitted to a more close scrutiny reactor concept options may reveal diverging safety behaviors and also development opportunities. In this respect, three issues are explored in this paper. A first question is the meaning of non-active, i.e. inherent and passive safety features. Next, is the ranking of advanced and new reactor concepts from the viewpoint of inherent and passive safety. Multiple correspondence analysis may provide a simple tool, whose use is shown for the case of HTR-500, AP600 and PRISM. Conversely, probabilistic risk assessment would allow quantitative comparisons, although lack of information and data is an obstacle. Finally, is demonstration of safety performances as a step toward market deployment of the new reactor systems

  8. Legacy question

    International Nuclear Information System (INIS)

    Healy, J.W.

    1977-01-01

    The legacy question discussed refers to the definition of appropriate actions in this generation to provide a world that will allow future generations to use the earth without excessive limitations caused by our use and disposal of potentially hazardous materials

  9. An Online National Archive of Multiple-Choice Questions for Astro 101 and the Development of the Question Complexity Rubric

    Science.gov (United States)

    Cormier, S.; Prather, E.; Brissenden, G.

    2011-09-01

    We are developing a national archive of multiple-choice questions for use in the Astronomy 101 classroom. These questions are intended to supplement an instructor's implementation of Think-Pair-Share or for their assessment purposes (i.e., exams and homework). We are also developing the Question Complexity Rubric (QCR) to guide members of the Astro 101 teaching and learning community in assisting us with hierarchically ranking questions in this archive based on their conceptual complexity. Using the QCR, a score is assigned to differentiate each question based on the cognitive steps necessary to comprehensively explain the reasoning pathway to the correct answer. The lowest QCR score is given to questions with a reasoning pathway requiring only declarative knowledge. The highest QCR score is given to questions with a reasoning pathway that requires multiple connected cognitive steps. When completed, the online question archive will provide users with the utility to 1) use the QCR to score questions 2) search for and download questions based on topic and/or QCR score, and 3) add their own questions to the archive. Stop by our poster to test your skills at determining question complexity by trying out the QCR with our sample questions.

  10. Quality management and patient safety: survey results from 102 Hungarian hospitals.

    NARCIS (Netherlands)

    Makai, P.; Klazinga, N.; Wagner, C.; Boncz, I.; Gulácsi, L.

    2009-01-01

    OBJECTIVES: The aim of this study is to describe the development of quality management systems in Hungarian hospitals. It also aims to answer the policy question, whether a separate patient safety policy should be created additional to quality policies, on national as well as hospital level. METHOD:

  11. Difficult Questions of Difficult Questions: The Role of The Researcher and Transcription Styles

    Science.gov (United States)

    Henderson, Holly

    2018-01-01

    This paper refracts a comparison of three distinct transcription styles through questions of researcher reflexivity. It uses the data from a single question asked by the researcher in multiple interviews for a small empirical project. These data are transcribed in three ways, and the resulting transcripts are discussed in relation to the analysis…

  12. The development of safety cases for healthcare services: Practical experiences, opportunities and challenges

    International Nuclear Information System (INIS)

    Sujan, Mark; Spurgeon, Peter; Cooke, Matthew; Weale, Andy; Debenham, Philip; Cross, Steve

    2015-01-01

    There has been growing interest in the concept of safety cases for medical devices and health information technology, but questions remain about how safety cases can be developed and used meaningfully in the safety management of healthcare services and processes. The paper presents two examples of the development and use of safety cases at a service level in healthcare. These first practical experiences at the service level suggest that safety cases might be a useful tool to support service improvement and communication of safety in healthcare. The paper argues that safety cases might be helpful in supporting healthcare organisations with the adoption of proactive and rigorous safety management practices. However, it is also important to consider the different level of maturity of safety management and regulatory oversight in healthcare. Adaptations to the purpose and use of safety cases might be required, complemented by the provision of education to both practitioners and regulators. - Highlights: • Empirical description of safety case development at service level in healthcare. • Safety cases can support adoption of proactive and rigorous safety management. • Adaptation to purpose and use of safety cases might be required in healthcare. • Education should be provided to practitioners and regulators

  13. Evaluation of the safety of the operating nuclear power plants built to earlier standards

    International Nuclear Information System (INIS)

    Menteseoglu, S.

    2001-01-01

    The objective of this paper is to provide practical assistance on judging the safety of a nuclear power plant, on the basis of a comparison with current safety standards and operational practices. For nuclear power plants built to earlier standards for which there are questions about the adequacy of the maintenance of the plant design and operational practices, a safety review against current standards and practices can be considered a high priority. The objective of reviewing nuclear power plants built to earlier standards against current standards and practices is to determine whether there are any deviations which would have an impact on plant safety. The safety significance of the issues identified should be judged according to their implications for plant design and operation in terms of basic safety concepts such as defence in depth and safety culture. In addition, this paper provides assistance on the prioritization of corrective measures and their implementation so as to approach an acceptable level of safety

  14. Decree No 87-137 of 2 March 1987 concerning the High Council for nuclear safety and information

    International Nuclear Information System (INIS)

    1987-01-01

    This Decree amends the Decree of 13th March 1973 setting up a High Council for Nuclear Safety. Its purpose is to widen the terms of reference of the High Council for Nuclear Safety. In addition to its responsibilities as regards the safety of nuclear installations, it is now competent in the field of information. The Council is now charged with informing the media as well as the public not only on questions of safety proper but also on incidents and accidents occurring in nuclear installations. (NEA) [fr

  15. Safety Evaluation of the ESP Sludge Washing Baselines Runs. Revision 1

    International Nuclear Information System (INIS)

    Gupta, M.K.

    1994-08-01

    The purpose is to provide the technical basis for the evaluation of Unreviewed Safety Question for the Extended Sludge Processing (ESP) Sludge Washing Baseline Runs. The Baseline runs are necessary: to ascertain the mechanical fitness of the equipment and modifications not operated since 1988 and to resolve technical questions associated with process control; i.e., sludge suspension, sludge settling, heat transfer, and temperature control. These issues need to be resolved prior to resumption of normal ESP operations. The equipment used for the Baseline runs are Tanks 42H and 51H and their associated equipment

  16. Safety assessment and surveillance of decommissioning operations at DOE's nuclear facilities

    International Nuclear Information System (INIS)

    Cowgill, M.G.; Prochnow, D.; Worthington, P.R.

    1995-01-01

    A description is provided of a systematic approach currently being developed and deployed at the Department of Energy to obtain assurance that post-operational activities at nuclear facilities will be conducted in a safe manner. Using this approach, personnel will have available a formalized set of safety principles and associated question sets to assist them in the conducting of safety assessments and surveillance. Information gathered through this means will also be analyzed to determine if there are any generic complex-wide strengths or deficiencies associated with decommissioning activities and to which attention should be drawn

  17. Question, answer, compare: a cross-category comparison of answers on question and answer websites

    Science.gov (United States)

    Ocepek, Melissa G.; Westbrook, Lynn

    2015-10-01

    Online information seekers make heavy use of websites that accept their natural language questions. This study compared the three types of such websites: social question and answer (Q&A), digital reference services, and ask-an-expert services. Questions reflecting daily life, research, and crisis situations were posed to high use websites of all three types. The resulting answers' characteristics were analyzed in terms of speed, transparency, formality, and intimacy. The results indicate that social Q&A websites excel in speed, ask-an-expert websites in intimacy, and digital reference services in transparency and formality.

  18. Examining the Impact of Question Surface Features on Students' Answers to Constructed-Response Questions on Photosynthesis

    Science.gov (United States)

    Weston, Michele; Haudek, Kevin C.; Prevost, Luanna; Urban-Lurain, Mark; Merrill, John

    2015-01-01

    One challenge in science education assessment is that students often focus on surface features of questions rather than the underlying scientific principles. We investigated how student written responses to constructed-response questions about photosynthesis vary based on two surface features of the question: the species of plant and the order of…

  19. Generic Drugs: Questions and Answers

    Science.gov (United States)

    ... Vaccines, Blood & Biologics Animal & Veterinary Cosmetics Tobacco Products Drugs Home Drugs Resources for You Information for Consumers (Drugs) Questions & Answers Generic Drugs: Questions & Answers Share Tweet Linkedin Pin it More ...

  20. Questions concerning safety and risk after the nuclear accidents in Japan. Deepened accident analysis for the Fukushima Daiichi power plant; Sicherheits- und Risikofragen im Nachgang zu den nuklearen Stoer- und Unfaellen in Japan. Vertiefte Ereignisanalyse zur Anlage Fukushima-Daini

    Energy Technology Data Exchange (ETDEWEB)

    Pistner, Christoph; Englert, Matthias [Oeko-Institut e.V. - Institut fuer Angewandte Oekologie, Darmstadt (Germany)

    2015-02-25

    The study questions concerning safety and risk in Japanese power plants following the disastrous nuclear accident covers the following issues: the nuclear facility Fukushima Daiichi, site characterization, important technical equipment, important electro-technical equipment, personal; description of the accident progression in the Fukushima nuclear power plant: impact of the earthquake, impact of the tsunami, short-term measures of the operating personnel, pressure and temperature situation in the containments, restoration of the after-heat cooling system in the units 1/2 and 4, fuel element storage pool, summarized parameters during the accident progress; comparative analysis of the accident progression at the Fukushima Daiichi site.

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

    Science.gov (United States)

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

    2015-01-01

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

  2. Geotechnical aspects of site evaluation and foundations for nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2003-01-01

    This publication is a revision of the former safety standards of IAEA Safety Series No. 50-SG-S8. The scope has been extended to cover not only foundations but also design questions related to geotechnical science and engineering, such as the bearing capacity of foundations, design of earth structures and design of buried structures. Seismic aspects also play an important role in this field, and consequently the Safety Guide on Evaluation of Seismic Hazards for Nuclear Power Plants, Safety Standards Series No. NS-G-3.3, which discusses the determination of seismic input motion, is referenced on several occasions. The present Safety Guide provides an interpretation of the Safety Requirements on Site Evaluation for Nuclear Installations and guidance on how to implement them. It is intended for the use of safety assessors or regulators involved in the licensing process as well as the designers of nuclear power plants, and it provides them with guidance on the methods and procedures for analyses to support the assessment of the geotechnical aspects of the safety of nuclear power plants

  3. Geotechnical aspects of site evaluation and foundations for nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2006-01-01

    This publication is a revision of the former safety standards of IAEA Safety Series No. 50-SG-S8. The scope has been extended to cover not only foundations but also design questions related to geotechnical science and engineering, such as the bearing capacity of foundations, design of earth structures and design of buried structures Seismic aspects also play an important role in this field, and consequently the Safety Guide on Evaluation of Seismic Hazards for Nuclear Power Plants, Safety Standards Series No. NS-G-3.3, which discusses the determination of seismic input motion, is referenced on several occasions. The present Safety Guide provides an interpretation of the Safety Requirements on Site Evaluation for Nuclear Installations and guidance on how to implement them. It is intended for the use of safety assessors or regulators involved in the licensing process as well as the designers of nuclear power plants, and it provides them with guidance on the methods and procedures for analyses to support the assessment of the geotechnical aspects of the safety of nuclear power plants

  4. RESI-1 and RESI-2: pPrototypes of an information system on reactor safety

    International Nuclear Information System (INIS)

    Schultheiss, G.F.; Eglin, W.; Katz, F.W.; Krings, T.; Pee, A.; Schlechtendahl, E.G.

    1975-04-01

    To demonstrate by practical experience the feasibility of the information system elaborated in the 'Study of an Information System on Reactor Safety RESI' (KFK 1900), the prototype systems RESI-1 and RESI-2 were developed and tested in operation. The two systems have been considerably reduced both in extent and contents as compared to the information system described in the study. The RESI-1 prototype system is a paper version established for verification of all the individual functions before passing over to the computer-aided interactive version RESI-2. RESI-2 is based on the GOLEM system of Siemens. Both protoype systems have proved that the essential features: 1) documentation, 2) formulation of and answering to safety questions, which are relevant with respect to particular licensing cases, 3) formulation of safety questions related to individual reactor types can be managed satisfactorily. All the functions of information retrieval have been tested carefully over several months. Particularities of project development and of the methods elaborated are described in detail and presented in this report. (orig.) [de

  5. Comparison of Performance on Multiple-Choice Questions and Open-Ended Questions in an Introductory Astronomy Laboratory

    Science.gov (United States)

    Wooten, Michelle M.; Cool, Adrienne M.; Prather, Edward E.; Tanner, Kimberly D.

    2014-01-01

    When considering the variety of questions that can be used to measure students' learning, instructors may choose to use multiple-choice questions, which are easier to score than responses to open-ended questions. However, by design, analyses of multiple-choice responses cannot describe all of students' understanding. One method that can…

  6. 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)

  7. Nuclear safety: what is the price to pay? Press file

    International Nuclear Information System (INIS)

    Lheureux, Yves; Leclerc, Nathalie

    2016-01-01

    After having outlined that the ANCCLI's concern about French contradictions in the field of nuclear safety, this publication proposes an overview of the situation of nuclear safety in France in 2016 from the ANCCLI's point of view: big lessons and (too) small changes after Chernobyl and Fukushima, what has changed since Chernobyl and Fukushima. It outlines why emergency measures are not adapted according to the work of the joint ANCCLI-ACRO scientific committee. The following issues are thus commented: too many remaining questions, age and safety level of a nuclear plant, the specific intervention plans (PPI), sheltering, iodine distribution, population evacuation, evacuation time about nuclear sites, hosting sites in case of evacuation, refugees, safety and security. Recommendations are then given, based on European, Japanese, American, Canadian and Indian experiences. The project of a white paper on the post-accidental situation is presented. Several illustrations are proposed about some of the above issues

  8. Questioning context: a set of interdisciplinary questions for investigating contextual factors affecting health decision making

    Science.gov (United States)

    Charise, Andrea; Witteman, Holly; Whyte, Sarah; Sutton, Erica J.; Bender, Jacqueline L.; Massimi, Michael; Stephens, Lindsay; Evans, Joshua; Logie, Carmen; Mirza, Raza M.; Elf, Marie

    2011-01-01

    Abstract Objective  To combine insights from multiple disciplines into a set of questions that can be used to investigate contextual factors affecting health decision making. Background  Decision‐making processes and outcomes may be shaped by a range of non‐medical or ‘contextual’ factors particular to an individual including social, economic, political, geographical and institutional conditions. Research concerning contextual factors occurs across many disciplines and theoretical domains, but few conceptual tools have attempted to integrate and translate this wide‐ranging research for health decision‐making purposes. Methods  To formulate this tool we employed an iterative, collaborative process of scenario development and question generation. Five hypothetical health decision‐making scenarios (preventative, screening, curative, supportive and palliative) were developed and used to generate a set of exploratory questions that aim to highlight potential contextual factors across a range of health decisions. Findings  We present an exploratory tool consisting of questions organized into four thematic domains – Bodies, Technologies, Place and Work (BTPW) – articulating wide‐ranging contextual factors relevant to health decision making. The BTPW tool encompasses health‐related scholarship and research from a range of disciplines pertinent to health decision making, and identifies concrete points of intersection between its four thematic domains. Examples of the practical application of the questions are also provided. Conclusions  These exploratory questions provide an interdisciplinary toolkit for identifying the complex contextual factors affecting decision making. The set of questions comprised by the BTPW tool may be applied wholly or partially in the context of clinical practice, policy development and health‐related research. PMID:21029277

  9. Problems of making decisions with account of risk and safety factors

    Energy Technology Data Exchange (ETDEWEB)

    Larichev, O I

    1987-01-01

    New trends in making decisions on accidents when using large-scale technologies-NPPs, chemical plants etc., are considered. Three main directions in the investigations in this field are distinguished. One of them consists in risk measuring (its perception by people, ways of its quantitative determination). The second direction consists in increasing the safety of large-scale production systems. Here the following questions are considered: risk assessment (the safety standard statement), site selection for new systems, man-machine interaction problems, development of safer technologies, cost benefit safety analysis. The third direction is connected with the problem of accidents and their analysis. This direction includes considering the reasons and process of the accident development, preparing for the possible accidents, monitoring under extreme conditions, accident effect analysis.

  10. Problems of making decisions with account of risk and safety factors

    International Nuclear Information System (INIS)

    Larichev, O.I.

    1987-01-01

    New trends in making decisions on accidents when using large-scale technologies-NPPs, chemical plants etc., are considered. Three main directions in the investigations in this field are distinguished. One of them consists in risk measuring (its perception by people, ways of its quantitative determination). The second direction consists in increasing the safety of large-scale production systems. Here the following questions are considered: risk assessment (the safety standard statement), site selection for new systems, man-machine interaction problems, development of safer technologies, cost benefit safety analysis. The third direction is connected with the problem of accidents and their analysis. This direction includes considering the reasons and process of the accident development, preparing for the possible accidents, monitoring under extreme conditions, accident effect analysis

  11. Annotating Logical Forms for EHR Questions.

    Science.gov (United States)

    Roberts, Kirk; Demner-Fushman, Dina

    2016-05-01

    This paper discusses the creation of a semantically annotated corpus of questions about patient data in electronic health records (EHRs). The goal is to provide the training data necessary for semantic parsers to automatically convert EHR questions into a structured query. A layered annotation strategy is used which mirrors a typical natural language processing (NLP) pipeline. First, questions are syntactically analyzed to identify multi-part questions. Second, medical concepts are recognized and normalized to a clinical ontology. Finally, logical forms are created using a lambda calculus representation. We use a corpus of 446 questions asking for patient-specific information. From these, 468 specific questions are found containing 259 unique medical concepts and requiring 53 unique predicates to represent the logical forms. We further present detailed characteristics of the corpus, including inter-annotator agreement results, and describe the challenges automatic NLP systems will face on this task.

  12. Generating ethnographic research questions

    DEFF Research Database (Denmark)

    Friberg, Torbjörn

    2015-01-01

    ? By drawing on the conceptual history of anthropology, the aim of this article is to generate ethnographic-oriented research questions concerned with higher education. The first part of the article provides an ethnographic background, while the second part focuses on Paul Willis's reasoning on ethnographic......As part of recent complex transformations, it seems that higher educational organisations are being forced to reorganise, standardise and streamline in order to survive in the new political and economic context. How are ethnographers in general going to approach these contemporary phenomena...... imagination, as a prerequisite for generating alternative research questions. The third part makes explicit anthropologist Maurice Godelier's theoretical imagination, carving out some specific theoretical parts which may be used in the generating process. The conclusion then suggests a number of questions...

  13. Assessing progress in the development of safety culture

    International Nuclear Information System (INIS)

    Rotaru, Ioan; Ghita, Sorin

    1999-01-01

    The concept of safety culture was introduced by the International Nuclear Safety Advisory Group (INSAG) in the Summary Report on the Post-Accident Meeting on the Chernobyl Accident in 1986. The concept was further expanded in the 1988 INSAG-3 report, Basic Safety Principles for Nuclear Power Plants, and again in 1991 in the INSAG-4 report. Recognizing the increasing role that safety culture is expected to play in nuclear installations worldwide, the Convention on Nuclear Safety states the Contracting Parties' desire 'to promote an effective nuclear safety culture'. The concept of safety culture is defined in INSAG-4 as follows: Safety culture is that assembly of characteristics and attitudes in organizations and individuals which establishes that, as an overriding priority, nuclear plant safety issues receive the attention warranted by their significance. Safety culture is also an amalgamation of values, standards, morals and norms of acceptable behaviour. These are aimed at maintaining a self disciplined approach to the enhancement of safety beyond legislative and regulatory requirements. Therefore, the safety culture has to be inherent in the thoughts and actions of all the individuals at every level in an organization. The leadership provided by top management is crucial. Safety culture applies to conventional and personal safety as well as nuclear safety. All safety consideration are affected by common points of beliefs, attitudes, behaviour, and cultural differences, closely linked to a shared system of values and standards. The paper poses questions and tries to find answers relative to issues like: - how to assess progress; - specific organizational indicators of a progressive safety culture; - detection of incipient weaknesses in safety culture (organizational issues, employee issues, technology issues); - revitalizing a weakened safety culture; - overall assesment of safety culture; - general evaluation model. In conclusion, there is no consistent and

  14. Supplementary safety system 1/4 scale testing

    Energy Technology Data Exchange (ETDEWEB)

    Garrett, R.L.; Paik, I.K.

    1993-09-01

    During the course of updating the K-Reactor Safety Analysis Report Chapter 15 in 1990, it was identified that the current Supplementary Safety System (SSS) may not be adequate in protecting the reactor during the process water pump coastdown initiated by a loss of AC power when the safety rods are assumed to fail. A SSS modification project was initiated to add an additional ink injection pathway near the pump suction. In addition, the Department of Energy raised a question on the thermal buoyancy effects on moderator flow pattern and ink dispersion in the moderator space. The development and documentation of a two-dimensional code called MODFLOW was undertaken to describe the problem. This report discusses the results of the moderator flow and ink (Gadolinium Poison Solution - GPS) dispersion tests designed to provide qualified data for validation and benchmarking of the MODFLOW computer code with the secondary objectives being the development of concentration profiles and video footage of simulated GPS dispersion under steady-state and transient flow conditions.

  15. An online expert network for high quality information on occupational safety and health: cross-sectional study of user satisfaction and impact

    NARCIS (Netherlands)

    Rhebergen, Martijn D. F.; Lenderink, Annet F.; van Dijk, Frank J. H.; Hulshof, Carel T. J.

    2011-01-01

    Many people have difficulties finding information on health questions, including occupational safety and health (OSH) issues. One solution to alleviate these difficulties could be to offer questioners free-of-charge, online access to a network of OSH experts who provide tailored, high-quality

  16. 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...

  17. Effectiveness of the Convention on Nuclear Safety

    International Nuclear Information System (INIS)

    Schwarz, G.

    2016-01-01

    The Convention on Nuclear Safety (CNS) has been established after the Chernobyl accident with the primary objective of achieving and maintaining a high level of nuclear safety worldwide, through the enhancement of national measures and international cooperation. The CNS is an incentive convention. It defines the basic safety standard which shall be met by the Contracting Parties. The verification of compliance is based on a self-assessment by the Countries and a Peer Review by the other Contracting Parties. As of July 2015, there are 78 Contracting Parties. Among the Contracting Parties of the Convention are all countries operating nuclear power plants except the Islamic Republic of Iran and Taiwan, all countries constructing nuclear power plants, all countries having nuclear power plants in long term shutdown and all countries having signed contracts for the construction of nuclear power plants. The National Reports under the CNS therefore cover almost all nuclear power plants of the world. The peer review of reports, questions and answers that are exchanged in connection with the Review Meetings provided a unique overview of nuclear safety provisions and issues in countries planning or operating nuclear power plants. This is especially important for neighbouring countries to those operating nuclear power plants.

  18. Instance-Based Question Answering

    Science.gov (United States)

    2006-12-01

    cluster-based query expan- sion, learning answering strategies, machine learning in NLP To my wife Monica Abstract During recent years, question...process is typically tedious and involves expertise in crafting and implement- ing these models (e.g. rule-based), utilizing NLP resources, and...questions. For languages that use capitalization (e.g. not Chinese or Arabic ) for named entities, IBQA can make use of NE classing (e.g. “Bob Marley

  19. Understanding Super-Earths with MINERVA-Australis at USQ's Mount Kent Observatory

    Science.gov (United States)

    Wittenmyer, Robert; Horner, Jonathan; Kane, Stephen; Plavchan, Peter; Ciardi, David; Eastman, Jason; Johnson, John Asher; Wright, Jason; McCrady, Nate; MINERVA Collaboration

    2018-01-01

    Super Earths, planets between 5-10 Earth masses, are the most common types of planets known, yet are completely absent from our Solar system. As a result, their detailed properties, compositions, and formation mechanisms are poorly understood. NASA's Transiting Exoplanet Survey Satellite (TESS) will identify hundreds of Super-Earths orbiting bright stars, for the first time allowing in-depth characterisation of these planets. At the University of Southern Queensland, we are host to the MINERVA-Australis project, dedicated wholly to the follow-up characterisation and mass measurement of TESS planets. We give an update on the status of MINERVA-Australis and our expected performance. We also present results from the fully operational Northern MINERVA array, with the primary mission of discovering rocky planets orbiting 80 nearby bright stars.

  20. Advances in operational safety and severe accident research

    Energy Technology Data Exchange (ETDEWEB)

    Simola, K. [VTT Automation (Finland)

    2002-02-01

    A project on reactor safety was carried out as a part of the NKS programme during 1999-2001. The objective of the project was to obtain a shared Nordic view of certain key safety issues related to the operating nuclear power plants in Finland and Sweden. The focus of the project was on selected central aspects of nuclear reactor safety that are of common interest for the Nordic nuclear authorities, utilities and research bodies. The project consisted of three sub-projects. One of them concentrated on the problems related to risk-informed deci- sion making, especially on the uncertainties and incompleteness of probabilistic safety assessments and their impact on the possibilities to use the PSA results in decision making. Another sub-project dealt with questions related to maintenance, such as human and organisational factors in maintenance and maintenance management. The focus of the third sub-project was on severe accidents. This sub-project concentrated on phenomenological studies of hydrogen combustion, formation of organic iodine, and core re-criticality due to molten core coolant interaction in the lower head of reactor vessel. Moreover, the current status of severe accident research and management was reviewed. (au)