WorldWideScience

Sample records for safety improvement program

  1. Gap Analysis Approach for Construction Safety Program Improvement

    Directory of Open Access Journals (Sweden)

    Thanet Aksorn

    2007-06-01

    Full Text Available To improve construction site safety, emphasis has been placed on the implementation of safety programs. In order to successfully gain from safety programs, factors that affect their improvement need to be studied. Sixteen critical success factors of safety programs were identified from safety literature, and these were validated by safety experts. This study was undertaken by surveying 70 respondents from medium- and large-scale construction projects. It explored the importance and the actual status of critical success factors (CSFs. Gap analysis was used to examine the differences between the importance of these CSFs and their actual status. This study found that the most critical problems characterized by the largest gaps were management support, appropriate supervision, sufficient resource allocation, teamwork, and effective enforcement. Raising these priority factors to satisfactory levels would lead to successful safety programs, thereby minimizing accidents.

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

    Science.gov (United States)

    1998-08-26

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

  3. Safety implications of standardized continuous quality improvement programs in community pharmacy.

    Science.gov (United States)

    Boyle, Todd A; Ho, Certina; Mackinnon, Neil J; Mahaffey, Thomas; Taylor, Jeffrey M

    2013-06-01

    Standardized continuous quality improvement (CQI) programs combine Web-based technologies and standardized improvement processes, tools, and expectations to enable quality-related events (QREs) occurring in individual pharmacies to be shared with pharmacies in other jurisdictions. Because standardized CQI programs are still new to community pharmacy, little is known about how they impact medication safety. This research identifies key aspects of medication safety that change as a result of implementing a standardized CQI program. Fifty-three community pharmacies in Nova Scotia, Canada, adopted the SafetyNET-Rx standardized CQI program in April 2010. The Institute for Safe Medication Practices (ISMP) Canada's Medication Safety Self-Assessment (MSSA) survey was administered to these pharmacies before and 1 year into their use of the SafetyNET-Rx program. The nonparametric Wilcoxon signed-rank test was used to explore where changes in patient safety occurred as a result of SafetyNETRx use. Significant improvements occurred with quality processes and risk management, staff competence, and education, and communication of drug orders and other information. Patient education, environmental factors, and the use of devices did not show statistically significant changes. As CQI programs are designed to share learning from QREs, it is reassuring to see that the largest improvements are related to quality processes, risk management, staff competence, and education.

  4. Effect of generic issues program on improving safety

    International Nuclear Information System (INIS)

    Fard, M. R.; Kauffman, J. V.

    2010-01-01

    The U.S. Nuclear Regulatory Commission (NRC) identifies (by its assessment of plant operation) certain issues involving public health and safety, the common defense and security, or the environment that could affect multiple entities under NRC jurisdiction. The Generic Issues Program (GIP) addresses the resolution of these Generic Issues (GIs). The resolution of these issues may involve new or revised rules, new or revised guidance, or revised interpretation of rules or guidance that affect nuclear power plant licensees, nuclear material certificate holders, or holders of other regulatory approvals. U.S. NRC provides information related to the past and ongoing GIP activities to the general public by the use of three main resources, namely NUREG-0933, 'Resolution of Generic Safety Issues, ' Generic Issues Management Control System (GIMCS), and GIP public web page. GIP information resources provide information such as historical information on resolved GIs, current status of the open GIs, policy documents, program procedures, GIP annual and quarterly reports and the process to contact GIP and propose a GI This paper provides an overview of the GIP and several examples of safety improvements resulting from the resolution of GIs. In addition, the paper provides a brief discussion of a few recent GIs to illustrate how the program functions to improve safety. (authors)

  5. Federal Aviation Administration weather program to improve aviation safety

    Science.gov (United States)

    Wedan, R. W.

    1983-01-01

    The implementation of the National Airspace System (NAS) will improve safety services to aviation. These services include collision avoidance, improved landing systems and better weather data acquisition and dissemination. The program to improve the quality of weather information includes the following: Radar Remote Weather Display System; Flight Service Automation System; Automatic Weather Observation System; Center Weather Processor, and Next Generation Weather Radar Development.

  6. The association between event learning and continuous quality improvement programs and culture of patient safety.

    Science.gov (United States)

    Mazur, Lukasz; Chera, Bhishamjit; Mosaly, Prithima; Taylor, Kinley; Tracton, Gregg; Johnson, Kendra; Comitz, Elizabeth; Adams, Robert; Pooya, Pegah; Ivy, Julie; Rockwell, John; Marks, Lawrence B

    2015-01-01

    To present our approach and results from our quality and safety program and to report their possible impact on our culture of patient safety. We created an event learning system (termed a "good catch" program) and encouraged staff to report any quality or safety concerns in real time. Events were analyzed to assess the utility of safety barriers. A formal continuous quality improvement program was created to address these reported events and make improvements. Data on perceptions of the culture of patient safety were collected using the Agency for Health Care Research and Quality survey administered before, during, and after the initiatives. Of 560 good catches reported, 367 could be ascribed to a specific step on our process map. The calculated utility of safety barriers was highest for those embedded into the pretreatment quality assurance checks performed by physicists and dosimetrists (utility score 0.53; 93 of 174) and routine checks done by therapists on the initial day of therapy. Therapists and physicists reported the highest number of good catches (24% each). Sixty-four percent of events were caused by performance issues (eg, not following standardized processes, including suboptimal communications). Of 31 initiated formal improvement events, 26 were successfully implemented and sustained, 4 were discontinued, and 1 was not implemented. Most of the continuous quality improvement program was conducted by nurses (14) and therapists (7). Percentages of positive responses in the patient safety culture survey appear to have increased on all dimensions (p continuous quality improvement programs can be successfully implemented and that there are contemporaneous improvements in the culture of safety. Copyright © 2015 American Society for Radiation Oncology. Published by Elsevier Inc. All rights reserved.

  7. Safety performance indicators program

    International Nuclear Information System (INIS)

    Vidal, Patricia G.

    2004-01-01

    In 1997 the Nuclear Regulatory Authority (ARN) initiated a program to define and implement a Safety Performance Indicators System for the two operating nuclear power plants, Atucha I and Embalse. The objective of the program was to incorporate a set of safety performance indicators to be used as a new regulatory tool providing an additional view of the operational performance of the nuclear power plants, improving the ability to detect degradation on safety related areas. A set of twenty-four safety performance indicators was developed and improved throughout pilot implementation initiated in July 1998. This paper summarises the program development, the main criteria applied in each stage and the results obtained. (author)

  8. West Virginia peer exchange : streamlining highway safety improvement program project delivery.

    Science.gov (United States)

    2015-01-01

    The West Virginia Division of Highways (WV DOH) hosted a Peer Exchange to share information and experiences : for streamlining Highway Safety Improvement Program (HSIP) project delivery. The event was held September : 22 to 23, 2014 in Charleston, We...

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2009-07-01

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

  10. 77 FR 70409 - System Safety Program

    Science.gov (United States)

    2012-11-26

    ...-0060, Notice No. 2] 2130-AC31 System Safety Program AGENCY: Federal Railroad Administration (FRA... rulemaking (NPRM) published on September 7, 2012, FRA proposed regulations to require commuter and intercity passenger railroads to develop and implement a system safety program (SSP) to improve the safety of their...

  11. IMPROVING PATIENT SAFETY:

    DEFF Research Database (Denmark)

    Bagger, Bettan; Taylor Kelly, Hélène; Hørdam, Britta

    Improving patient safety is both a national and international priority as millions of patients Worldwide suffer injury or death every year due to unsafe care. University College Zealand employs innovative pedagogical approaches in educational design. Regional challenges related to geographic......, social and cultural factors have resulted in a greater emphasis upon digital technology. Attempts to improve patient safety by optimizing students’ competencies in relation to the reporting of clinical errors, has resulted in the development of an interdisciplinary e-learning concept. The program makes...

  12. Safety culture improvement. An adaptive management framework

    International Nuclear Information System (INIS)

    Obadia, Isaac Jose

    2005-01-01

    After the Chernobyl nuclear accident in 1986, the International Atomic Energy Agency (IAEA) established the safety culture concept as a proactive mean to contribute to safety improvement, starting a worldwide safety culture enhancement program within nuclear organizations mainly focused on nuclear power plants. More recently, the safety culture concept has been extended to non-power applications such as nuclear research reactors and nuclear technological research and development organizations. In 1999, the Nuclear Engineering Institute (IEN), a research and technological development unit of the Brazilian Nuclear Energy Commission (CNEN), started a management change program aiming at improving its performance level of excellence. This change program has been developed assuming the occurrence of complex causal inter-relationships between the organizational culture and the implementation of the management process. A systematic and adaptive management framework comprised of a safety culture improvement practice integrated to a management process based on the Criteria for Excellence of the Brazilian Quality Award Model, has been developed and implemented at IEN. The case study has demonstrated that the developed framework makes possible an effective safety culture improvement and simultaneously facilitates an effective implementation of the management process, thus providing some governance to the change program. (author)

  13. Nuclear safety in Slovak Republic. Status of safety improvements

    International Nuclear Information System (INIS)

    Toth, A.

    1999-01-01

    Status of the safety improvements at Bohunice V-1 units concerning WWER-440/V-230 design upgrading were as follows: supplementing of steam generator super-emergency feed water system; higher capacity of emergency core cooling system; supplementing of automatic links between primary and secondary circuit systems; higher level of secondary system automation. The goal of the modernization program for Bohunice V-1 units WWER-440/V-230 was to increase nuclear safety to the level of the proposals and IAEA recommendations and to reach probability goals of the reactor concerning active zone damage, leak of radioactive materials, failures of safety systems and damage shields. Upgrading program for Mochovce NPP - WWER-440/V-213 is concerned with improving the integrity of the reactor pressure vessel, steam generators 'leak before break' methods applied for the NPP, instrumentation and control of safety systems, diagnostic systems, replacement of in-core monitoring system, emergency analyses, pressurizers safety relief valves, hydrogen removal system, seismic evaluations, non-destructive testing, fire protection. Implementation of quality assurance has a special role in improvement of operational safety activities as well as safety management and safety culture, radiation protection, decommissioning and waste management and training. The Year 2000 problem is mentioned as well

  14. 75 FR 15484 - Railroad Safety Technology Program Grant Program

    Science.gov (United States)

    2010-03-29

    ... governments for projects that have a public benefit of improved railroad safety and efficiency. The program... State and local governments for projects * * * that have a public benefit of improved safety and network... minimum 20 percent grantee cost share (cash or in-kind) match requirement. DATES: FRA will begin accepting...

  15. Current activities on safety improvement at Ukrainian NPPs

    International Nuclear Information System (INIS)

    Stovbun, V.V.

    2000-01-01

    This report describes general development status of the national programs on safety improvement of the Ukrainian NPPs, basic approaches adopted for planning and implementation of safety improvement works, and state of implementation of principal technical activities aimed at safety improvement of Ukrainian NPPs. (author)

  16. Safety goals and safety culture opening plenary. 1. WANO's Role in Maintaining and Improving Safety Culture

    International Nuclear Information System (INIS)

    Tsutsumi, Ryosuke

    2001-01-01

    Over the past several years, operators of the world's nuclear plants have compiled an increasingly impressive record of operational performance. Among the many factors that have led to this improvement are the unprecedented cooperation and information exchange among the world's nuclear operators. This paper presents the World Association of Nuclear Operators (WANO) operating experience program and WANO peer review program as examples of the kinds of interaction that are occurring around the globe to maintain and improve the nuclear safety culture. In addition, some unique features of WANO are discussed. WANO has established four programs to help its members communicate effectively with each other. These include the exchange of operating experiences, voluntary peer reviews, professional and technical development, and technical support and exchange. The operating experience program alerts members to events that have occurred at other NPPs and enables members to take appropriate actions to prevent event recurrence. When an event occurs at a plant, management at that plant analyses the event and completes an event report, which is then sent to the WANO regional center to which the plant belongs. After a regional center review and necessary iteration, the report is posted onto the WANO Web site to make it available to all WANO members. By the end of 2000, more than 1500 event reports had been posted. The WANO Peer Review Program is a unique opportunity for members to learn and share the best worldwide insights into safe and reliable nuclear operations. The peer review program has become one of WANO's most important activities containing all essential elements of WANO's mission. A WANO peer review team consists of 15 to 16 people with NPP experience; most team members are from countries outside the one that they are visiting. These teams of peers from plants around the world visit host plants upon request to identify strengths and areas for improvement, with a strong

  17. An integrated approach for improving occupational health and safety management: the voluntary protection program in Taiwan.

    Science.gov (United States)

    Su, Teh-Sheng; Tsai, Way-Yi; Yu, Yi-Chun

    2005-05-01

    A voluntary compliance program for occupational health and safety management, Voluntary Protection Programs (VPP), was implemented with a strategy of cooperation and encouragement in Taiwan. Due to limitations on increasing the human forces of inspection, a regulatory-based guideline addressing the essence of Occupational Health and Safety Management Systems (OHSMS) was promulgated, which combined the resources of third parties and insurance providers to accredit a self-improving worksite with the benefits of waived general inspection and a merit contributing to insurance premium payment reduction. A designated institute accepts enterprise's applications, performs document review and organizes the onsite inspection. A final review committee of Council of Labor Affairs (CLA) confers a two-year certificate on an approved site. After ten years, the efforts have shown a dramatic reduction of occupational injuries and illness in the total number of 724 worksites granted certification. VPP worksites, in comparison with all industries, had 49% lower frequency rate in the past three years. The severity rate reduction was 80% in the same period. The characteristics of Taiwan VPP program and international occupational safety and health management programs are provided. A Plan-Do-Check-Act management cycle was employed for pursuing continual improvements to the culture fostered. The use of a quantitative measurement for assessing the performance of enterprises' occupational safety and health management showed the efficiency of the rating. The results demonstrate that an employer voluntary protection program is a promising strategy for a developing country.

  18. Aviation Safety/Automation Program Conference

    Science.gov (United States)

    Morello, Samuel A. (Compiler)

    1990-01-01

    The Aviation Safety/Automation Program Conference - 1989 was sponsored by the NASA Langley Research Center on 11 to 12 October 1989. The conference, held at the Sheraton Beach Inn and Conference Center, Virginia Beach, Virginia, was chaired by Samuel A. Morello. The primary objective of the conference was to ensure effective communication and technology transfer by providing a forum for technical interchange of current operational problems and program results to date. The Aviation Safety/Automation Program has as its primary goal to improve the safety of the national airspace system through the development and integration of human-centered automation technologies for aircraft crews and air traffic controllers.

  19. Strategies to Improve Management of Shoulder Dystocia Under the AHRQ Safety Program for Perinatal Care.

    Science.gov (United States)

    McArdle, Jill; Sorensen, Asta; Fowler, Christina I; Sommerness, Samantha; Burson, Katrina; Kahwati, Leila

    2018-03-01

    To assess implementation of safety strategies to improve management of births complicated by shoulder dystocia in labor and delivery units. Mixed-methods implementation evaluation. Labor and delivery units (N = 18) in 10 states participating in the Safety Program for Perinatal Care (SPPC). Shoulder dystocia is unpredictable, requiring rapid and coordinated action. Key informants were labor and delivery unit staff who implemented SPPC safety strategies. The SPPC was implemented by using the TeamSTEPPS teamwork and communication framework and tools, applying safety science principles (standardization, independent checks, and learn from defects) to shoulder dystocia management, and establishing an in situ simulation program focused on shoulder dystocia to practice teamwork and communication skills. Unit staff received training, a toolkit, technical assistance, and unit-specific feedback reports. Quantitative data on unit-reported process improvement measures and qualitative data from staff interviews were used to understand changes in use of safety principles, teamwork/communication, and in situ simulation. Use of shoulder dystocia safety strategies improved on the units. Differences between baseline and follow-up (10 months) were as follows: in situ simulation (50% vs. 89%), teamwork and communication (67% vs. 94%), standardization (67% to 94%), learning from defects (67% vs. 89%), and independent checks (56% vs. 78%). Interview data showed reasons to address management of shoulder dystocia, various approaches to implement safety practices, and facilitators and barriers to implementation. Successful management of shoulder dystocia requires a rapid, standardized, and coordinated response. The SPPC strategies to increase safety of shoulder dystocia management are scalable, replicable, and adaptable to unit needs and circumstances. Copyright © 2018 AWHONN, the Association of Women's Health, Obstetric and Neonatal Nurses. Published by Elsevier Inc. All rights

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2009-07-01

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

  1. Effective safety training program design

    International Nuclear Information System (INIS)

    Chilton, D.A.; Lombardo, G.J.; Pater, R.F.

    1991-01-01

    Changes in the oil industry require new strategies to reduce costs and retain valuable employees. Training is a potentially powerful tool for changing the culture of an organization, resulting in improved safety awareness, lower-risk behaviors and ultimately, statistical improvements. Too often, safety training falters, especially when applied to pervasive, long-standing problems. Stepping, Handling and Lifting injuries (SHL) more commonly known as back injuries and slips, trips and falls have plagued mankind throughout the ages. They are also a major problem throughout the petroleum industry. Although not as widely publicized as other immediately-fatal accidents, injuries from stepping, materials handling, and lifting are among the leading causes of employee suffering, lost time and diminished productivity throughout the industry. Traditional approaches have not turned the tide of these widespread injuries. a systematic safety training program, developed by Anadrill Schlumberger with the input of new training technology, has the potential to simultaneously reduce costs, preserve employee safety, and increase morale. This paper: reviews the components of an example safety training program, and illustrates how a systematic approach to safety training can make a positive impact on Stepping, Handling and Lifting injuries

  2. West Virginia Peer Exchange : Streamlining Highway Safety Improvement Program Project Delivery - An RSPCB Peer Exchange

    Science.gov (United States)

    2014-09-01

    The West Virginia Division of Highways (WV DOH) hosted a Peer Exchange to share information and experiences for streamlining Highway Safety Improvement Program (HSIP) project delivery. The event was held September 23 to 24, 2014 in Charleston, West V...

  3. Improving nuclear safety at international research reactors: The Integrated Research Reactor Safety Enhancement Program (IRRSEP)

    International Nuclear Information System (INIS)

    Huizenga, David; Newton, Douglas; Connery, Joyce

    2002-01-01

    Nuclear energy continues to play a major role in the world's energy economy. Research and test reactors are an important component of a nation's nuclear power infrastructure as they provide training, experiments and operating experience vital to developing and sustaining the industry. Indeed, nations with aspirations for nuclear power development usually begin their programs with a research reactor program. Research reactors also are vital to international science and technology development. It is important to keep them safe from both accident and sabotage, not only because of our obligation to prevent human and environmental consequence but also to prevent corresponding damage to science and industry. For example, an incident at a research reactor could cause a political and public backlash that would do irreparable harm to national nuclear programs. Following the accidents at Three Mile Island and Chernobyl, considerable efforts and resources were committed to improving the safety posture of the world's nuclear power plants. Unsafe operation of research reactors will have an amplifying effect throughout a country or region's entire nuclear programs due to political, economic and nuclear infrastructure consequences. (author)

  4. An optimization model for improving highway safety

    Directory of Open Access Journals (Sweden)

    Promothes Saha

    2016-12-01

    Full Text Available This paper developed a traffic safety management system (TSMS for improving safety on county paved roads in Wyoming. TSMS is a strategic and systematic process to improve safety of roadway network. When funding is limited, it is important to identify the best combination of safety improvement projects to provide the most benefits to society in terms of crash reduction. The factors included in the proposed optimization model are annual safety budget, roadway inventory, roadway functional classification, historical crashes, safety improvement countermeasures, cost and crash reduction factors (CRFs associated with safety improvement countermeasures, and average daily traffics (ADTs. This paper demonstrated how the proposed model can identify the best combination of safety improvement projects to maximize the safety benefits in terms of reducing overall crash frequency. Although the proposed methodology was implemented on the county paved road network of Wyoming, it could be easily modified for potential implementation on the Wyoming state highway system. Other states can also benefit by implementing a similar program within their jurisdictions.

  5. Steam Pressure-Reducing Station Safety and Energy Efficiency Improvement Project

    Energy Technology Data Exchange (ETDEWEB)

    Lower, Mark D [ORNL; Christopher, Timothy W [ORNL; Oland, C Barry [ORNL

    2011-06-01

    The Facilities and Operations (F&O) Directorate is sponsoring a continuous process improvement (CPI) program. Its purpose is to stimulate, promote, and sustain a culture of improvement throughout all levels of the organization. The CPI program ensures that a scientific and repeatable process exists for improving the delivery of F&O products and services in support of Oak Ridge National Laboratory (ORNL) Management Systems. Strategic objectives of the CPI program include achieving excellence in laboratory operations in the areas of safety, health, and the environment. Identifying and promoting opportunities for achieving the following critical outcomes are important business goals of the CPI program: improved safety performance; process focused on consumer needs; modern and secure campus; flexibility to respond to changing laboratory needs; bench strength for the future; and elimination of legacy issues. The Steam Pressure-Reducing Station (SPRS) Safety and Energy Efficiency Improvement Project, which is under the CPI program, focuses on maintaining and upgrading SPRSs that are part of the ORNL steam distribution network. This steam pipe network transports steam produced at the ORNL steam plant to many buildings in the main campus site. The SPRS Safety and Energy Efficiency Improvement Project promotes excellence in laboratory operations by (1) improving personnel safety, (2) decreasing fuel consumption through improved steam system energy efficiency, and (3) achieving compliance with applicable worker health and safety requirements. The SPRS Safety and Energy Efficiency Improvement Project being performed by F&O is helping ORNL improve both energy efficiency and worker safety by modifying, maintaining, and repairing SPRSs. Since work began in 2006, numerous energy-wasting steam leaks have been eliminated, heat losses from uninsulated steam pipe surfaces have been reduced, and deficient pressure retaining components have been replaced. These improvements helped ORNL

  6. 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.

  7. NPP Temelin. Status of safety improvements

    International Nuclear Information System (INIS)

    1999-01-01

    The WWER-1000 Temelin NPP under construction has been subjected as other NPPs of the same type to numerous project reviews resulting in quite a number of recommendations for design changes. Results of the IAEA mission to review the resolution of WWER-1000 safety issues at Temelin NPP are cited in this paper. The main conclusions emphasize that a combination of eastern and western technology and practices led to safety improvements in comparison with the international practices. Plant managers are clearly committed to implementation of operational programs which are consistent with effective western operational safety practices. Considerable effort remains to bring planned programs to successful implementation, in particular in meeting the need to foster strong safety culture among all personnel

  8. Program management plan for the conduct of a research, development, and demonstration program for improving the safety of nuclear powerplants

    International Nuclear Information System (INIS)

    1981-12-01

    Congress passed Public Law 96-567, Nuclear Safety Research, Development, and Demonstration Act of 1980, (hereafter referred to as the Act) to provide for an accelerated and coordinated program of light water reactor safety research, development, and demonstration to be carried out by the Department of Energy. In order to assure that this program would be compatible with the needs of Nuclear Regulatory Commission (NRC) and industry, the Department of Energy (DOE) initiated its response to Section 4 of the Act by conducting individual information gathering meetings with NRC and a wide cross section of the nuclear industry. The Department received recommendations on needs of what type of activities would and would not be appropriate for the Department to assist in satisfying these needs. Based on the evaluation of these inputs, it is concluded that the Department's ongoing Light Water Reactor (LWR) safety program is responsive to the Act. Specifically, the Department's ongoing program includes tasks in the areas of regulatory assessment, risk assessment, fission product source term, and emergency preparedness as well as providing technical assistance to the Institute of Nuclear Power Operations (INPO) to improve training of nuclear power personnel. These were among the very high priority efforts that were identified as necessary and appropriate for support by the Department

  9. Use of a Surgical Safety Checklist to Improve Team Communication.

    Science.gov (United States)

    Cabral, Richard A; Eggenberger, Terry; Keller, Kathryn; Gallison, Barry S; Newman, David

    2016-09-01

    To improve surgical team communication, a team at Broward Health Imperial Point Hospital, Ft Lauderdale, Florida, implemented a program for process improvement using a locally adapted World Health Organization Surgical Safety Checklist. This program included a standardized, comprehensive time out and a briefing/debriefing process. Postimplementation responses to the Safety Attitudes Questionnaire revealed a significant increase in the surgical team's perception of communication compared with that reported on the pretest (6% improvement resulting in t79 = -1.72, P improved surgical teamwork behaviors and an enhanced culture of safety in the OR. Copyright © 2016 AORN, Inc. Published by Elsevier Inc. All rights reserved.

  10. The effectiveness of a bicycle safety program for improving safety-related knowledge and behavior in young elementary students.

    Science.gov (United States)

    McLaughlin, Karen A; Glang, Ann

    2010-05-01

    The purpose of this study was to evaluate the "Bike Smart" program, an eHealth software program that teaches bicycle safety behaviors to young children. Participants were 206 elementary students in grades kindergarten to 3. A random control design was employed to evaluate the program, with students assigned to either the treatment condition (Bike Smart) or the control condition (a video on childhood safety). Outcome measures included computer-based knowledge items (safety rules, helmet placement, hazard discrimination) and a behavioral measure of helmet placement. Results demonstrated that regardless of gender, cohort, and grade the participants in the treatment group showed greater gains than control participants in both the computer-presented knowledge items (p > .01) and the observational helmet measure (p > .05). Findings suggest that the Bike Smart program can be a low cost, effective component of safety training packages that include both skills-based and experiential training.

  11. Medication safety programs in primary care: a scoping review.

    Science.gov (United States)

    Khalil, Hanan; Shahid, Monica; Roughead, Libby

    2017-10-01

    Medication safety plays an essential role in all healthcare organizations; improving this area is paramount to quality and safety of any wider healthcare program. While several medication safety programs in the hospital setting have been described and the associated impact on patient safety evaluated, no systematic reviews have described the impact of medication safety programs in the primary care setting. A preliminary search of the literature demonstrated that no systematic reviews, meta-analysis or scoping reviews have reported on medication safety programs in primary care; instead they have focused on specific interventions such as medication reconciliation or computerized physician order entry. This scoping review sought to map the current medication safety programs used in primary care. The current scoping review sought to examine the characteristics of medication safety programs in the primary care setting and to map evidence on the outcome measures used to assess the effectiveness of medication safety programs in improving patient safety. The current review considered participants of any age and any condition using care obtained from any primary care services. We considered studies that focussed on the characteristics of medication safety programs and the outcome measures used to measure the effectiveness of these programs on patient safety in the primary care setting. The context of this review was primary care settings, primary healthcare organizations, general practitioner clinics, outpatient clinics and any other clinics that do not classify patients as inpatients. We considered all quantitative studied published in English. A three-step search strategy was utilized in this review. Data were extracted from the included studies to address the review question. The data extracted included type of medication safety program, author, country of origin, aims and purpose of the study, study population, method, comparator, context, main findings and outcome

  12. Improving patient safety in radiology: a work in progress

    International Nuclear Information System (INIS)

    Sze, Raymond W.

    2008-01-01

    The purpose of this paper is to share the experiences, including successes and failures, as well as the ongoing process of developing and implementing a safety program in a large pediatric radiology department. Building a multidisciplinary pediatric radiology safety team requires successful recruitment of team members, selection of a team leader, and proper and ongoing training and tools, and protected time. Challenges, including thorough examples, are presented on improving pediatric radiology safety intradepartmentally, interdepartmentally, and institutionally. Finally, some major challenges to improving safety in pediatric radiology, and healthcare in general, are presented along with strategies to overcome these challenges. Our safety program is a work in progress; this article is a personal account and the reader is asked for tolerance of its occasional subjective tone and contents. (orig.)

  13. Using Contemporary Leadership Skills in Medication Safety Programs.

    Science.gov (United States)

    Hertig, John B; Hultgren, Kyle E; Weber, Robert J

    2016-04-01

    The discipline of studying medication errors and implementing medication safety programs in hospitals dates to the 1970s. These initial programs to prevent errors focused only on pharmacy operation changes - and not the broad medication use system. In the late 1990s, research showed that faulty systems, and not faulty people, are responsible for errors and require a multidisciplinary approach. The 2013 ASHP Statement on the Role of the Medication Safety Leader recommended that medication safety leaders be integrated team members rather than a single point of contact. Successful medication safety programs must employ a new approach - one that embraces the skills of all health care team members and positions many leaders to improve safety. This approach requires a new set of leadership skills based on contemporary management principles, including followership, team-building, tracking and assessing progress, storytelling and communication, and cultivating innovation, all of which promote transformational change. The application of these skills in developing or changing a medication safety program is reviewed in this article.

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

    International Nuclear Information System (INIS)

    Chung, Dae Wook

    2011-01-01

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

  15. Structural Aging Program approach to providing an improved basis for aging management of safety-related concrete structures

    International Nuclear Information System (INIS)

    Naus, D.J.; Oland, C.B.; Ellingwood, B.

    1993-01-01

    The Structural Aging (SAG) Program is being conducted at the Oak Ridge National Laboratory (ORNL) for the United States Nuclear Regulatory Commission (USNRC). The SAG Program is addressing the aging management of safety-related concrete structures in nuclear power plants for the purpose of providing improved technical bases for their continued service. The program is organized into four tasks: Program Management, Materials Property Data Base, Structural Component Assessment/Repair Technologies, and Quantitative Methodology for Continued Service Determinations. Objectives and a summary of recent accomplishments under each of these tasks are presented

  16. The International Atomic Energy Agency (IAEA) research program to improve safety assessment methodologies for near-surface radioactive waste disposal facilities (ISAM)

    International Nuclear Information System (INIS)

    Torres-Vidal, C.; Kozak, M.W.

    2000-01-01

    The International Atomic Energy Agency (IAEA) launched a Coordinated Research Program in November 1997 on Improvement of Safety Assessment Methodologies for Near Surface Radioactive Waste Disposal Facilities (ISAM). The purpose of this paper is to describe the program and its goals, and to describe achievements of the program to date. The main objectives of the ISAM program are outlined. The primary focus of ISAM is on the practical application of safety assessment methodologies. Three kinds of practical situations are being addressed in the program: safety assessments for large vaults typical of those in Western Europe and North America, smaller vaults for medium and industrial wastes typical in eastern Europe and the former Soviet Union, and a proposed borehole technology for disposal of spent sources in low-technology conditions. (author)

  17. Research on the improvement of nuclear safety

    International Nuclear Information System (INIS)

    Yoo, Keon Joong; Kim, Dong Soo; Kim, Hui Dong; Park, Chang Kyu

    1993-06-01

    To improve the nuclear safety, this project is divided into three areas which are the development of safety analysis technology, the development of severe accident analysis technology and the development of integrated safety assessment technology. 1. The development of safety analysis technology. The present research aims at the development of necessary technologies for nuclear safety analysis in Korea. Establishment of the safety analysis technologies enables to reduce the expenditure both by eliminating excessive conservatisms incorporated in nuclear reactor design and by increasing safety margins in operation. It also contributes to improving plant safety through realistic analyses of the Emergency Operating Procedures (EOP). 2. The development of severe accident analysis technology. By the computer codes (MELCOR and CONTAIN), the in-vessel and the ex-vessel severe accident phenomena are simulated. 3. The development of integrated safety assessment technology. In the development of integrated safety assessment techniques, the included research areas are the improvement of PSA computer codes, the basic study on the methodology for human reliability analysis (HRA) and common cause failure (CCF). For the development of the level 2 PSA computer code, the basic research for the interface between level 1 and 2 PSA, the methodology for the treatment of containment event tree are performed. Also the new technologies such as artificial intelligence, object-oriented programming techniques are used for the improvement of computer code and the assessment techniques

  18. Workplace safety and health programs, practices, and conditions in auto collision repair businesses.

    Science.gov (United States)

    Brosseau, L M; Bejan, A; Parker, D L; Skan, M; Xi, M

    2014-01-01

    This article describes the results of a pre-intervention safety assessment conducted in 49 auto collision repair businesses and owners' commitments to specific improvements. A 92-item standardized audit tool employed interviews, record reviews, and observations to assess safety and health programs, training, and workplace conditions. Owners were asked to improve at least one-third of incorrect, deficient, or missing (not in compliance with regulations or not meeting best practice) items, of which a majority were critical or highly important for ensuring workplace safety. Two-thirds of all items were present, with the highest fraction related to electrical safety, machine safety, and lockout/tagout. One-half of shops did not have written safety programs and had not conducted recent training. Many had deficiencies in respiratory protection programs and practices. Thirteen businesses with a current or past relationship with a safety consultant had a significantly higher fraction of correct items, in particular related to safety programs, up-to-date training, paint booth and mixing room conditions, electrical safety, and respiratory protection. Owners selected an average of 58% of recommended improvements; they were most likely to select items related to employee Right-to-Know training, emergency exits, fire extinguishers, and respiratory protection. They were least likely to say they would improve written safety programs, stop routine spraying outside the booth, or provide adequate fire protection for spray areas outside the booth. These baseline results suggest that it may be possible to bring about workplace improvements using targeted assistance from occupational health and safety professionals.

  19. End-Stage Renal Disease Outcomes among the Kaiser Permanente Southern California Creatinine Safety Program (Creatinine SureNet): Opportunities to Reflect and Improve.

    Science.gov (United States)

    Sim, John J; Batech, Michael; Danforth, Kim N; Rutkowski, Mark P; Jacobsen, Steven J; Kanter, Michael H

    2017-01-01

    The Kaiser Permanente Southern California (KPSC) creatinine safety program (Creatinine SureNet) identifies and outreaches to thousands of people annually who may have had a missed diagnosis for chronic kidney disease (CKD). We sought to determine the value of this outpatient program and evaluate opportunities for improvement. Longitudinal cohort study (February 2010 through December 2015) of KPSC members captured into the creatinine safety program who were characterized using demographics, laboratory results, and different estimations of glomerular filtration rate. Age- and sex-adjusted rates of end-stage renal disease (ESRD) were compared with those in the overall KPSC population. Among 12,394 individuals, 83 (0.7%) reached ESRD. The age- and sex-adjusted relative risk of ESRD was 2.7 times higher compared with the KPSC general population during the same period (94.7 vs 35.4 per 100,000 person-years; p creatinine measurements, only 13% had a urine study performed (32% among patients with confirmed CKD). Our study found a higher incidence of ESRD among individuals captured into the KPSC creatinine safety program. If the Chronic Kidney Disease Epidemiology Collaboration equation were used, fewer people would have been captured while improving the accuracy for diagnosing CKD. Urine testing was low even among patients with confirmed CKD. Our findings demonstrate the importance of a creatinine safety net program in an integrated health system but also suggest opportunities to improve CKD care and screening.

  20. Improvement of Safety Assessment Methodologies for Near Surface Disposal Facilities

    International Nuclear Information System (INIS)

    Batandjieva, B.; Torres-Vidal, C.

    2002-01-01

    The International Atomic Energy Agency (IAEA) Coordinated research program ''Improvement of Safety Assessment Methodologies for Near Surface Disposal Facilities'' (ISAM) has developed improved safety assessment methodology for near surface disposal facilities. The program has been underway for three years and has included around 75 active participants from 40 countries. It has also provided examples for application to three safety cases--vault, Radon type and borehole radioactive waste disposal facilities. The program has served as an excellent forum for exchange of information and good practices on safety assessment approaches and methodologies used worldwide. It also provided an opportunity for reaching broad consensus on the safety assessment methodologies to be applied to near surface low and intermediate level waste repositories. The methodology has found widespread acceptance and the need for its application on real waste disposal facilities has been clearly identified. The ISAM was finalized by the end of 2000, working material documents are available and an IAEA report will be published in 2002 summarizing the work performed during the three years of the program. The outcome of the ISAM program provides a sound basis for moving forward to a new IAEA program, which will focus on practical application of the safety assessment methodologies to different purposes, such as licensing radioactive waste repositories, development of design concepts, upgrading existing facilities, reassessment of operating repositories, etc. The new program will also provide an opportunity for development of guidance on application of the methodology that will be of assistance to both safety assessors and regulators

  1. Highway Safety Program Manual: Volume 3: Motorcycle Safety.

    Science.gov (United States)

    National Highway Traffic Safety Administration (DOT), Washington, DC.

    Volume 3 of the 19-volume Highway Safety Program Manual (which provides guidance to State and local governments on preferred highway safety practices) concentrates on aspects of motorcycle safety. The purpose and specific objectives of a State motorcycle safety program are outlined. Federal authority in the highway safety area and general policies…

  2. Improving the safety and reliability of Monju

    International Nuclear Information System (INIS)

    Itou, Kazumoto; Maeda, Hiroshi; Moriyama, Masatoshi

    1998-01-01

    Comprehensive safety review has been performed at Monju to determine why the Monju secondary sodium leakage accident occurred. We investigated how to improve the situation based on the results of the safety review. The safety review focused on five aspects of whether the facilities for dealing with the sodium leakage accident were adequate: the reliability of the detection method, the reliability of the method for preventing the spread of the sodium leakage accident, whether the documented operating procedures are adequate, whether the quality assurance system, program, and actions were properly performed and so on. As a result, we established for Monju a better method of dealing with sodium leakage accidents, rapid detection of sodium leakage, improvement of sodium drain facilities, and way to reduce damage to Monju systems after an accident. We also improve the operation procedures and quality assurance actions to increase the safety and reliability of Monju. (author)

  3. A Computer Program for Assessing Nuclear Safety Culture Impact

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-10-15

    Through several accidents of NPP including the Fukushima Daiichi in 2011 and Chernobyl accidents in 1986, a lack of safety culture was pointed out as one of the root cause of these accidents. Due to its latent influences on safety performance, safety culture has become an important issue in safety researches. Most of the researches describe how to evaluate the state of the safety culture of the organization. However, they did not include a possibility that the accident occurs due to the lack of safety culture. Because of that, a methodology for evaluating the impact of the safety culture on NPP's safety is required. In this study, the methodology for assessing safety culture impact is suggested and a computer program is developed for its application. SCII model which is the new methodology for assessing safety culture impact quantitatively by using PSA model. The computer program is developed for its application. This program visualizes the SCIs and the SCIIs. It might contribute to comparing the level of the safety culture among NPPs as well as improving the management safety of NPP.

  4. Status report of the US Department of Energy's International Nuclear Safety Program

    International Nuclear Information System (INIS)

    1994-12-01

    The US Department of Energy (DOE) implements the US Government's International Nuclear Safety Program to improve the level of safety at Soviet-designed nuclear power plants in Central and Eastern Europe, Russia, and Unkraine. The program is conducted consistent with guidance and policies established by the US Department of State (DOS) and the Agency for International Development and in close collaboration with the Nuclear Regulatory Commission. Some of the program elements were initiated in 1990 under a bilateral agreement with the former Soviet Union; however, most activities began after the Lisbon Nuclear Safety Initiative was announced by the DOS in 1992. Within DOE, the program is managed by the International Division of the Office of Nuclear Energy. The overall objective of the International Nuclear Safety Program is to make comprehensive improvements in the physical conditions of the power plants, plant operations, infrastructures, and safety cultures of countries operating Soviet-designed reactors. This status report summarizes the Internatioal Nuclear Safety Program's activities that have been completed as of September 1994 and discusses those activities currently in progress

  5. Operational safety improvement in OPR 1000

    International Nuclear Information System (INIS)

    Jung, Y.-E.

    2005-01-01

    Nuclear power operating experience management might be an important factor for the operational safety improvement. KHNP's nuclear information management system, called KONIS receives, distributes and manages all nuclear information from domestic and foreign, especially operating experience. Ulchin 3 and 4, the first units of OPR 1000 series operates several organizations regarding management of operating experience e.g. specialist group program, various task forces, equipment specialist system for operator, etc. Peer review is another contribution for nuclear safety. (author)

  6. EPRI program in water reactor safety

    International Nuclear Information System (INIS)

    Loewenstein, W.B.; Gelhaus, F.; Gopalakrishnan, A.

    1975-01-01

    The basis for EPRI's water reactor safety program is twofold. First is compilation and development of fundamental background data necessary for quantified light-water reactor (LWR) safety assurance appraisals. Second is development of realistic and experimentally bench-marked analytical procedures. The results are expected either to confirm the safety margins in current operating parameters, and to identify overly conservative controls, or, in some cases, to provide a basis for improvements to further minimize uncertainties in expected performance. Achievement of these objectives requires the synthesis of related current and projected experimental-analytical projects toward establishment of an experimentally-based analysis for the assurance of safety for LWRs

  7. Fundamentals of a patient safety program

    International Nuclear Information System (INIS)

    Frush, Karen S.

    2008-01-01

    Thousands of people are injured or die from medical errors and adverse events each year, despite being cared for by hard-working, intelligent and well-intended health care professionals, working in the highly complex and high-risk environment of the American health care system. Patient safety leaders have described a need for health care organizations to make error prevention a major strategic objective while at the same time recognizing the importance of transforming the traditional health care culture. In response, comprehensive patient safety programs have been developed with the aim of reducing medical errors and adverse events and acting as a catalyst in the development of a culture of safety. Components of these programs are described, with an emphasis on strategies to improve pediatric patient safety. Physicians, as leaders of the health care team, have a unique opportunity to foster the culture and commitment required to address the underlying systems causes of medical error and harm. (orig.)

  8. Nuclear safety training program (NSTP) for dismantling

    International Nuclear Information System (INIS)

    Cretskens, Pieter; Lenie, Koen; Mulier, Guido

    2014-01-01

    European Control Services (GDF Suez) has developed and is still developing specific training programs for the dismantling and decontamination of nuclear installations. The main topic in these programs is nuclear safety culture. We therefore do not focus on technical training but on developing the right human behavior to work in a 'safety culture' environment. The vision and techniques behind these programs have already been tested in different environments: for example the dismantling of the BN MOX Plant in Dessel (Belgium), Nuclear Safety Culture Training for Electrabel NPP Doel..., but also in the non-nuclear industry. The expertise to do so was found in combining the know-how of the Training and the Nuclear Department of ECS. In training, ECS is one of the main providers of education in risky tasks, like elevation and manipulation of charges, working in confined spaces... but it does also develop training on demand to improve safety in a certain topic. Radiation Protection is the core business in the Nuclear Department with a presence on most of the nuclear sites in Belgium. Combining these two domains in a nuclear safety training program, NSTP, is an important stage in a dismantling project due to specific contamination, technical and other risks. It increases the level of safety and leads to a harmonization of different working cultures. The modular training program makes it possible to evaluate constantly as well as in group or individually. (authors)

  9. 2011 Annual Criticality Safety Program Performance Summary

    Energy Technology Data Exchange (ETDEWEB)

    Andrea Hoffman

    2011-12-01

    specifically recognizes that the approval of SAR-400 approves the INL Criticality Safety Program. No new source requirements were released in 2011. A revision to LRD-18001 is planned for 2012 to clarify design requirements for criticality alarms. Training - Criticality Safety Engineering has developed training and provides training for many employee positions, including fissionable material handlers, facility managers, criticality safety officers, firefighters, and criticality safety engineers. Criticality safety training at the INL is a program strength. A revision to the training module developed in 2010 to supplement MFC certified fissionable material handlers (operators) training was prepared and presented in August of 2011. This training, 'Applied Science of Criticality Safety,' builds upon existing training and gives operators a better understanding of how their criticality controls are derived. Improvements to 00INL189, 'INL Criticality Safety Principles' are planned for 2012 to strengthen fissionable material handler training.

  10. 78 FR 66987 - Railroad Safety Technology Program Grant Program

    Science.gov (United States)

    2013-11-07

    ... carriers, railroad suppliers, and State and local governments for projects that have a public benefit of... projects . . . that have a public benefit of improved safety and network efficiency.'' To be eligible for... million. This grant program has a maximum 80-percent Federal and minimum 20-percent grantee cost share...

  11. Brunswick improvement program

    International Nuclear Information System (INIS)

    Howe, P.W.

    1985-01-01

    The performance of the twin 790-MW Mark-4 boiling water reactors located at the Brunswick steam electric plant has historically been well below average. The plant experienced low availability, low capacity factors, high US Nuclear Regulatory Commission (NRC) violations, excessive radioactive waste generation, excessive licensee event reports (LERs), an unacceptable industrial safety record, poor SALP ratings, and numerous other deficiencies leading to unacceptable performance. In June 1982 it was determined that certain periodic tests (PT) had never been performed. While one unit was down for a refueling/modification outage, Carolina Power and Light (CP and L) elected to bring the other unit off line and perform an extensive self-examination. As a result, a number of needed improvements covering a wide range of plant activities were identified. CP and L elected to consolidate all the elements of the improvement into a single, plant-wide program. The consolidated program, called the Brunswick Improvement Program (BIP), was established. Major objectives of the BIP and measurable results are presented

  12. Journey Toward High Reliability: A Comprehensive Safety Program to Improve Quality of Care and Safety Culture in a Large, Multisite Radiation Oncology Department.

    Science.gov (United States)

    Woodhouse, Kristina Demas; Volz, Edna; Maity, Amit; Gabriel, Peter E; Solberg, Timothy D; Bergendahl, Howard W; Hahn, Stephen M

    2016-05-01

    High-reliability organizations (HROs) focus on continuous identification and improvement of safety issues. We sought to advance a large, multisite radiation oncology department toward high reliability through the implementation of a comprehensive safety culture (SC) program at the University of Pennsylvania Department of Radiation Oncology. In 2011, with guidance from safety literature and experts in HROs, we designed an SC framework to reduce radiation errors. All state-reported medical events (SRMEs) from 2009 to 2016 were retrospectively reviewed and plotted on a control chart. Changes in SC grade were assessed using the Agency for Healthcare Research and Quality Hospital Survey. Outcomes measured included the number of radiation treatment fractions and days between SRMEs, as well as SC grade. Multifaceted safety initiatives were implemented at our main academic center and across all network sites. Postintervention results demonstrate increased staff fundamental safety knowledge, enhanced peer review with an electronic system, and special cause variation of SRMEs on control chart analysis. From 2009 to 2016, the number of days and fractions between SRMEs significantly increased, from a mean of 174 to 541 days (P safety framework. Our multifaceted initiatives, focusing on culture and system changes, can be successfully implemented in a large academic radiation oncology department to yield measurable improvements in SC and outcomes. Copyright © 2016 by American Society of Clinical Oncology.

  13. FLUOR HANFORD SAFETY MANAGEMENT PROGRAMS

    Energy Technology Data Exchange (ETDEWEB)

    GARVIN, L. J.; JENSEN, M. A.

    2004-04-13

    This document summarizes safety management programs used within the scope of the ''Project Hanford Management Contract''. The document has been developed to meet the format and content requirements of DOE-STD-3009-94, ''Preparation Guide for US. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses''. This document provides summary descriptions of Fluor Hanford safety management programs, which Fluor Hanford nuclear facilities may reference and incorporate into their safety basis when producing facility- or activity-specific documented safety analyses (DSA). Facility- or activity-specific DSAs will identify any variances to the safety management programs described in this document and any specific attributes of these safety management programs that are important for controlling potentially hazardous conditions. In addition, facility- or activity-specific DSAs may identify unique additions to the safety management programs that are needed to control potentially hazardous conditions.

  14. ELECTRICAL SAFETY IMPROVEMENT PROJECT A COMPLEX WIDE TEAMING INITIATIVE

    Energy Technology Data Exchange (ETDEWEB)

    GRAY BJ

    2007-11-26

    This paper describes the results of a year-long project, sponsored by the Energy Facility Contractors Group (EFCOG) and designed to improve overall electrical safety performance throughout Department of Energy (DOE)-owned sites and laboratories. As evidenced by focused metrics, the Project was successful primarily due to the joint commitment of contractor and DOE electrical safety experts, as well as significant support from DOE and contractor senior management. The effort was managed by an assigned project manager, using classical project-management principles that included execution of key deliverables and regular status reports to the Project sponsor. At the conclusion of the Project, the DOE not only realized measurable improvement in the safety of their workers, but also had access to valuable resources that will enable them to do the following: evaluate and improve electrical safety programs; analyze and trend electrical safety events; increase electrical safety awareness for both electrical and non-electrical workers; and participate in ongoing processes dedicated to continued improvement.

  15. Kozloduy nuclear power plant. Units 1-4. Status of safety improvements. Rev. 2

    International Nuclear Information System (INIS)

    1999-01-01

    This paper presents the results of the safety improvements activities carried out by the Kozloduy Nuclear Power Plant (KNPP) within the period 1990-1998. The steam supply system of this units is based of the reactor WWER-440/ B-230, which is a PWR of russian design developed according to the safety standards in force in USSR in late sixties. Up to now 10 reactor units of this type are in operation in four NPPs. Despite of efforts of the different plants to implement safety improvements measures during first 10-15 years of operation of this type of reactor its major safety problems were not eliminated and were a subject of international concern. The systematic evaluation of the deficiencies of the original design of this type of reactors have been initiated by IAEA in the beginning of 1990 and brought to developing a comprehensive list of safety problems which required urgent implementation of safety measures in all plants. To solve this problems in 1991 KNPP initiated implementation of so called 'short term' safety improvement program, developed with the help of WANO under agreement with Bulgarian Nuclear Safety Authority (BNSA) and consortium RISKAUDIT. The program was based on a stage approach and was foreseen to be implemented by tree stages in very tight time schedule in order to achieve significant and rapid improvements of the level of safety in operation of the units. The Short term program was implemented between from 1991 to 1997 owing to strong safety commitment of NEC and KNPP staff as well as broad international cooperation and financial support. Important part of resources were supplied under PHARE program of CEC, EBRD grant agreement and EDF support. In parallel a special assessment process started in 1995 in order to evaluate the level of safety, achieved by Short Term Program, according to current safety standards and to define the measures, which should be implemented by the Utility to complete the process of improving the safety in future

  16. German Light-Water-Reactor Safety-Research Program

    International Nuclear Information System (INIS)

    Seipel, H.G.; Lummerzheim, D.; Rittig, D.

    1977-01-01

    The Light-Water-Reactor Safety-Research Program, which is part of the energy program of the Federal Republic of Germany, is presented in this article. The program, for which the Federal Minister of Research and Technology of the Federal Republic of Germany is responsible, is subdivided into the following four main problem areas, which in turn are subdivided into projects: (1) improvement of the operational safety and reliability of systems and components (projects: quality assurance, component safety); (2) analysis of the consequences of accidents (projects: emergency core cooling, containment, external impacts, pressure-vessel failure, core meltdown); (3) analysis of radiation exposure during operation, accident, and decommissioning (project: fission-product transport and radiation exposure); and (4) analysis of the risk created by the operation of nuclear power plants (project: risk and reliability). Various problems, which are included in the above-mentioned projects, are concurrently studied within the Heiss-Dampf Reaktor experiments

  17. 75 FR 44051 - Resolicitation of Applications for the Railroad Safety Technology Program Grant Program (RS-TEC...

    Science.gov (United States)

    2010-07-27

    ... have a public benefit of improved railroad safety and efficiency. The program makes available $50... projects * * * that have a public benefit of improved safety and network efficiency.'' To be eligible for... percent grantee, cost share (cash or in-kind) requirement. Applications that do not clearly indicate at...

  18. Improvement critical care patient safety: using nursing staff development strategies, at Saudi Arabia.

    Science.gov (United States)

    Basuni, Enas M; Bayoumi, Magda M

    2015-01-13

    Intensive care units (ICUs) provide lifesaving care for the critically ill patients and are associated with significant risks. Moreover complexity of care within ICUs requires that the health care professionals exhibit a trans-disciplinary level of competency to improve patient safety. This study aimed at using staff development strategies through implementing patient safety educational program that may minimize the medical errors and improve patient outcome in hospital. The study was carried out using a quasi experimental design. The settings included the intensive care units at General Mohail Hospital and National Mohail Hospital, King Khalid University, Saudi Arabia. The study was conducted from March to June 2012. A convenience sample of all prevalent nurses at three shifts in the aforementioned settings during the study period was recruited. The program was implemented on 50 staff nurses in different ICUs. Their age ranged between 25-40 years. Statistically significant relation was revealed between safety climate and job satisfaction among nurses in the study sample (p=0.001). The years of experiences in ICU ranged between one year 11 (16.4) to 10 years 20 (29.8), most of them (68%) were working in variable shift, while 32% were day shift only. Improvements were observed in safety climate, teamwork climate, and nurse turnover rates on ICUs after implementing a safety program. On the heels of this improvement; nurses' total knowledge, skills and attitude were enhanced regarding patient safety dimensions. Continuous educational program for ICUs nursing staff through organized in-service training is needed to increase their knowledge and skills about the importance of improving patient safety measure. Emphasizing on effective collaborative system also will improve patient safety measures in ICUS.

  19. MORT: a safety management program developed for ERDA

    International Nuclear Information System (INIS)

    1977-03-01

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

  20. A performance improvement plan to increase nurse adherence to use of medication safety software.

    Science.gov (United States)

    Gavriloff, Carrie

    2012-08-01

    Nurses can protect patients receiving intravenous (IV) medication by using medication safety software to program "smart" pumps to administer IV medications. After a patient safety event identified inconsistent use of medication safety software by nurses, a performance improvement team implemented the Deming Cycle performance improvement methodology. The combined use of improved direct care nurse communication, programming strategies, staff education, medication safety champions, adherence monitoring, and technology acquisition resulted in a statistically significant (p < .001) increase in nurse adherence to using medication safety software from 28% to above 85%, exceeding national benchmark adherence rates (Cohen, Cooke, Husch & Woodley, 2007; Carefusion, 2011). Copyright © 2012 Elsevier Inc. All rights reserved.

  1. Development and implementation of a hospital-based patient safety program

    International Nuclear Information System (INIS)

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

    2006-01-01

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

  2. Radiation safety program in a high dose rate brachytherapy facility

    International Nuclear Information System (INIS)

    Rodriguez, L.V.; Hermoso, T.M.; Solis, R.C.

    2001-01-01

    The use of remote afterloading equipment has been developed to improve radiation safety in the delivery of treatment in brachytherapy. Several accidents, however, have been reported involving high dose-rate brachytherapy system. These events, together with the desire to address the concerns of radiation workers, and the anticipated adoption of the International Basic Safety Standards for Protection Against Ionizing Radiation (IAEA, 1996), led to the development of the radiation safety program at the Department of Radiotherapy, Jose R. Reyes Memorial Medical Center and at the Division of Radiation Oncology, St. Luke's Medical Center. The radiation safety program covers five major aspects: quality control/quality assurance, radiation monitoring, preventive maintenance, administrative measures and quality audit. Measures for evaluation of effectiveness of the program include decreased unnecessary exposures of patients and staff, improved accuracy in treatment delivery and increased department efficiency due to the development of staff vigilance and decreased anxiety. The success in the implementation required the participation and cooperation of all the personnel involved in the procedures and strong management support. This paper will discuss the radiation safety program for a high dose rate brachytherapy facility developed at these two institutes which may serve as a guideline for other hospitals intending to install a similar facility. (author)

  3. The Effectiveness of Aquatic Group Therapy for Improving Water Safety and Social Interactions in Children with Autism Spectrum Disorder: A Pilot Program

    Science.gov (United States)

    Alaniz, Michele L.; Rosenberg, Sheila S.; Beard, Nicole R.; Rosario, Emily R.

    2017-01-01

    Drowning is the number one cause of accidental death in children with Autism Spectrum Disorder (ASD). Few studies have examined the effectiveness of swim instruction for improving water safety skills in children with moderate to severe ASD. This study examines the feasibility and effectiveness of an aquatic therapy program on water safety and…

  4. THE FLUORBOARD A STATISTICALLY BASED DASHBOARD METHOD FOR IMPROVING SAFETY

    International Nuclear Information System (INIS)

    PREVETTE, S.S.

    2005-01-01

    The FluorBoard is a statistically based dashboard method for improving safety. Fluor Hanford has achieved significant safety improvements--including more than a 80% reduction in OSHA cases per 200,000 hours, during its work at the US Department of Energy's Hanford Site in Washington state. The massive project on the former nuclear materials production site is considered one of the largest environmental cleanup projects in the world. Fluor Hanford's safety improvements were achieved by a committed partnering of workers, managers, and statistical methodology. Safety achievements at the site have been due to a systematic approach to safety. This includes excellent cooperation between the field workers, the safety professionals, and management through OSHA Voluntary Protection Program principles. Fluor corporate values are centered around safety, and safety excellence is important for every manager in every project. In addition, Fluor Hanford has utilized a rigorous approach to using its safety statistics, based upon Dr. Shewhart's control charts, and Dr. Deming's management and quality methods

  5. Safety guidance and inspection program for particle accelerator

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Do Whey [Korea Institute of Nuclear Safety, Taejon (Korea, Republic of); Lee, Hee Seock; Yeo, In Whan [Pohang Accelerator Laboratory, Pohang (Korea, Republic of)] (and others)

    2001-03-15

    The inspection program and the safety guidance were developed to enhance the radiation protection for the use of particle accelerators. First the classification of particle accelerators was conducted to develop the safety inspection protocol efficiently. The status of particle accelerators which were operated at the inside and outside of the country, and their safety programs were surveyed. The characteristics of radiation production was researched for each type of particle accelerators. Two research teams were launched for industrial and research accelerators and for medical accelerators, respectively. In each stages of a design, a fabrication, an installation, a commissioning, and normal operation of accelerators, those safety inspection protocols were developed. Because all protocols resulted from employing safety experts, doing the questionnaire, and direct facility surveys, it can be applicable to present safety problem directly. The detail improvement concepts were proposed to revise the domestic safety rule. This results might also be useful as a practical guidance for the radiation safety officer of an accelerator facility, and as the detail standard for the governmental inspection authorities.

  6. Prioritization of tasks in the draft LWR safety technology program plan. Final report

    International Nuclear Information System (INIS)

    Lim, E.Y.; Miller, W.J.; Parkinson, W.J.; Ritzman, R.L.; vonHerrmann, J.L.; Wood, P.J.

    1980-05-01

    The purpose of this report is to describe both the approach taken and the results produced in the SAI effort to prioritize the tasks in the Sandia draft LWR Safety Technology Program Plan. This work used the description of important safety issues developed in the Reactor Safety Study (2) to quantify the effect of safety improvements resulting from a research and development program on the risk from nuclear power plants. Costs of implementation of these safety improvements were also estimated to allow a presentation of the final results in a value (i.e., risk reduction) vs. impact (i.e., implementation costs) matrix

  7. Confidence improvement of disosal safety bydevelopement of a safety case for high-level radioactive waste disposal

    Energy Technology Data Exchange (ETDEWEB)

    Baik, Min Hoon; Ko, Nak Youl; Jeong, Jong Tae; Kim, Kyung Su [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-12-15

    Many countries have developed a safety case suitable to their own countries in order to improve the confidence of disposal safety in deep geological disposal of high-level radioactive waste as well as to develop a disposal program and obtain its license. This study introduces and summarizes the meaning, necessity, and development process of the safety case for radioactive waste disposal. The disposal safety is also discussed in various aspects of the safety case. In addition, the status of safety case development in the foreign countries is briefly introduced for Switzerland, Japan, the United States of America, Sweden, and Finland. The strategy for the safety case development that is being developed by KAERI is also briefly introduced. Based on the safety case, we analyze the efforts necessary to improve confidence in disposal safety for high-level radioactive waste. Considering domestic situations, we propose and discuss some implementing methods for the improvement of disposal safety, such as construction of a reliable information database, understanding of processes related to safety, reduction of uncertainties in safety assessment, communication with stakeholders, and ensuring justice and transparency. This study will contribute to the understanding of the safety case for deep geological disposal and to improving confidence in disposal safety through the development of the safety case in Korea for the disposal of high-level radioactive waste.

  8. SAFETY IMPROVES DRAMATICALLY IN FLUOR HANFORD SOIL AND GROUNDWATER REMEDIATION PROJECT

    International Nuclear Information System (INIS)

    GERBER MS

    2007-01-01

    This paper describes dramatic improvements in the safety record of the Soil and Groundwater Remediation Project (SGRP) at the Hanford Site in southeast Washington state over the past four years. During a period of enormous growth in project work and scope, contractor Fluor Hanford reduced injuries, accidents, and other safety-related incidents and enhanced a safety culture that earned the SGRP Star Status in the Department of Energy's (DOE's) Voluntary Protection Program (VPP) in 2007. This paper outlines the complex and multi-faceted work of Fluor Hanford's SGRP and details the steps taken by the project's Field Operations and Safety organizations to improve safety. Holding field safety meetings and walkdowns, broadening safety inspections, organizing employee safety councils, intensively flowing down safety requirements to subcontractors, and adopting other methods to achieve remarkable improvement in safety are discussed. The roles of management, labor and subcontractors are detailed. Finally, SGRP's safety improvements are discussed within the context of overall safety enhancements made by Fluor Hanford in the company's 11 years of managing nuclear waste cleanup at the Hanford Site

  9. General aviation crash safety program at Langley Research Center

    Science.gov (United States)

    Thomson, R. G.

    1976-01-01

    The purpose of the crash safety program is to support development of the technology to define and demonstrate new structural concepts for improved crash safety and occupant survivability in general aviation aircraft. The program involves three basic areas of research: full-scale crash simulation testing, nonlinear structural analyses necessary to predict failure modes and collapse mechanisms of the vehicle, and evaluation of energy absorption concepts for specific component design. Both analytical and experimental methods are being used to develop expertise in these areas. Analyses include both simplified procedures for estimating energy absorption capabilities and more complex computer programs for analysis of general airframe response. Full-scale tests of typical structures as well as tests on structural components are being used to verify the analyses and to demonstrate improved design concepts.

  10. Improving Employees' Safety Awareness in Healthcare Organizations Using the DMAIC Quality Improvement Approach.

    Science.gov (United States)

    Momani, Amer; Hirzallah, Muʼath; Mumani, Ahmad

    Occupational injuries and illnesses in healthcare can cause great human suffering, incur high cost, and have an adverse impact on the quality of patient care. One of the most effective solutions for addressing health and safety issues and improving decisions at the point of care rests in raising employees' safety awareness to recognize, avoid, or respond to potential problems before they arise. In this article, the DMAIC Six Sigma model (Define, Measure, Analyze, Improve, Control) is used as a systematic program to measure, improve, and sustain employees' safety awareness in healthcare organizations. We report on a case study using the model, which was implemented and validated at a local hospital. First, the occupational health and safety knowledge that each job requires was identified. Next, the degree of competence of jobholders to meet these requirements was assessed. Based on the assessment, different awareness-raising efforts were proposed and implemented. The results showed significant improvement in the overall safety awareness compliance assessed: from 74.2% to 84.4% (p < .001) after the intervention. The proposed model ensures that the organization's awareness-raising efforts serve its actual needs and produce optimized and sustained results that eventually lead to safer healthcare service.

  11. Critical roles of orthopaedic surgeon leadership in healthcare systems to improve orthopaedic surgical patient safety.

    Science.gov (United States)

    Kuo, Calvin C; Robb, William J

    2013-06-01

    The prevention of medical and surgical harm remains an important public health problem despite increased awareness and implementation of safety programs. Successful introduction and maintenance of surgical safety programs require both surgeon leadership and collaborative surgeon-hospital alignment. Documentation of success of such surgical safety programs in orthopaedic practice is limited. We describe the scope of orthopaedic surgical patient safety issues, define critical elements of orthopaedic surgical safety, and outline leadership roles for orthopaedic surgeons needed to establish and sustain a culture of safety in contemporary healthcare systems. We identified the most common causes of preventable surgical harm based on adverse and sentinel surgical events reported to The Joint Commission. A comprehensive literature review through a MEDLINE(®) database search (January 1982 through April 2012) to identify pertinent orthopaedic surgical safety articles found 14 articles. Where gaps in orthopaedic literature were identified, the review was supplemented by 22 nonorthopaedic surgical references. Our final review included 36 articles. Six important surgical safety program elements needed to eliminate preventable surgical harm were identified: (1) effective surgical team communication, (2) proper informed consent, (3) implementation and regular use of surgical checklists, (4) proper surgical site/procedure identification, (5) reduction of surgical team distractions, and (6) routine surgical data collection and analysis to improve the safety and quality of surgical patient care. Successful surgical safety programs require a culture of safety supported by all six key surgical safety program elements, active surgeon champions, and collaborative hospital and/or administrative support designed to enhance surgical safety and improve surgical patient outcomes. Further research measuring improvements from such surgical safety systems in orthopaedic care is needed.

  12. The NASA Aviation Safety Program: Overview

    Science.gov (United States)

    Shin, Jaiwon

    2000-01-01

    In 1997, the United States set a national goal to reduce the fatal accident rate for aviation by 80% within ten years based on the recommendations by the Presidential Commission on Aviation Safety and Security. Achieving this goal will require the combined efforts of government, industry, and academia in the areas of technology research and development, implementation, and operations. To respond to the national goal, the National Aeronautics and Space Administration (NASA) has developed a program that will focus resources over a five year period on performing research and developing technologies that will enable improvements in many areas of aviation safety. The NASA Aviation Safety Program (AvSP) is organized into six research areas: Aviation System Modeling and Monitoring, System Wide Accident Prevention, Single Aircraft Accident Prevention, Weather Accident Prevention, Accident Mitigation, and Synthetic Vision. Specific project areas include Turbulence Detection and Mitigation, Aviation Weather Information, Weather Information Communications, Propulsion Systems Health Management, Control Upset Management, Human Error Modeling, Maintenance Human Factors, Fire Prevention, and Synthetic Vision Systems for Commercial, Business, and General Aviation aircraft. Research will be performed at all four NASA aeronautics centers and will be closely coordinated with Federal Aviation Administration (FAA) and other government agencies, industry, academia, as well as the aviation user community. This paper provides an overview of the NASA Aviation Safety Program goals, structure, and integration with the rest of the aviation community.

  13. Safety culture improvements in a nuclear laboratory setting

    International Nuclear Information System (INIS)

    Smith, K.L.; McKenna, J.

    2014-01-01

    In 2008, AECL performed a comprehensive safety culture assessment using recognized, industry-proven methodologies. Main observations were grouped into several key areas including standards, procedures, error-free work, and leadership fundamentals. Shortly thereafter, in 2009 May, the National Research Universal (NRU) reactor was shut down following discovery of a small leak of heavy water. Extensive repairs were required to return the reactor to service and a root cause investigation was conducted to determine the organizational and programmatic causes that led to the event. Taken together, these presented management with insights into common areas of weaknesses in performance and behaviours. A Corrective Action Plan (CAP) to address both the findings of the root cause analysis and safety culture assessment was captured in a comprehensive improvement plan issued in 2010 March, entitled the Voyageur Program Phase II (Voyageur II). The CAP addresses six key areas: Improve equipment reliability; Drive desired behaviours; Improve problem identification and resolution; Improve use of industry Operating Experience (OPEX) and reduce isolationism; Improve standards of operation; and, Improve management oversight. AECL's safety culture has been monitored regularly using quarterly surveys. A detailed safety culture assessment was executed in 2012 September. Compared with previous results, improvements for AECL were noted in the following areas: Use of Operating Experience, specifically in work planning, pre job briefs and training; Procedure quality; Availability of safety equipment; Control of temporary changes; and, Improved operational standards. (author)

  14. Safety culture improvements in a nuclear laboratory setting

    Energy Technology Data Exchange (ETDEWEB)

    Smith, K.L.; McKenna, J. [Atomic Energy of Canada Limited, Chalk River, ON (Canada)

    2014-07-01

    In 2008, AECL performed a comprehensive safety culture assessment using recognized, industry-proven methodologies. Main observations were grouped into several key areas including standards, procedures, error-free work, and leadership fundamentals. Shortly thereafter, in 2009 May, the National Research Universal (NRU) reactor was shut down following discovery of a small leak of heavy water. Extensive repairs were required to return the reactor to service and a root cause investigation was conducted to determine the organizational and programmatic causes that led to the event. Taken together, these presented management with insights into common areas of weaknesses in performance and behaviours. A Corrective Action Plan (CAP) to address both the findings of the root cause analysis and safety culture assessment was captured in a comprehensive improvement plan issued in 2010 March, entitled the Voyageur Program Phase II (Voyageur II). The CAP addresses six key areas: Improve equipment reliability; Drive desired behaviours; Improve problem identification and resolution; Improve use of industry Operating Experience (OPEX) and reduce isolationism; Improve standards of operation; and, Improve management oversight. AECL's safety culture has been monitored regularly using quarterly surveys. A detailed safety culture assessment was executed in 2012 September. Compared with previous results, improvements for AECL were noted in the following areas: Use of Operating Experience, specifically in work planning, pre job briefs and training; Procedure quality; Availability of safety equipment; Control of temporary changes; and, Improved operational standards. (author)

  15. THE SCHOOL HEALTH AND SAFETY PROGRAM.

    Science.gov (United States)

    1963

    INVOLVING INDIVIDUALS AS WELL AS ORGANIZATIONS, THE PROGRAM AIMED AT THE OPTIMUM HEALTH OF ALL CHILDREN, AND IMPROVEMENT OF HEALTH AND SAFETY STANDARDS WITHIN THE COMMUNITY. EACH OF THE CHILDREN WAS URGED TO HAVE A SUCCESSFUL VACCINATION FOR SMALL POX, THE DPT SERIES AND BOOSTER, THE POLIO SERIES, AND CORRECTIONS OF ALL DENTAL DEFECTS AND…

  16. Electronuclear's safety culture assessment and enhancement program

    International Nuclear Information System (INIS)

    Selvatici, E.; Diaz-Francisco, J.M.; Diniz de Souza, V.

    2002-01-01

    The present paper describes the Eletronuclear's safety culture assessment and enhancement program. The program was launched by the company's top management one year after the creation of Eletronuclear in 1997, from the merging of two companies with different organizational cultures, the design and engineering company Nuclen and the nuclear directorate of the Utility Furnas, Operator of the Angra1 NPP. The program consisted of an assessment performed internally in 1999 with the support and advice of the IAEA. This assessment, performed with the help of a survey, pooled about 80% of the company's employees. The overall result of the assessment was that a satisfactory level of safety culture existed; however, a number of points with a considerable margin for improvement were also identified. These points were mostly related with behavioural matters such as motivation, stress in the workplace, view of mistakes, handling of conflicts, and last but not least a view by a considerable number of employees that a conflict between safety and production might exist. An Action Plan was established by the company managers to tackle these weak points. This Plan was issued as company guideline by the company's Directorate. The subsequent step was to detail and implement the different actions of the Plan, which is the phase that we are at present. In the detailing of the Action Plan, special care was taken to sum up efforts, avoiding duplication of work or competition with already existing programs. In this process it was identified that the company had a considerable number of initiatives directly related to organizational and safety culture improvement, already operational. These initiatives have been integrated in the detailed Action Plan. A new assessment, for checking the effectiveness of the undertaken actions, is planned for 2003. (author)

  17. Fusion Safety Program annual report, fiscal year 1985

    International Nuclear Information System (INIS)

    Holland, D.F.; Merrill, B.J.; Herring, J.S.; Piet, S.J.; Longhurst, G.R.

    1987-02-01

    The Fusion Safety Program (FSP) has supported magnetic fusion technology for seven years, and this is the seventh annual report issued by the FSP. Program focus is identification of the magnitude and distribution of radioactive inventories in fusion reactors, and research and analysis of postulated accident scenarios that could cause the release of a portion of these inventories. Research results are used to develop improved designs that can reduce the probability and magnitude of such releases and thus improve the overall safety of fusion reactors. During FY-1985, research activities continued and participation continued on the Ignition Systems Project (ISP). This report presents the significant results of EGandG Idaho, Inc., activities and those from outside contracts, and includes a list of publications produced during the year, and activities planned for FY-1986

  18. Nuclear safety. Improvement programme

    International Nuclear Information System (INIS)

    2000-01-01

    In this brochure the improvement programme of nuclear safety of the Mochovce NPP is presented in detail. In 1996, a 'Mochovce NPP Nuclear Safety Improvement Programme' was developed in the frame of unit 1 and 2 completion project. The programme has been compiled as a continuous one, with the aim to reach the highest possible safety level at the time of commissioning and to establish good preconditions for permanent safety improvement in future. Such an approach is in compliance with the world's trends of safety improvement, life-time extension, modernisation and nuclear station power increase. The basic document for development of the 'Programme' is the one titled 'Safety Issues and their Ranking for WWER 440/213 NPP' developed by a group of IAEA experts. The following organisations were selected for solution of the safety measures: EUCOM (Consortium of FRAMATOME, France, and SIEMENS, Germany); SKODA Prague, a.s.; ENERGOPROJEKT Prague, a.s. (EGP); Russian organisations associated in ATOMENERGOEXPORT; VUJE Trnava, a.s

  19. Improving regulatory oversight of maintenance programs

    International Nuclear Information System (INIS)

    Cook, S.

    2008-01-01

    Safe nuclear power plant operation requires that risks due to failure or unavailability of Structures, Systems and Components (SSCs) be minimized. Implementation of an effective maintenance program is a key means for achieving this goal. In its regulatory framework, the important relationship between maintenance and safety is acknowledged by the CNSC. A high level maintenance program requirement is included in the Class I Facilities Regulations. In addition, the operating licence contains a condition based on the principle that the design function and performance of SSCs needs to remain consistent with the plant's design and analysis documents. Nuclear power plant licensees have the primary responsibility for safe operation of their facilities and consequently for implementation of a successful maintenance program. The oversight role of the Canadian Nuclear Safety Commission (CNSC) is to ensure that the licensee carries out that responsibility. The challenge for the CNSC is how to do this consistently and efficiently. Three opportunities for improvement to regulatory maintenance oversight are being pursued. These are related to the regulatory framework, compliance verification inspection activities and monitoring of self-reporting. The regulatory framework has been improved by clarifying expectations through the issuance of S-210 'Maintenance Programs for Nuclear Power Plants'. Inspection activities have been improved by introducing new maintenance inspections into the baseline program. Monitoring is being improved by making better use of self-reported and industry produced maintenance related performance indicators. As with any type of program change, the challenge is to ensure the consistent and optimal application of regulatory activities and resources. This paper is a summary of the CNSC's approach to improving its maintenance oversight strategy. (author)

  20. Best practices: an electronic drug alert program to improve safety in an accountable care environment.

    Science.gov (United States)

    Griesbach, Sara; Lustig, Adam; Malsin, Luanne; Carley, Blake; Westrich, Kimberly D; Dubois, Robert W

    2015-04-01

    The accountable care organization (ACO), one of the most promising and talked about new models of care, focuses on improving communication and care transitions by tying potential shared savings to specific clinical and financial benchmarks. An important factor in meeting these benchmarks is an ACO's ability to manage medications in an environment where medical and pharmacy care has been integrated. The program described in this article highlights the critical components of Marshfield Clinic's Drug Safety Alert Program (DSAP), which focuses on prioritizing and communicating safety issues related to medications with the goal of reducing potential adverse drug events. Once the medication safety concern is identified, it is reviewed to evaluate whether an alert warrants sending prescribers a communication that identifies individual patients or a general communication to all physicians describing the safety concern. Instead of basing its decisions regarding clinician notification about drug alerts on subjective criteria, the Marshfield Clinic's DSAP uses an internally developed scoring system. The scoring system includes criteria developed from previous drug alerts, such as level of evidence, size of population affected, severity of adverse event identified or targeted, litigation risk, available alternatives, and potential for duration of medication use. Each of the 6 criteria is assigned a weight and is scored based upon the content and severity of the alert received.  In its first 12 months, the program targeted 6 medication safety concerns involving the following medications: topiramate, glyburide, simvastatin, citalopram, pioglitazone, and lovastatin. Baseline and follow-up prescribing data were gathered on the targeted medications. Follow-up review of prescribing data demonstrated that the DSAP provided quality up-to-date safety information that led to changes in drug therapy and to decreases in potential adverse drug events. In aggregate, nearly 10,000 total

  1. SAFETY IMPROVES DRAMATICALLY IN FLUOR HANFORD SOIL AND GROUNDWATER REMEDIATION PROJECT

    Energy Technology Data Exchange (ETDEWEB)

    GERBER MS

    2007-12-05

    This paper describes dramatic improvements in the safety record of the Soil and Groundwater Remediation Project (SGRP) at the Hanford Site in southeast Washington state over the past four years. During a period of enormous growth in project work and scope, contractor Fluor Hanford reduced injuries, accidents, and other safety-related incidents and enhanced a safety culture that earned the SGRP Star Status in the Department of Energy's (DOE's) Voluntary Protection Program (VPP) in 2007. This paper outlines the complex and multi-faceted work of Fluor Hanford's SGRP and details the steps taken by the project's Field Operations and Safety organizations to improve safety. Holding field safety meetings and walkdowns, broadening safety inspections, organizing employee safety councils, intensively flowing down safety requirements to subcontractors, and adopting other methods to achieve remarkable improvement in safety are discussed. The roles of management, labor and subcontractors are detailed. Finally, SGRP's safety improvements are discussed within the context of overall safety enhancements made by Fluor Hanford in the company's 11 years of managing nuclear waste cleanup at the Hanford Site.

  2. Lesson learned from PSA in the design improvement program of KSNP+

    International Nuclear Information System (INIS)

    Kim, M.R.; Lim, H.K.; Kang, S.K.; Park, K.S.

    2001-01-01

    KOPEC (Korea Power Engineering Co.) in conjunction with the client KEPCO (Korea Electric Power Corp.) has been developing a highly competitive Improved Korean Standard Nuclear Power Plant named KSNP+. From the beginning of Design Improvement Program, PSA was carried out to assure that the safety level of KSNP+ is maintained or improved in comparison with that of KSNP, the Korean Standard NPP. To achieve the safety goal of KSNP+, PSA team reviewed all design changes that might affect the plant safety. Design vulnerabilities were identified from the PSA results and safety improvement items were recommended to the system designers. Through the Design Improvement Program, KSNP+ became more reliable, safer and economically competitive than KSNP. This was achieved by systematic approach for design optimization and effective use of PSA technology based on past experience and expertise of nuclear power plant. (author)

  3. Nature-based strategies for improving urban health and safety

    Science.gov (United States)

    Michelle C. Kondo; Eugenia C. South; Charles C. Branas

    2015-01-01

    Place-based programs are being noticed as key opportunities to prevent disease and promote public health and safety for populations at-large. As one key type of place-based intervention, nature-based and green space strategies can play an especially large role in improving health and safety for dwellers in urban environments such as US legacy cities that lack nature...

  4. Improving operating room safety

    Directory of Open Access Journals (Sweden)

    Garrett Jill

    2009-11-01

    Full Text Available Abstract Despite the introduction of the Universal Protocol, patient safety in surgery remains a daily challenge in the operating room. This present study describes one community health system's efforts to improve operating room safety through human factors training and ultimately the development of a surgical checklist. Using a combination of formal training, local studies documenting operating room safety issues and peer to peer mentoring we were able to substantially change the culture of our operating room. Our efforts have prepared us for successfully implementing a standardized checklist to improve operating room safety throughout our entire system. Based on these findings we recommend a multimodal approach to improving operating room safety.

  5. Area Safety Program for the tokamak fusion test reactor (TFTR)

    International Nuclear Information System (INIS)

    Rappe, G.M.

    1984-10-01

    Overall the Area Safety Program has proved to be a very successful operation. There is no doubt that a safety program organized through line management is the best way to involve all personnel. Naturally, when the program was first started, there was some criticism and a certain resistance on the part of a few individuals to fully participate. However, once the program was underway and it could be seen that it was working to everyone's advantage, this reluctance disappeared and a spirit of full cooperation is now enjoyed. It is very important that for this success to continue there must be a two way flow of information, both from the Area Safety Coordinators up through line management, and from senior management, with decisions and answers, back down through the management chain with the utmost dispatch. As with all programs, there is still room for improvement. This program has started a review cycle with a view to streamlining certain areas and possibly increasing its scope in others

  6. Findings From the National Machine Guarding Program-A Small Business Intervention: Machine Safety.

    Science.gov (United States)

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

    2016-09-01

    The purpose of this nationwide intervention was to improve machine safety in small metal fabrication businesses (3 to 150 employees). The failure to implement machine safety programs related to guarding and lockout/tagout (LOTO) are frequent causes of Occupational Safety and Health Administration (OSHA) citations and may result in serious traumatic injury. Insurance safety consultants conducted a standardized evaluation of machine guarding, safety programs, and LOTO. Businesses received a baseline evaluation, two intervention visits, and a 12-month follow-up evaluation. The intervention was completed by 160 businesses. Adding a safety committee was associated with a 10% point increase in business-level machine scores (P increase in LOTO program scores (P < 0.0001). Insurance safety consultants proved effective at disseminating a machine safety and LOTO intervention via management-employee safety committees.

  7. SHEAR Kit case study : ConocoPhillips Canada leverages technology for health, safety and environmental operations to improve program effectiveness

    Energy Technology Data Exchange (ETDEWEB)

    Hayter, J. [Pangaea Systems Inc., Calgary, AB (Canada)

    2003-07-01

    This PowerPoint presentation outlined the elements of an automated safety program that Pangaea Systems Inc. has provided to ConocoPhillips Canada Ltd. SHEAR is a web-based computer application that centralizes health, safety and environment documentation to enable better reporting and improved business analysis of management involvement; hazard identification and risk control; rules and work procedures; training; communication; and, incident and accident reporting and investigation. SHEAR collects findings from audits, site inspections, safety meetings, hazards and risks, and accidents. Its purpose is to identify, classify and better understand events and to develop a process for remedial action. This presentation described SHEAR's incident severity potential index, the incident reporting process, and the elements of the management system. 8 figs.

  8. Measuring and improving patient safety through health information technology: The Health IT Safety Framework.

    Science.gov (United States)

    Singh, Hardeep; Sittig, Dean F

    2016-04-01

    Health information technology (health IT) has potential to improve patient safety but its implementation and use has led to unintended consequences and new safety concerns. A key challenge to improving safety in health IT-enabled healthcare systems is to develop valid, feasible strategies to measure safety concerns at the intersection of health IT and patient safety. In response to the fundamental conceptual and methodological gaps related to both defining and measuring health IT-related patient safety, we propose a new framework, the Health IT Safety (HITS) measurement framework, to provide a conceptual foundation for health IT-related patient safety measurement, monitoring, and improvement. The HITS framework follows both Continuous Quality Improvement (CQI) and sociotechnical approaches and calls for new measures and measurement activities to address safety concerns in three related domains: 1) concerns that are unique and specific to technology (e.g., to address unsafe health IT related to unavailable or malfunctioning hardware or software); 2) concerns created by the failure to use health IT appropriately or by misuse of health IT (e.g. to reduce nuisance alerts in the electronic health record (EHR)), and 3) the use of health IT to monitor risks, health care processes and outcomes and identify potential safety concerns before they can harm patients (e.g. use EHR-based algorithms to identify patients at risk for medication errors or care delays). The framework proposes to integrate both retrospective and prospective measurement of HIT safety with an organization's existing clinical risk management and safety programs. It aims to facilitate organizational learning, comprehensive 360 degree assessment of HIT safety that includes vendor involvement, refinement of measurement tools and strategies, and shared responsibility to identify problems and implement solutions. A long term framework goal is to enable rigorous measurement that helps achieve the safety

  9. A randomized, controlled intervention of machine guarding and related safety programs in small metal-fabrication businesses.

    Science.gov (United States)

    Parker, David L; Brosseau, Lisa M; Samant, Yogindra; Xi, Min; Pan, Wei; Haugan, David

    2009-01-01

    Metal fabrication employs an estimated 3.1 million workers in the United States. The absence of machine guarding and related programs such as lockout/tagout may result in serious injury or death. The purpose of this study was to improve machine-related safety in small metal-fabrication businesses. We used a randomized trial with two groups: management only and management-employee. We evaluated businesses for the adequacy of machine guarding (machine scorecard) and related safety programs (safety audit). We provided all businesses with a report outlining deficiencies and prioritizing their remediation. In addition, the management-employee group received four one-hour interactive training sessions from a peer educator. We evaluated 40 metal-fabrication businesses at baseline and 37 (93%) one year later. Of the three nonparticipants, two had gone out of business. More than 40% of devices required for adequate guarding were missing or inadequate, and 35% of required safety programs and practices were absent at baseline. Both measures improved significantly during the course of the intervention. No significant differences in changes occurred between the two intervention groups. Machine-guarding practices and programs improved by up to 13% and safety audit scores by up to 23%. Businesses that added safety committees or those that started with the lowest baseline measures showed the greatest improvements. Simple and easy-to-use assessment tools allowed businesses to significantly improve their safety practices, and safety committees facilitated this process.

  10. Speech Recognition Interfaces Improve Flight Safety

    Science.gov (United States)

    2013-01-01

    "Alpha, Golf, November, Echo, Zulu." "Sierra, Alpha, Golf, Echo, Sierra." "Lima, Hotel, Yankee." It looks like some strange word game, but the combinations of words above actually communicate the first three points of a flight plan from Albany, New York to Florence, South Carolina. Spoken by air traffic controllers and pilots, the aviation industry s standard International Civil Aviation Organization phonetic alphabet uses words to represent letters. The first letter of each word in the series is combined to spell waypoints, or reference points, used in flight navigation. The first waypoint above is AGNEZ (alpha for A, golf for G, etc.). The second is SAGES, and the third is LHY. For pilots of general aviation aircraft, the traditional method of entering the letters of each waypoint into a GPS device is a time-consuming process. For each of the 16 waypoints required for the complete flight plan from Albany to Florence, the pilot uses a knob to scroll through each letter of the alphabet. It takes approximately 5 minutes of the pilot s focused attention to complete this particular plan. Entering such a long flight plan into a GPS can pose a safety hazard because it can take the pilot s attention from other critical tasks like scanning gauges or avoiding other aircraft. For more than five decades, NASA has supported research and development in aviation safety, including through its Vehicle Systems Safety Technology (VSST) program, which works to advance safer and more capable flight decks (cockpits) in aircraft. Randy Bailey, a lead aerospace engineer in the VSST program at Langley Research Center, says the technology in cockpits is directly related to flight safety. For example, "GPS navigation systems are wonderful as far as improving a pilot s ability to navigate, but if you can find ways to reduce the draw of the pilot s attention into the cockpit while using the GPS, it could potentially improve safety," he says.

  11. Elements of a nuclear criticality safety program

    International Nuclear Information System (INIS)

    Hopper, C.M.

    1995-01-01

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

  12. Improving the safety of Ukrainian NPP to reach an internationally accepted level

    International Nuclear Information System (INIS)

    Bozhko, S.; Helske, J.; Janke, R.; Mayoral, C.

    2013-01-01

    This paper summarizes the safety status and the modernization progress of Ukrainian NPPs towards an internationally accepted level of safety. After a brief discussion of the concept of what is called an 'international accepted level' for new and operating NPPs, the status of Russian type WWER and in particular the Ukrainian NPPs is presented. Then, the performed investigations of the gaps between international accepted level and the original status of Ukrainian NPPs are presented. The safety objectives of the modernization programs, some examples of defence in depth improvements, and an overall view of the modernization programs of Ukrainian NPPs are produced. Then, few important safety improvements implemented at the oldest Ukrainian WWER-1000 South Ukraine-1 are given in more detail. Finally, a conclusion presents the current status on the way to fulfill the national safety targets and to reach an internationally accepted level for all the Ukrainian NPPs. The paper is followed by the slides of the presentation. (authors)

  13. Researchers' Roles in Patient Safety Improvement.

    Science.gov (United States)

    Pietikäinen, Elina; Reiman, Teemu; Heikkilä, Jouko; Macchi, Luigi

    2016-03-01

    In this article, we explore how researchers can contribute to patient safety improvement. We aim to expand the instrumental role researchers have often occupied in relation to patient safety improvement. We reflect on our own improvement model and experiences as patient safety researchers in an ongoing Finnish multi-actor innovation project through self-reflective narration. Our own patient safety improvement model can be described as systemic. Based on the purpose of the innovation project, our improvement model, and the improvement models of the other actors in the project, we have carried out a wide range of activities. Our activities can be summarized in 8 overlapping patient safety improvement roles: modeler, influencer, supplier, producer, ideator, reflector, facilitator, and negotiator. When working side by side with "practice," researchers are offered and engage in several different activities. The way researchers contribute to patient safety improvement and balance between different roles depends on the purpose of the study, as well as on the underlying patient safety improvement models. Different patient safety research paradigms seem to emphasize different improvement roles, and thus, they also face different challenges. Open reflection on the underlying improvement models and roles can help researchers with different backgrounds-as well as other actors involved in patient safety improvement-in structuring their work and collaborating productively.

  14. Design safety improvements of Kozloduy NPP to meet the modern safety requirements towards the old generation PWR

    International Nuclear Information System (INIS)

    Hinovski, M.P.; Sabinov, S.

    2001-01-01

    Activities related to safety improvement of Kozloduy NPP units, started at the end of 1970s included seismic resistance upgrading, fire safety improvement, reliable heat final absorber etc. During the last 10 years the approach was systematized and improved. Units 1 to 4 are of great interest; therefore here we will discuss these units only. As a result of studies and analyses performed at the end of the 1980s and the beginning of the 1990s, problems related to the safety were identified and complex of technical measures was developed and planned. A considerable part of these measures has already been implemented, and the rest will be performed during the next years. Activities were performed by stages, and at the moment the last stage is under way. It shall be finished by the year 2003. The number of the measures is quite large to describe them here in full scope -- during the first stage of the safety program (1991-1993) were developed and analyzed more than 4200 documents and more than 160 measures were executed. During the second and third stages more than 300 important improvements were realized. In the frame of the program, financed by EBRD, 10 new systems with great importance were implemented and 8 systems were significantly modified. The main measures are described below. (author)

  15. 10 CFR 70.62 - Safety program and integrated safety analysis.

    Science.gov (United States)

    2010-01-01

    ...; (iv) Potential accident sequences caused by process deviations or other events internal to the... have experience in nuclear criticality safety, radiation safety, fire safety, and chemical process... this safety program; namely, process safety information, integrated safety analysis, and management...

  16. Obtaining Valid Safety Data for Software Safety Measurement and Process Improvement

    Science.gov (United States)

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

    2010-01-01

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

  17. A Laboratory Safety Program at Delaware.

    Science.gov (United States)

    Whitmyre, George; Sandler, Stanley I.

    1986-01-01

    Describes a laboratory safety program at the University of Delaware. Includes a history of the program's development, along with standard safety training and inspections now being implemented. Outlines a two-day laboratory safety course given to all graduate students and staff in chemical engineering. (TW)

  18. 78 FR 69433 - Executive Order 13650 Improving Chemical Facility Safety and Security Listening Sessions

    Science.gov (United States)

    2013-11-19

    ... Chemical Facility Safety and Security Listening Sessions AGENCY: National Protection and Programs... from stakeholders on issues pertaining to Improving Chemical Facility Safety and Security (Executive... regulations, guidance, and policies; and identifying best practices in chemical facility safety and security...

  19. Krsko NPP Periodic Safety Review program

    International Nuclear Information System (INIS)

    Basic, I.; Spiler, J.; Novsak, M.

    2001-01-01

    The need for conducting a Periodic Safety Review for the Krsko NPP has been clearly recognized both by the NEK and the regulator (SNSA). The PSR would be highly desirable both in the light of current trends in safety oversight practices and because of many benefits it is capable to provide. On January 11, 2001 the SNSA issued a decision requesting the Krsko NPP to prepare a program and determine a schedule for the implementation of the program for 'Periodic Safety Review of NPP Krsko'. The program, which is required to be in accordance with the IAEA safety philosophy and with the EU practice, was submitted for the approval to the SNSA by the end of March 2001. The paper summarizes Krsko NPP Periodic Safety Review Program [1] including implemented SNSA and IAEA Expert Mission comments.(author)

  20. Assistance of Foreign Countries and International Organizations to Support Safety Improvements at Ignalina NPP

    International Nuclear Information System (INIS)

    Shevaldin, V.

    1997-01-01

    International cooperation and assistance for the improving safety of Ignalina NPP is described. Sweden was among the first countries which supported safety improvements at Ignalina NPP. The first project in the cooperation was BARSELINA, Probabilistic Safety Analysis of Ignalina NPP. The cooperation is still bringing significant support to the plant, including improvements in the fire protection, communications system, physical protection, and many other areas. Another one very important source of assistance was Nuclear Safety Account, administered by the EBRD. In 1993 experts of the plant, together with representatives of VATESI and SKI (Sweden) have worked out a short-term safety improvement program SIP-1, which was financed by the EBRD . Eighteen safety related projects were selected, expensive and reliable equipment was procured and installed

  1. Recommended research program for improving seismic safety of light-water nuclear power plants

    International Nuclear Information System (INIS)

    1979-04-01

    Recommendations are presented for research areas concerned with seismic safety. These recommendations are based on an analysis of the answers to a questionnaire which was sent to over 80 persons working in the area of seismic safety of nuclear power plants. In addition to the answers of the 55 questionnaires which were received, the recommendations are based on ideas expressed at a meeting of an ad hoc group of professionals formed by Sandia, review of literature, current research programs, and engineering judgement

  2. AEC controlled area safety program

    Energy Technology Data Exchange (ETDEWEB)

    Hendricks, D W [Nevada Operations Office, Atomic Energy Commission, Las Vegas, NV (United States)

    1969-07-01

    The detonation of underground nuclear explosives and the subsequent data recovery efforts require a comprehensive pre- and post-detonation safety program for workers within the controlled area. The general personnel monitoring and environmental surveillance program at the Nevada Test Site are presented. Some of the more unusual health-physics aspects involved in the operation of this program are also discussed. The application of experience gained at the Nevada Test Site is illustrated by description of the on-site operational and safety programs established for Project Gasbuggy. (author)

  3. AEC controlled area safety program

    International Nuclear Information System (INIS)

    Hendricks, D.W.

    1969-01-01

    The detonation of underground nuclear explosives and the subsequent data recovery efforts require a comprehensive pre- and post-detonation safety program for workers within the controlled area. The general personnel monitoring and environmental surveillance program at the Nevada Test Site are presented. Some of the more unusual health-physics aspects involved in the operation of this program are also discussed. The application of experience gained at the Nevada Test Site is illustrated by description of the on-site operational and safety programs established for Project Gasbuggy. (author)

  4. 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.

  5. Fusion safety program plan

    International Nuclear Information System (INIS)

    Crocker, J.G.; Holland, D.F.; Herring, J.S.

    1980-09-01

    The program plan consists of research that has been divided into 13 different areas. These areas focus on the radioactive inventories that are expected in fusion reactors, the energy sources potentially available to release a portion of these inventories, and analysis and design techniques to assess and ensure that the safety risks associated with operation of magnetic fusion facilities are acceptably low. The document presents both long-term program requirements that must be fulfilled as part of the commercialization of fusion power and a five-year plan for each of the 13 different program areas. Also presented is a general discussion of magnetic fusion reactor safety, a method for establishing priorities in the program, and specific priority ratings for each task in the five-year plan

  6. Improving staff perception of a safety climate with crew resource management training.

    Science.gov (United States)

    Kuy, SreyRam; Romero, Ramon A L

    2017-06-01

    Communication failure is one of the top root causes in patient safety adverse events. Crew resource management (CRM) is a team building communication process intended to improve patient safety by improving team dynamics. First, to describe implementation of CRM in a Veterans Affair (VA) surgical service. Second, to assess whether staff CRM training is related to improvement in staff perception of a safety climate. Mandatory CRM training was implemented for all surgical service staff at a VA Hospital at 0 and 12 mo. Safety climate questionnaires were completed by operating room staff at a baseline, 6 and 12 mo after the initial CRM training. Participants reported improvement on all 27 points on the safety climate questionnaire at 6 mo compared with the baseline. At 12 mo, there was sustained improvement in 23 of the 27 areas. This is the first published report about the effect of CRM training on staff perception of a safety climate in a VA surgical service. We demonstrate that CRM training can be successfully implemented widespread in a surgical program. Overall, there was improvement in 100% of areas assessed on the safety climate questionnaire at 6 mo after CRM training. By 1 y, this improvement was sustained in 23 of 27 areas, with the areas of greatest improvement being the performance of briefings, collaboration between nurses and doctors, valuing nursing input, knowledge about patient safety, and institutional promotion of a patient safety climate. Published by Elsevier Inc.

  7. OPG - Waterways public safety program

    Energy Technology Data Exchange (ETDEWEB)

    Bennett, Tony [Ontario Power Generation (Canada)

    2011-07-01

    Ontario Power Generation (OPG) operates 65 hydroelectric generating stations in Ontario and has 241 dams. Security around dams is an important matter to minimize exposure of the public to hazards and to prevent an uncontrolled release of water and also to be prepared in case of failure. The purpose of this presentation is to describe the waterways public safety program developed by OPG in association with the Ontario Waterpower Associattion, the Canadian Dam Association and the Ontario Ministry of Natural Resoruces. This program takes a managed system approach with continuous review to address specific and changing conditions of sites. Policies, accountability mechanisms and assessments are first planned, and then implemented, every day functioning is monitored, corrective actions are developed on the basis of issues and reports are compiled for planning of new improvements. This research program provided OPG with new methods for preventing accidents more efficiently.

  8. National plan to enhance aviation safety through human factors improvements

    Science.gov (United States)

    Foushee, Clay

    1990-01-01

    The purpose of this section of the plan is to establish a development and implementation strategy plan for improving safety and efficiency in the Air Traffic Control (ATC) system. These improvements will be achieved through the proper applications of human factors considerations to the present and future systems. The program will have four basic goals: (1) prepare for the future system through proper hiring and training; (2) develop a controller work station team concept (managing human errors); (3) understand and address the human factors implications of negative system results; and (4) define the proper division of responsibilities and interactions between the human and the machine in ATC systems. This plan addresses six program elements which together address the overall purpose. The six program elements are: (1) determine principles of human-centered automation that will enhance aviation safety and the efficiency of the air traffic controller; (2) provide new and/or enhanced methods and techniques to measure, assess, and improve human performance in the ATC environment; (3) determine system needs and methods for information transfer between and within controller teams and between controller teams and the cockpit; (4) determine how new controller work station technology can optimally be applied and integrated to enhance safety and efficiency; (5) assess training needs and develop improved techniques and strategies for selection, training, and evaluation of controllers; and (6) develop standards, methods, and procedures for the certification and validation of human engineering in the design, testing, and implementation of any hardware or software system element which affects information flow to or from the human.

  9. Performance improvement of the Annular Core Pulse Reactor for reactor safety experiments

    International Nuclear Information System (INIS)

    Reuscher, J.A.; Pickard, P.S.

    1976-01-01

    The Annular Core Pulse Reactor (ACPR) is a TRIGA type reactor which has been in operation at Sandia Laboratories since 1967. The reactor is utilized in a wide variety of experimental programs which include radiation effects, neutron radiography, activation analysis, and fast reactor safety. During the past several years, the ACPR has become an important experimental facility for the United States Fast Reactor Safety Research Program and questions of interest to the safety of the LMFBR are being addressed. In order to enhance the capabilities of the ACPR for reactor safety experiments, a project to improve the performance of the reactor was initiated. It is anticipated that the pulse fluence can be increased by a factor of 2.0 to 2.5 utilizing a two-region core concept with high heat capacity fuel elements around the central irradiation cavity. In addition, the steady-state power of the reactor will be increased by about a factor of two. The new features of the improvements are described

  10. Price-Anderson Nuclear Safety Enforcement Program. 1997 annual report

    International Nuclear Information System (INIS)

    1998-01-01

    This report summarizes activities in the Department of Energy's Price-Anderson Amendments Act (PAAA) Enforcement Program in calendar year 1997 and highlights improvements planned for 1998. The DOE Enforcement Program involves the Office of Enforcement and Investigation in the DOE Headquarters Office of Environment, Safety and Health, as well as numerous PAAA Coordinators and technical advisors in DOE Field and Program Offices. The DOE Enforcement Program issued 13 Notices of Violation (NOV's) in 1997 for cases involving significant or potentially significant nuclear safety violations. Six of these included civil penalties totaling $440,000. Highlights of these actions include: (1) Brookhaven National Laboratory Radiological Control Violations / Associated Universities, Inc.; (2) Bioassay Program Violations at Mound / EG ampersand G, Inc.; (3) Savannah River Crane Operator Uptake / Westinghouse Savannah River Company; (4) Waste Calciner Worker Uptake / Lockheed-Martin Idaho Technologies Company; and (5) Reactor Scram and Records Destruction at Sandia / Sandia Corporation (Lockheed-Martin). Sandia / Sandia Corporation (Lockheed-Martin)

  11. Highway Safety Program Manual: Volume 8: Alcohol in Relation to Highway Safety.

    Science.gov (United States)

    National Highway Traffic Safety Administration (DOT), Washington, DC.

    Volume 8 of the 19-volume Highway Safety Program Manual (which provides guidance to State and local governments on preferred highway safety practices) concentrates on alcohol in relation to highway safety. The purpose and objectives of the alcohol program are outlined. Federal authority in the area of highway safety and general policies regarding…

  12. Implementation of a Radiological Safety Coach program

    Energy Technology Data Exchange (ETDEWEB)

    Konzen, K.K. [Safe Sites of Colorado, Golden, CO (United States). Rocky Flats Environmental Technology Site; Langsted, J.M. [M.H. Chew and Associates, Golden, CO (United States)

    1998-02-01

    The Safe Sites of Colorado Radiological Safety program has implemented a Safety Coach position, responsible for mentoring workers and line management by providing effective on-the-job radiological skills training and explanation of the rational for radiological safety requirements. This position is significantly different from a traditional classroom instructor or a facility health physicist, and provides workers with a level of radiological safety guidance not routinely provided by typical training programs. Implementation of this position presents a challenge in providing effective instruction, requiring rapport with the radiological worker not typically developed in the routine radiological training environment. The value of this unique training is discussed in perspective with cost-savings through better radiological control. Measures of success were developed to quantify program performance and providing a realistic picture of the benefits of providing one-on-one or small group training. This paper provides a description of the unique features of the program, measures of success for the program, a formula for implementing this program at other facilities, and a strong argument for the success (or failure) of the program in a time of increased radiological safety emphasis and reduced radiological safety budgets.

  13. Implementation of a Radiological Safety Coach program

    International Nuclear Information System (INIS)

    Konzen, K.K.

    1998-01-01

    The Safe Sites of Colorado Radiological Safety program has implemented a Safety Coach position, responsible for mentoring workers and line management by providing effective on-the-job radiological skills training and explanation of the rational for radiological safety requirements. This position is significantly different from a traditional classroom instructor or a facility health physicist, and provides workers with a level of radiological safety guidance not routinely provided by typical training programs. Implementation of this position presents a challenge in providing effective instruction, requiring rapport with the radiological worker not typically developed in the routine radiological training environment. The value of this unique training is discussed in perspective with cost-savings through better radiological control. Measures of success were developed to quantify program performance and providing a realistic picture of the benefits of providing one-on-one or small group training. This paper provides a description of the unique features of the program, measures of success for the program, a formula for implementing this program at other facilities, and a strong argument for the success (or failure) of the program in a time of increased radiological safety emphasis and reduced radiological safety budgets

  14. Improving Patient Safety: Improving Communication.

    Science.gov (United States)

    Bittner-Fagan, Heather; Davis, Joshua; Savoy, Margot

    2017-12-01

    Communication among physicians, staff, and patients is a critical element in patient safety. Effective communication skills can be taught and improved through training and awareness. The practice of family medicine allows for long-term relationships with patients, which affords opportunities for ongoing, high-quality communication. There are many barriers to effective communication, including patient factors, clinician factors, and system factors, but tools and strategies exist to address these barriers, improve communication, and engage patients in their care. Use of universal precautions for health literacy, appropriate medical interpreters, and shared decision-making are evidence-based tools that improve communication and increase patient safety. Written permission from the American Academy of Family Physicians is required for reproduction of this material in whole or in part in any form or medium.

  15. A strategic approach to quality improvement and patient safety education and resident integration in a general surgery residency.

    Science.gov (United States)

    O'Heron, Colette T; Jarman, Benjamin T

    2014-01-01

    To outline a structured approach for general surgery resident integration into institutional quality improvement and patient safety education and development. A strategic plan to address Accreditation Council for Graduate Medical Education (ACGME) Clinical Learning Environment Review assessments for resident integration into Quality Improvement and Patient Safety initiatives is described. Gundersen Lutheran Medical Foundation is an independent academic medical center graduating three categorical residents per year within an integrated multi-specialty health system serving 19 counties over 3 states. The quality improvement and patient safety education program includes a formal lecture series, online didactic sessions, mandatory quality improvement or patient safety projects, institutional committee membership, an opportunity to serve as a designated American College of Surgeons National Surgical Quality Improvement Project and Quality in Training representative, mandatory morbidity and mortality conference attendance and clinical electives in rural surgery and international settings. Structured education regarding and participation in quality improvement and patient safety programs are able to be accomplished during general surgery residency. The long-term outcomes and benefits of these strategies are unknown at this time and will be difficult to measure with objective data. © 2013 Published by Association of Program Directors in Surgery on behalf of Association of Program Directors in Surgery.

  16. Safety and economic impacts of photo radar program.

    Science.gov (United States)

    Chen, Greg

    2005-12-01

    means to manage traffic speed, reduce collisions and injuries, and combat the huge resulting economic burden to society. The cost-effectiveness of the program takes on special meaning and urgency when considering the present and future government funding constraints. The application of the program, however, should be planned and implemented with caution. Every effort should be made to focus on and to promote the program on safety improvement grounds. The program can be easily terminated because of political considerations, if the public perceives it as a cash cow to enhance government revenue.

  17. Public Health Service Safety Program

    Energy Technology Data Exchange (ETDEWEB)

    McBride, J R [Southwestern Radiological Health Laboratory, Las Vegas, NV (United States)

    1969-07-01

    Off-Site Radiological Safety Programs conducted on past Plowshare experimental projects by the Southwestern Radiological Health Laboratory for the AEC will be presented. Emphasis will be placed on the evaluation of the potential radiation hazard to off-site residents, the development of an appropriate safety plan, pre- and post-shot surveillance activities, and the necessity for a comprehensive and continuing community relations program. In consideration of the possible wide use of nuclear explosives in industrial applications, a new approach to off-site radiological safety will be discussed. (author)

  18. Public Health Service Safety Program

    International Nuclear Information System (INIS)

    McBride, J.R.

    1969-01-01

    Off-Site Radiological Safety Programs conducted on past Plowshare experimental projects by the Southwestern Radiological Health Laboratory for the AEC will be presented. Emphasis will be placed on the evaluation of the potential radiation hazard to off-site residents, the development of an appropriate safety plan, pre- and post-shot surveillance activities, and the necessity for a comprehensive and continuing community relations program. In consideration of the possible wide use of nuclear explosives in industrial applications, a new approach to off-site radiological safety will be discussed. (author)

  19. Radiologic safety program for ionizing radiation facilities in Parana, Brazil

    International Nuclear Information System (INIS)

    Schmidt, M.F.S.; Tilly Junior, J.G.

    1997-01-01

    A radiologic safety program for inspection, licensing and control of the use of ionizing radiation in medical, industrial and research facilities in Parana, Brazil is presented. The program includes stages such as: 1- division into implementation phases considering the activity development for each area; 2-use of the existing structure to implement and to improve services. The development of the program will permit to evaluate the improvement reached and to correct operational strategic. As a result, a quality enhancement at the services performed, a reduction for radiation dose exposure and a faster response for emergency situations will be expected

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-07-01

    Alberta Environment's water management operations (WMO) own and operates 46 dams and 800 km of canals. This presentation discussed a rehabilitation program designed to improve the safety of the WMO's Calgary weir which was built in 1908 to encourage settlement in the province. The weir includes a 32 m wide sluiceway, a 2.5 m concrete weir, and a fish ladder. A portage trail has been built to accommodate canoes, and signs are posted to indicate the hazards associated with the weir. The WMO has also launched an advertising campaign to outline hazards to the general public. The WMO has a contract with the Calgary fire department (CFD) to maintain a safety boom and provide rescue operations at the weir. The weir project aims to accommodate access and safety while enhancing flood conveyance capabilities of the weir. The project will allow upstream passage for patrol boats operated by the Calgary fire department's aquatic rescue service. The final design of the weir will include a series of drops constructed downstream of the weir to create pool and riffle structures that will eliminate hydraulic rollers. Notches will be cut in the weir to regulate flows moving through the new low and high flow channels. Case studies of other low-head dams operated by the WMO were also presented. tabs., figs.

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

    Science.gov (United States)

    Mascherek, Anna C.

    2017-01-01

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

  2. Leveraging Safety Programs to Improve and Support Security Programs

    Energy Technology Data Exchange (ETDEWEB)

    Leach, Janice [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Snell, Mark K. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Pratt, R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Sandoval, S. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-10-01

    There has been a long history of considering Safety, Security, and Safeguards (3S) as three functions of nuclear security design and operations that need to be properly and collectively integrated with operations. This paper specifically considers how safety programmes can be extended directly to benefit security as part of an integrated facility management programme. The discussion will draw on experiences implementing such a programme at Sandia National Laboratories’ Annular Research Reactor Facility. While the paper focuses on nuclear facilities, similar ideas could be used to support security programmes at other types of high-consequence facilities and transportation activities.

  3. NASA Aviation Safety Program Systems Analysis/Program Assessment Metrics Review

    Science.gov (United States)

    Louis, Garrick E.; Anderson, Katherine; Ahmad, Tisan; Bouabid, Ali; Siriwardana, Maya; Guilbaud, Patrick

    2003-01-01

    The goal of this project is to evaluate the metrics and processes used by NASA's Aviation Safety Program in assessing technologies that contribute to NASA's aviation safety goals. There were three objectives for reaching this goal. First, NASA's main objectives for aviation safety were documented and their consistency was checked against the main objectives of the Aviation Safety Program. Next, the metrics used for technology investment by the Program Assessment function of AvSP were evaluated. Finally, other metrics that could be used by the Program Assessment Team (PAT) were identified and evaluated. This investigation revealed that the objectives are in fact consistent across organizational levels at NASA and with the FAA. Some of the major issues discussed in this study which should be further investigated, are the removal of the Cost and Return-on-Investment metrics, the lack of the metrics to measure the balance of investment and technology, the interdependencies between some of the metric risk driver categories, and the conflict between 'fatal accident rate' and 'accident rate' in the language of the Aviation Safety goal as stated in different sources.

  4. 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

  5. USSR orders computers to improve nuclear safety

    International Nuclear Information System (INIS)

    Anon.

    1990-01-01

    Control Data Corp (CDC) has received an order valued at $32-million from the Soviet Union for six Cyber 962 mainframe computer systems to be used to increase the safety of civilian nuclear powerplants. The firm is now waiting for approval of the contract by the US government and Western Allies. The computers, ordered by the Soviet Research and Development Institute of Power Engineering (RDIPE), will analyze safety factors in the operation of nuclear reactors over a wide range of conditions. The Soviet Union's civilian nuclear program is one of the largest in the world, with over 50 plants in operation. Types of safety analyses the computers perform include: neutron-physics calculations, radiation-protection studies, stress analysis, reliability analysis of equipment and systems, ecological-impact calculations, transient analysis, and support activities for emergency response. They also include a simulator with realistic mathematical models of Soviet nuclear powerplants to improve operator training

  6. Pressure Safety Program Implementation at ORNL

    Energy Technology Data Exchange (ETDEWEB)

    Lower, Mark [ORNL; Etheridge, Tom [ORNL; Oland, C. Barry [XCEL Engineering, Inc.

    2013-01-01

    The Oak Ridge National Laboratory (ORNL) is a US Department of Energy (DOE) facility that is managed by UT-Battelle, LLC. In February 2006, DOE promulgated worker safety and health regulations to govern contractor activities at DOE sites. These regulations, which are provided in 10 CFR 851, Worker Safety and Health Program, establish requirements for worker safety and health program that reduce or prevent occupational injuries, illnesses, and accidental losses by providing DOE contractors and their workers with safe and healthful workplaces at DOE sites. The regulations state that contractors must achieve compliance no later than May 25, 2007. According to 10 CFR 851, Subpart C, Specific Program Requirements, contractors must have a structured approach to their worker safety and health programs that at a minimum includes provisions for pressure safety. In implementing the structured approach for pressure safety, contractors must establish safety policies and procedures to ensure that pressure systems are designed, fabricated, tested, inspected, maintained, repaired, and operated by trained, qualified personnel in accordance with applicable sound engineering principles. In addition, contractors must ensure that all pressure vessels, boilers, air receivers, and supporting piping systems conform to (1) applicable American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (2004) Sections I through XII, including applicable code cases; (2) applicable ASME B31 piping codes; and (3) the strictest applicable state and local codes. When national consensus codes are not applicable because of pressure range, vessel geometry, use of special materials, etc., contractors must implement measures to provide equivalent protection and ensure a level of safety greater than or equal to the level of protection afforded by the ASME or applicable state or local codes. This report documents the work performed to address legacy pressure vessel deficiencies and comply

  7. Surgical Technical Evidence Review for Elective Total Joint Replacement Conducted for the AHRQ Safety Program for Improving Surgical Care and Recovery

    Science.gov (United States)

    Siletz, Anaar E.; Singer, Emily S.; Faltermeier, Claire; Hu, Q. Lina; Ko, Clifford Y.; Golladay, Gregory J.; Kates, Stephen L.; Wick, Elizabeth C.; Maggard-Gibbons, Melinda

    2018-01-01

    Background: Use of enhanced recovery pathways (ERPs) can improve patient outcomes, yet national implementation of these pathways remains low. The Agency for Healthcare Research and Quality (AHRQ; funder), the American College of Surgeons, and the Johns Hopkins Medicine Armstrong Institute for Patent Safety and Quality have developed the Safety Program for Improving Surgical Care and Recovery—a national effort to catalyze implementation of practices to improve perioperative care and enhance recovery of surgical patients. This review synthesizes evidence that can be used to develop a protocol for elective total knee arthroplasty (TKA) and total hip arthroplasty (THA). Study Design: This review focuses on potential components of the protocol relevant to surgeons; anesthesia components are reported separately. Components were identified through review of existing pathways and from consultation with technical experts. For each, a structured review of MEDLINE identified systematic reviews, randomized trials, and observational studies that reported on these components in patients undergoing elective TKA/THA. This primary evidence review was combined with existing clinical guidelines in a narrative format. Results: Sixteen components were reviewed. Of the 10 preoperative components, most were focused on risk factor assessment including anemia, diabetes mellitus, tobacco use, obesity, nutrition, immune-modulating therapy, and opiates. Preoperative education, venous thromboembolism (VTE) prophylaxis, and bathing/Staphylococcus aureus decolonization were also included. The routine use of drains was the only intraoperative component evaluated. The 5 postoperative components included early mobilization, continuous passive motion, extended duration VTE prophylaxis, early oral alimentation, and discharge planning. Conclusion: This review synthesizes the evidence supporting potential surgical components of an ERP for elective TKA/THA. The AHRQ Safety Program for Improving

  8. Surgical Technical Evidence Review for Elective Total Joint Replacement Conducted for the AHRQ Safety Program for Improving Surgical Care and Recovery.

    Science.gov (United States)

    Childers, Christopher P; Siletz, Anaar E; Singer, Emily S; Faltermeier, Claire; Hu, Q Lina; Ko, Clifford Y; Golladay, Gregory J; Kates, Stephen L; Wick, Elizabeth C; Maggard-Gibbons, Melinda

    2018-01-01

    Use of enhanced recovery pathways (ERPs) can improve patient outcomes, yet national implementation of these pathways remains low. The Agency for Healthcare Research and Quality (AHRQ; funder), the American College of Surgeons, and the Johns Hopkins Medicine Armstrong Institute for Patent Safety and Quality have developed the Safety Program for Improving Surgical Care and Recovery-a national effort to catalyze implementation of practices to improve perioperative care and enhance recovery of surgical patients. This review synthesizes evidence that can be used to develop a protocol for elective total knee arthroplasty (TKA) and total hip arthroplasty (THA). This review focuses on potential components of the protocol relevant to surgeons; anesthesia components are reported separately. Components were identified through review of existing pathways and from consultation with technical experts. For each, a structured review of MEDLINE identified systematic reviews, randomized trials, and observational studies that reported on these components in patients undergoing elective TKA/THA. This primary evidence review was combined with existing clinical guidelines in a narrative format. Sixteen components were reviewed. Of the 10 preoperative components, most were focused on risk factor assessment including anemia, diabetes mellitus, tobacco use, obesity, nutrition, immune-modulating therapy, and opiates. Preoperative education, venous thromboembolism (VTE) prophylaxis, and bathing/ Staphylococcus aureus decolonization were also included. The routine use of drains was the only intraoperative component evaluated. The 5 postoperative components included early mobilization, continuous passive motion, extended duration VTE prophylaxis, early oral alimentation, and discharge planning. This review synthesizes the evidence supporting potential surgical components of an ERP for elective TKA/THA. The AHRQ Safety Program for Improving Surgical Care and Recovery aims to guide hospitals and

  9. Improved obstetric safety through programmatic collaboration.

    Science.gov (United States)

    Goffman, Dena; Brodman, Michael; Friedman, Arnold J; Minkoff, Howard; Merkatz, Irwin R

    2014-01-01

    Healthcare safety and quality are critically important issues in obstetrics, and society, healthcare providers, patients and insurers share a common goal of working toward safer practice, and are continuously seeking strategies to facilitate improvements. To this end, 4 New York City voluntary hospitals with large maternity services initiated a unique collaborative quality improvement program. It was facilitated by their common risk management advisors, FOJP Service Corporation, and their professional liability insurer, Hospitals Insurance Company. Under the guidance of 4 obstetrics and gynecology departmental chairmen, consensus best practices for obstetrics were developed which included: implementation of evidence based protocols with audit and feedback; standardized educational interventions; mandatory electronic fetal monitoring training; and enhanced in-house physician coverage. Each institution developed unique safety related expertise (development of electronic documentation, team training, and simulation education), and experiences were shared across the collaborative. The collaborative group developed robust systems for audit of outcomes and documentation quality, as well as enforcement mechanisms. Ongoing feedback to providers served as a key component of the intervention. The liability carrier provided financial support for these patient safety innovations. As a result of the interventions, the overall AOI for our institutions decreased 42% from baseline (January-June 2008) to the most recently reviewed time period (July-December 2011) (10.7% vs 6.2%, p Risk Management of the American Hospital Association.

  10. Process safety improvement-Quality and target zero

    Energy Technology Data Exchange (ETDEWEB)

    Van Scyoc, Karl [Det Norske Veritas (U.S.A.) Inc., DNV Energy Solutions, 16340 Park Ten Place, Suite 100, Houston, TX 77084 (United States)], E-mail: karl.van.scyoc@dnv.com

    2008-11-15

    Process safety practitioners have adopted quality management principles in design of process safety management systems with positive effect, yet achieving safety objectives sometimes remain a distant target. Companies regularly apply tools and methods which have roots in quality and productivity improvement. The 'plan, do, check, act' improvement loop, statistical analysis of incidents (non-conformities), and performance trending popularized by Dr. Deming are now commonly used in the context of process safety. Significant advancements in HSE performance are reported after applying methods viewed as fundamental for quality management. In pursuit of continual process safety improvement, the paper examines various quality improvement methods, and explores how methods intended for product quality can be additionally applied to continual improvement of process safety. Methods such as Kaizen, Poke yoke, and TRIZ, while long established for quality improvement, are quite unfamiliar in the process safety arena. These methods are discussed for application in improving both process safety leadership and field work team performance. Practical ways to advance process safety, based on the methods, are given.

  11. Process safety improvement-Quality and target zero

    International Nuclear Information System (INIS)

    Van Scyoc, Karl

    2008-01-01

    Process safety practitioners have adopted quality management principles in design of process safety management systems with positive effect, yet achieving safety objectives sometimes remain a distant target. Companies regularly apply tools and methods which have roots in quality and productivity improvement. The 'plan, do, check, act' improvement loop, statistical analysis of incidents (non-conformities), and performance trending popularized by Dr. Deming are now commonly used in the context of process safety. Significant advancements in HSE performance are reported after applying methods viewed as fundamental for quality management. In pursuit of continual process safety improvement, the paper examines various quality improvement methods, and explores how methods intended for product quality can be additionally applied to continual improvement of process safety. Methods such as Kaizen, Poke yoke, and TRIZ, while long established for quality improvement, are quite unfamiliar in the process safety arena. These methods are discussed for application in improving both process safety leadership and field work team performance. Practical ways to advance process safety, based on the methods, are given

  12. Process safety improvement--quality and target zero.

    Science.gov (United States)

    Van Scyoc, Karl

    2008-11-15

    Process safety practitioners have adopted quality management principles in design of process safety management systems with positive effect, yet achieving safety objectives sometimes remain a distant target. Companies regularly apply tools and methods which have roots in quality and productivity improvement. The "plan, do, check, act" improvement loop, statistical analysis of incidents (non-conformities), and performance trending popularized by Dr. Deming are now commonly used in the context of process safety. Significant advancements in HSE performance are reported after applying methods viewed as fundamental for quality management. In pursuit of continual process safety improvement, the paper examines various quality improvement methods, and explores how methods intended for product quality can be additionally applied to continual improvement of process safety. Methods such as Kaizen, Poke yoke, and TRIZ, while long established for quality improvement, are quite unfamiliar in the process safety arena. These methods are discussed for application in improving both process safety leadership and field work team performance. Practical ways to advance process safety, based on the methods, are given.

  13. Price-Anderson Nuclear Safety Enforcement Program. 1996 Annual report

    International Nuclear Information System (INIS)

    1996-01-01

    This first annual report on DOE's Price Anderson Amendments Act enforcement program covers the activities, accomplishments, and planning for calendar year 1996. It also includes the infrastructure development activities of 1995. It encompasses the activities of the headquarters' Office of Enforcement in the Office of Environment, Safety and Health (EH) and Investigation and the coordinators and technical advisors in DOE's Field and Program Offices and other EH Offices. This report includes an overview of the enforcement program; noncompliances, investigations, and enforcement actions; summary of significant enforcement actions; examples where enforcement action was deferred; and changes and improvements to the program

  14. Crash Data Improvement Program : An RSPCB Peer Exchange

    Science.gov (United States)

    2011-08-04

    This report provides a summary of the Crash Data Improvement Program (CDIP) peer : exchange sponsored by the Federal Highway Administrations (FHWA) Office of Safety : on August 4, 2011. The peer exchange was hosted in conjunction with the annual :...

  15. Bohunice Nuclear Power Plant Safety Upgrading Program

    International Nuclear Information System (INIS)

    Toth, A.; Fagula, L.

    1996-01-01

    Bohunice nuclear Power Plant generation represents almost 50% of the Slovak republic electric power production. Due to such high level of commitment to nuclear power in the power generation system, a special attention is given to safe and reliable operation of NPPs. Safety upgrading and operational reliability improvement of Bohunice V-1 NPP was carried out by the Bohunice staff continuously since the plant commissioning. In the 1990 - 1993 period extensive projects were realised. As a result of 'Small Reconstruction of the Bohunice V-1 NPP', the standards of both the nuclear safety and operational reliability have been significantly improved. The implementation of another modifications that will take place gradually during extended refuelling outages and overhauls in the course of 1996 through 1999, is referred to as the Gradual Reconstruction of the Bohunice V-1 Plant. The general goal of the V-1 NPP safety upgrading is the achievement of internationally acceptable level of nuclear safety. Extensive and financially demanding modification process of Bohunice V-2 NPP is likely to be implemented after a completion of the Gradual Reconstruction of the Bohunice V-1 NPP, since the year 1999. With this in mind, a first draft of the strategy of the Bohunice V-2 NPP upgrading program based on Probabilistic Safety assessment consideration was developed. A number of actions with a general effect on Bohunice site safety is evident. All these activities are aimed at reaching the essential objective of Bohunice NPP Management - to ensure a safe, reliable and effective electric energy and heat generation at the Bohunice site. (author)

  16. National Ignition Facility Project Site Safety Program

    International Nuclear Information System (INIS)

    Dun, C

    2003-01-01

    This Safety Program for the National Ignition Facility (NIF) presents safety protocols and requirements that management and workers shall follow to assure a safe and healthful work environment during activities performed on the NIF Project site. The NIF Project Site Safety Program (NPSSP) requires that activities at the NIF Project site be performed in accordance with the ''LLNL ES and H Manual'' and the augmented set of controls and processes described in this NIF Project Site Safety Program. Specifically, this document: (1) Defines the fundamental NIF site safety philosophy. (2) Defines the areas covered by this safety program (see Appendix B). (3) Identifies management roles and responsibilities. (4) Defines core safety management processes. (5) Identifies NIF site-specific safety requirements. This NPSSP sets forth the responsibilities, requirements, rules, policies, and regulations for workers involved in work activities performed on the NIF Project site. Workers are required to implement measures to create a universal awareness that promotes safe practice at the work site and will achieve NIF management objectives in preventing accidents and illnesses. ES and H requirements are consistent with the ''LLNL ES and H Manual''. This NPSSP and implementing procedures (e.g., Management Walkabout, special work procedures, etc.,) are a comprehensive safety program that applies to NIF workers on the NIF Project site. The NIF Project site includes the B581/B681 site and support areas shown in Appendix B

  17. An evaluation of an airline cabin safety education program for elementary school children.

    Science.gov (United States)

    Liao, Meng-Yuan

    2014-04-01

    The knowledge, attitude, and behavior intentions of elementary school students about airline cabin safety before and after they took a specially designed safety education course were examined. A safety education program was designed for school-age children based on the cabin safety briefings airlines given to their passengers, as well as on lessons learned from emergency evacuations. The course is presented in three modes: a lecture, a demonstration, and then a film. A two-step survey was used for this empirical study: an illustrated multiple-choice questionnaire before the program, and, upon completion, the same questionnaire to assess its effectiveness. Before the program, there were significant differences in knowledge and attitude based on school locations and the frequency that students had traveled by air. After the course, students showed significant improvement in safety knowledge, attitude, and their behavior intention toward safety. Demographic factors, such as gender and grade, also affected the effectiveness of safety education. The study also showed that having the instructor directly interact with students by lecturing is far more effective than presenting the information using only video media. A long-term evaluation, the effectiveness of the program, using TV or video accessible on the Internet to deliver a cabin safety program, and a control group to eliminate potential extraneous factors are suggested for future studies. Copyright © 2013 Elsevier Ltd. All rights reserved.

  18. The U.S. Nuclear Regulatory Commission seismic safety research program

    International Nuclear Information System (INIS)

    Kenneally, R.M.; Guzy, D.J.; Murphy, A.J.

    1988-01-01

    The seismic safety research program sponsored by the U.S. Nuclear Regulatory Commission is directed toward improving the evaluation of potential earthquake effects on nuclear power plant operations. The research has been divided into three major program areas: earth sciences, seismic design margins, and fragilities and response. A major thrust of this research is to assess plant behavior for seismic events more severe and less probable than those considered in design. However, there is also research aimed at improving the evaluation of earthquake input and plant response at plant design levels

  19. Fusion safety program Annual report, Fiscal year 1995

    International Nuclear Information System (INIS)

    Longhurst, G.R.; Cadwallader, L.C.; Carmack, W.J.

    1995-12-01

    This report summarizes the major activities of the Fusion Safety Program in FY-95. The Idaho National Engineering Laboratory (INEL) is the designated lead laboratory, and Lockheed Idaho Technologies Company is the prime contractor for this program. The Fusion Safety Program was initiated in 1979. Activities are conducted at the INEL, at other DOE laboratories, and at other institutions. Among the technical areas covered in this report are tritium safety, beryllium safety, chemical reactions and activation product release, safety aspects of fusion magnet systems, plasma disruptions, risk assessment failure rate database development, and safety code development and application to fusion safety issues. Most of this work has been done in support of the International Thermonuclear Experimental Reactor (ITER). Also included in the report are summaries of the safety and environmental studies performed by the Fusion Safety Program for the Tokamak Physics Experiment and the Tokamak Fusion Test Reactor and the technical support for commercial fusion facility conceptual design studies. A final activity described is work to develop DOE Technical Standards for Safety of Fusion Test Facilities

  20. Recommendations to improve radiation safety during invasive cardiovascular procedures

    International Nuclear Information System (INIS)

    Miranda, Patricia; Ubeda, Carlos; Vano, Eliseo; Nocetti, Diego

    2014-01-01

    In this paper we present guidelines aimed to improve radiation safety during invasive cardiovascular procedures. Unwanted effects upon patients and medical personnel are conventionally classified. A program of Quality Assurance is proposed, an aspect of which is a program for radiologic protection, including operator protection, radiation monitoring, shielding and personnel training. Permanent and specific actions should be taken at every cardiovascular lab, before, during and after interventions. In order to implement these guidelines and actions, a fundamental step is a review of current legislation. Specific programs for quality control and radiologic protection along with a definition of acceptable radiation exposure doses are required

  1. 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

  2. A Scholarly Pathway in Quality Improvement and Patient Safety.

    Science.gov (United States)

    Ferguson, Catherine C; Lamb, Geoffrey

    2015-10-01

    There are several challenges to teaching quality improvement (QI) and patient safety material to medical students, as successful programs should combine didactic and experiential teaching methods, integrate the material into the preclinical and clinical years, and tailor the material to the schools' existing curriculum. The authors describe the development, implementation, and assessment of the Quality Improvement and Patient Safety (QuIPS) Scholarly Pathway-a faculty-mentored, three-year experience for students interested in gaining exposure to QI and patient safety concepts at the Medical College of Wisconsin (MCW). The QuIPS pathway capitalized on the existing structure of scholarly pathways for MCW medical students, allowing QI and patient safety to be incorporated into the existing curriculum using didactic and experiential instruction and spanning preclinical and clinical education. Student reaction to the QuIPS pathway has been favorable. Preliminary data demonstrate that student knowledge as measured by the Quality Improvement Knowledge Assessment Tool significantly increased after the first year of implementation. A novel curriculum such as the QuIPS pathway provides an important opportunity to develop and test new assessment tools for curricula in systems-based practice and practice-based learning and improvement. The authors also hope that by bringing together local QI and patient safety experts and stakeholders during the curricular development process, they have laid the groundwork for the creation of a more pervasive curriculum that will reach all MCW students in the future. The model may be generalizable to other U.S. medical schools with scholarly pathways as well.

  3. Evaluating the Effectiveness of an Educational Intervention to Improve the Patient Safety Attitudes of Intern Pharmacists.

    Science.gov (United States)

    Walpola, Ramesh L; Fois, Romano A; McLachlan, Andrew J; Chen, Timothy F

    2017-02-25

    Objective. To evaluate the effectiveness of a face-to-face educational intervention in improving the patient safety attitudes of intern pharmacists. Methods. A patient safety education program was delivered to intern pharmacists undertaking The University of Sydney Intern Training Program in 2014. Their patient safety attitudes were evaluated immediately prior to, immediately after, and three-months post-intervention. Underlying attitudinal factors were identified using exploratory factor analysis. Changes in factor scores were examined using analysis of variance. Results. Of the 120 interns enrolled, 95 (78.7%) completed all three surveys. Four underlying attitudinal factors were identified: attitudes towards addressing errors, questioning behaviors, blaming individuals, and reporting errors. Improvements in all attitudinal factors were evident immediately after the intervention. However, only improvements in attitudes towards blaming individuals involved in errors were sustained at three months post-intervention. Conclusion. The educational intervention was associated with short-term improvements in pharmacist interns' patient safety attitudes. However, other factors likely influenced their attitudes in the longer term.

  4. Radiation safety program in high dose rate brachytherapy facility at INHS Asvini

    Directory of Open Access Journals (Sweden)

    Kirti Tyagi

    2014-01-01

    Full Text Available Brachytherapy concerns primarily the use of radioactive sealed sources which are inserted into catheters or applicators and placed directly into tissue either inside or very close to the target volume. The use of radiation in treatment of patients involves both benefits and risks. It has been reported that early radiation workers had developed radiation induced cancers. These incidents lead to continuous work for the improvement of radiation safety of patients and personnel The use of remote afterloading equipment has been developed to improve radiation safety in the delivery of treatment in brachytherapy. The widespread adoption of high dose rate brachytherapy needs appropriate quality assurance measures to minimize the risks to both patients and medical staff. The radiation safety program covers five major aspects: quality control, quality assurance, radiation monitoring, preventive maintenance, administrative measures and quality audit. This paper will discuss the radiation safety program developedfor a high dose rate brachytherapy facility at our centre which may serve as a guideline for other centres intending to install a similar facility.

  5. Seismic safety margins research program overview

    International Nuclear Information System (INIS)

    Tokarz, F.J.; Smith, P.D.

    1978-01-01

    A multiyear seismic research program has been initiated at the Lawrence Livermore Laboratory. This program, the Seismic Safety Margins Research Program (SSMRP) is funded by the U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research. The program is designed to develop a probabilistic systems methodology for determining the seismic safety margins of nuclear power plants. Phase I, extending some 22 months, began in July 1978 at a funding level of approximately $4.3 million. Here we present an overview of the SSMRP. Included are discussions on the program objective, the approach to meet the program goal and objectives, end products, the probabilistic systems methodology, and planned activities for Phase I

  6. Nuclear Criticality Safety Department Qualification Program

    International Nuclear Information System (INIS)

    Carroll, K.J.; Taylor, R.G.; Worley, C.A.

    1996-01-01

    The Nuclear Criticality Safety Department (NCSD) is committed to developing and maintaining a staff of highly qualified personnel to meet the current and anticipated needs in Nuclear Criticality Safety (NCS) at the Oak Ridge Y-12 Plant. This document defines the Qualification Program to address the NCSD technical and managerial qualification as required by the Y-1 2 Training Implementation Matrix (TIM). This Qualification Program is in compliance with DOE Order 5480.20A and applicable Lockheed Martin Energy Systems, Inc. (LMES) and Y-1 2 Plant procedures. It is implemented through a combination of WES plant-wide training courses and professional nuclear criticality safety training provided within the department. This document supersedes Y/DD-694, Revision 2, 2/27/96, Qualification Program, Nuclear Criticality Safety Department There are no backfit requirements associated with revisions to this document

  7. National HTGR safety program

    International Nuclear Information System (INIS)

    Davis, D.E.; Kelley, A.P. Jr.

    1982-01-01

    This paper presents an overview of the National HTGR Program in the US with emphasis on the safety and licensing strategy being pursued. This strategy centers upon the development of an integrated approach to organizing and classifying the functions needed to produce safe and economical nuclear power production. At the highest level, four plant goals are defined - Normal Operation, Core and Plant Protection, Containment Integrity and Emergency Preparedness. The HTGR features which support the attainment of each goal are described and finally a brief summary is provided of the current status of the principal safety development program supporting the validation of the four plant goals

  8. Safety improvements of Temelin NPP

    International Nuclear Information System (INIS)

    Vita, J.

    2000-01-01

    A detailed overview is given of the efforts made to enhance the safety level of the plant considering recommendations of a number of assessment missions. A list is presented of 10 international missions of the IAEA at the Temelin plant, covering the period 1990 to 1998. For each mission the date and objective is given, the focus of the assessment is characterized, the international participation of experts is specified, and the main conclusions of the experts is reproduced. A commented list of 60 main design changes and safety improvements is also included, as they were implemented in the wake of various safety assessments. An overview of the Temelin safety improvement programme is attached, comprising brief descriptions of 30 planned improvement items together with the time schedules. (A.K.)

  9. Application of visualization and simulation program to improve work zone safety and mobility.

    Science.gov (United States)

    2010-01-01

    "A previous study sponsored by the Smart Work Zone Deployment Initiative, Feasibility of Visualization and Simulation Applications to Improve Work Zone Safety and Mobility, demonstrated the feasibility of combining readily available, inexpensiv...

  10. An augmented audit program for assuring radiation safety during radiographic examination operations

    International Nuclear Information System (INIS)

    Jervey, R.A. Jr.; Papin, P.J.

    1993-01-01

    Auditing a gamma radiography program is required as part of the authorizing license. Checklists and cursory reviews are the typical approach to addressing program requirements. A more proactive approach is recommended. The audit program described was prepared for a specific set of operating conditions but can be applied to any given program. Improvements in the effectiveness of the radiography safety program can be made with additional examination and emphasis on direct observation of licensed activities

  11. A study of the international trend and comprehensive enhancement program on the Nuclear Power Plant safety

    International Nuclear Information System (INIS)

    Jang, Soon Hong; Cho, Nam Jin; Paek, Won Phil

    1990-12-01

    The objectives of this study are as follows : overview of the international trend related to the safety of Nuclear Power Plant(NPPs), study of the present status of NPP safety in Korea in aspects of design, construction and operation, suggestion of the comprehensive program to improve NPP safety in Korea. The results of this study can contribute to improve the safety of existing and future NPPs, and to establish the severe accident policy in Korea

  12. A study of the international trend and comprehensive enhancement program on the Nuclear Power Plant safety

    Energy Technology Data Exchange (ETDEWEB)

    Jang, Soon Hong; Cho, Nam Jin; Paek, Won Phil [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

    1990-12-15

    The objectives of this study are as follows : overview of the international trend related to the safety of Nuclear Power Plant(NPPs), study of the present status of NPP safety in Korea in aspects of design, construction and operation, suggestion of the comprehensive program to improve NPP safety in Korea. The results of this study can contribute to improve the safety of existing and future NPPs, and to establish the severe accident policy in Korea.

  13. Design safety improvements of Kozloduy NPP

    International Nuclear Information System (INIS)

    Hinovski, I.

    1999-01-01

    Design safety improvements of Kozloduy NPP, discussed in detail, are concerned with: primary circuit integrity; reactor pressure vessel integrity; primary coolant piping integrity; primary coolant overpressure protection; leak before break status; design basis accidents and transients; severe accident analysis; improvements of safety and support systems; containment/confinement leak tightness and strength; seismic safety improvements; WWER-1000 control rod insertion; upgrading and modernization of Units 5 and 6; Year 2000 problem

  14. The Department of Energy nuclear criticality safety program

    International Nuclear Information System (INIS)

    Felty, J.R.

    2004-01-01

    This paper broadly covers key events and activities from which the Department of Energy Nuclear Criticality Safety Program (NCSP) evolved. The NCSP maintains fundamental infrastructure that supports operational criticality safety programs. This infrastructure includes continued development and maintenance of key calculational tools, differential and integral data measurements, benchmark compilation, development of training resources, hands-on training, and web-based systems to enhance information preservation and dissemination. The NCSP was initiated in response to Defense Nuclear Facilities Safety Board Recommendation 97-2, Criticality Safety, and evolved from a predecessor program, the Nuclear Criticality Predictability Program, that was initiated in response to Defense Nuclear Facilities Safety Board Recommendation 93-2, The Need for Critical Experiment Capability. This paper also discusses the role Dr. Sol Pearlstein played in helping the Department of Energy lay the foundation for a robust and enduring criticality safety infrastructure.

  15. DOE Defense Program (DP) safety programs. Final report, Task 003

    International Nuclear Information System (INIS)

    1998-01-01

    The overall objective of the work on Task 003 of Subcontract 9-X52-W7423-1 was to provide LANL with support to the DOE Defense Program (DP) Safety Programs. The effort included the identification of appropriate safety requirements, the refinement of a DP-specific Safety Analysis Report (SAR) Format and Content Guide (FCG) and Comprehensive Review Plan (CRP), incorporation of graded approach instructions into the guidance, and the development of a safety analysis methodologies document. All tasks which were assigned under this Task Order were completed. Descriptions of the objectives of each task and effort performed to complete each objective is provided here

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

    Science.gov (United States)

    Nielsen, Kent J

    2014-02-01

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

  17. Safety program considerations for space nuclear reactor systems

    International Nuclear Information System (INIS)

    Cropp, L.O.

    1984-08-01

    This report discusses the necessity for in-depth safety program planning for space nuclear reactor systems. The objectives of the safety program and a proposed task structure is presented for meeting those objectives. A proposed working relationship between the design and independent safety groups is suggested. Examples of safety-related design philosophies are given

  18. Evaluation of a guided continuous quality improvement program in community pharmacies.

    Science.gov (United States)

    Chinthammit, Chanadda; Rupp, Michael T; Armstrong, Edward P; Modisett, Tara; Snead, Rebecca P; Warholak, Terri L

    2017-01-01

    The importance of creating and sustaining a strong culture of patient safety has been recognized as a critical component of safe medication use. This study aims to assess changes in attitudes toward patient safety culture and frequency of quality-related event (QRE) reporting after guided implementation of a continuous quality improvement (CQI) program in a panel of community pharmacies in the United States (U.S.). Twenty-one community pharmacies volunteered to participate in the project and were randomly assigned to intervention or control groups. Pharmacy staff in the intervention group received guided training to ensure full implementation of a CQI program while those in the control group partially implemented the program. Pharmacy staff in both groups completed retrospective pre-post safety culture questionnaires and reported medication errors and near misses that occurred in their practices. Rasch analysis was applied to assess questionnaire validity and reliability and to confirm if the ordinal level data approximated interval level measures. Paired t-tests and repeated measure analysis of covariance tests were subsequently used to compare observed changes in the attitudes of subjects and frequency of QREs reporting in intervention and control groups. Sixty-nine employees completed the questionnaire, a 43.9% response rate. Improvement in attitudes toward patient safety was statistically significant in the intervention group in six domains: staff, training, and skill ( p  = 0.017); patient counseling ( p  = 0.043); communication about mistakes ( p  continuous improvement ( p  < 0.001); and overall patient safety perceptions ( p  = 0.033). No significant differences were observed in QRE reporting rates between intervention and control groups. However, differences were observed in the types of QREs reported (e.g., incorrect safety cap) and the point in the prescription processing workflow where a QRE was detected (e.g., partner check station, and drug

  19. Fusion Safety Program annual report, fiscal year 1994

    International Nuclear Information System (INIS)

    Longhurst, G.R.; Cadwallader, L.C.; Dolan, T.J.; Herring, J.S.; McCarthy, K.A.; Merrill, B.J.; Motloch, C.G.; Petti, D.A.

    1995-03-01

    This report summarizes the major activities of the Fusion Safety Program in fiscal year 1994. The Idaho National Engineering Laboratory (INEL) is the designated lead laboratory and Lockheed Idaho Technologies Company is the prime contractor for this program. The Fusion Safety Program was initiated in 1979. Activities are conducted at the INEL, at other DOE laboratories, and at other institutions, including the University of Wisconsin. The technical areas covered in this report include tritium safety, beryllium safety, chemical reactions and activation product release, safety aspects of fusion magnet systems, plasma disruptions, risk assessment failure rate data base development, and thermalhydraulics code development and their application to fusion safety issues. Much of this work has been done in support of the International Thermonuclear Experimental Reactor (ITER). Also included in the report are summaries of the safety and environmental studies performed by the Fusion Safety Program for the Tokamak Physics Experiment and the Tokamak Fusion Test Reactor and of the technical support for commercial fusion facility conceptual design studies. A major activity this year has been work to develop a DOE Technical Standard for the safety of fusion test facilities

  20. USNRC HTGR safety research program overview

    International Nuclear Information System (INIS)

    Foulds, R.B.

    1982-01-01

    An overview is given of current activities and planned research efforts of the US Nuclear Regulatory Commission (NRC) HTGR Safety Program. On-going research at Brookhaven National Laboratory, Oak Ridge National Laboratory, Los Alamos National Laboratory, and Pacific Northwest Laboratory are outlined. Tables include: HTGR Safety Issues, Program Tasks, HTGR Computer Code Library, and Milestones for Long Range Research Plan

  1. ATLAS program for advanced thermal-hydraulic safety research

    International Nuclear Information System (INIS)

    Song, Chul-Hwa; Choi, Ki-Yong; Kang, Kyoung-Ho

    2015-01-01

    Highlights: • Major achievements of the ATLAS program are highlighted in conjunction with both developing advanced light water reactor technologies and enhancing the nuclear safety. • The ATLAS data was shown to be useful for the development and licensing of new reactors and safety analysis codes, and also for nuclear safety enhancement through domestic and international cooperative programs. • A future plan for the ATLAS testing is introduced, covering recently emerging safety issues and some generic thermal-hydraulic concerns. - Abstract: This paper highlights the major achievements of the ATLAS program, which is an integral effect test program for both developing advanced light water reactor technologies and contributing to enhancing nuclear safety. The ATLAS program is closely related with the development of the APR1400 and APR"+ reactors, and the SPACE code, which is a best-estimate system-scale code for a safety analysis of nuclear reactors. The multiple roles of ATLAS testing are emphasized in very close conjunction with the development, licensing, and commercial deployment of these reactors and their safety analysis codes. The role of ATLAS for nuclear safety enhancement is also introduced by taking some examples of its contributions to voluntarily lead to multi-body cooperative programs such as domestic and international standard problems. Finally, a future plan for the utilization of ATLAS testing is introduced, which aims at tackling recently emerging safety issues such as a prolonged station blackout accident and medium-size break LOCA, and some generic thermal-hydraulic concerns as to how to figure out multi-dimensional phenomena and the scaling issue.

  2. Implementation of radiation safety program in a medical institution

    International Nuclear Information System (INIS)

    Palanca, Elena D.

    1999-01-01

    A medical institution that utilizes radiation for the diagnosis and treatment of diseases of malignancies develops and implements a radiation safety program to keep occupational exposures of radiation workers and exposures of non-radiation workers and the public to the achievable and a more achievable minimum, to optimize the use of radiation, and to prevent misadministration. The hospital radiation safety program is established by a core medical radiation committee composed of trained radiation safety officers and head of authorized users of radioactive materials and radiation machines from the different departments. The radiation safety program sets up procedural guidelines of the safe use of radioactive material and of radiation equipment. It offers regular training to radiation workers and radiation safety awareness courses to hospital staff. The program has a comprehensive radiation safety information system or radsis that circularizes the radiation safety program in the hospital. The radsis keeps the drafted and updated records of safety guides and policies, radioactive material and equipment inventory, personnel dosimetry reports, administrative, regulatory and licensing activity document, laboratory procedures, emergency procedures, quality assurance and quality control program process, physics and dosimetry procedures and reports, personnel and hospital staff training program. The medical radiation protection committee is tasked to oversee the actual implementation of the radiation safety guidelines in the different radiation facilities in the hospital, to review personnel exposures, incident reports and ALARA actions, operating procedures, facility inspections and audit reports, to evaluate the existing radiation safety procedures, to make necessary changes to these procedures, and make modifications of course content of the training program. The effective implementation of the radiation safety program provides increased confidence that the physician and

  3. The radiation safety self-assessment program of Ontario Hydro

    International Nuclear Information System (INIS)

    Armitage, G.; Chase, W.J.

    1987-01-01

    Ontario Hydro has developed a self-assessment program to ensure that high quality in its radiation safety program is maintained. The self-assessment program has three major components: routine ongoing assessment, accident/incident investigation, and detailed assessments of particular radiation safety subsystems or of the total radiation safety program. The operation of each of these components is described

  4. Sign up to Safety: developing a safety improvement plan.

    Science.gov (United States)

    Dight, Carol; Peters, Hayley

    2015-04-01

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

  5. Technical Excellence and Communication: The Cornerstones for Successful Safety and Mission Assurance Programs

    Science.gov (United States)

    Malone, Roy W.; Livingston, John M.

    2010-01-01

    The paper describes the role of technical excellence and communication in the development and maintenance of safety and mission assurance programs. The Marshall Space Flight Center (MSFC) Safety and Mission Assurance (S&MA) organization is used to illustrate philosophies and techniques that strengthen safety and mission assurance efforts and that contribute to healthy and effective organizational cultures. The events and conditions leading to the development of the MSFC S&MA organization are reviewed. Historic issues and concerns are identified. The adverse effects of resource limitations and risk assessment roles are discussed. The structure and functions of the core safety, reliability, and quality assurance functions are presented. The current organization s mission and vision commitments serve as the starting points for the description of the current organization. The goals and objectives are presented that address the criticisms of the predecessor organizations. Additional improvements are presented that address the development of technical excellence and the steps taken to improve communication within the Center, with program customers, and with other Agency S&MA organizations.

  6. Technical Excellence and Communication, the Cornerstones for Successful Safety and Mission Assurance Programs

    Science.gov (United States)

    Malone, Roy W.; Livingston, John M.

    2010-09-01

    The paper describes the role of technical excellence and communication in the development and maintenance of safety and mission assurance programs. The Marshall Space Flight Center(MSFC) Safety and Mission Assurance(S&MA) organization is used to illustrate philosophies and techniques that strengthen safety and mission assurance efforts and that contribute to healthy and effective organizational cultures. The events and conditions leading to the development of the MSFC S&MA organization are reviewed. Historic issues and concerns are identified. The adverse effects of resource limitations and risk assessment roles are discussed. The structure and functions of the core safety, reliability, and quality assurance functions are presented. The current organization’s mission and vision commitments serve as the starting points for the description of the current organization. The goals and objectives are presented that address the criticisms of the predecessor organizations. Additional improvements are presented that address the development of technical excellence and the steps taken to improve communication within the Center, with program customers, and with other Agency S&MA organizations.

  7. Improving versus maintaining nuclear safety

    International Nuclear Information System (INIS)

    2002-01-01

    The concept of improving nuclear safety versus maintaining it has been discussed at a number of nuclear regulators meetings in recent years. National reports have indicated that there are philosophical differences between NEA member countries about whether their regulatory approaches require licensees to continuously improve nuclear safety or to continuously maintain it. It has been concluded that, while the actual level of safety achieved in all member countries is probably much the same, this is difficult to prove in a quantitative way. In practice, all regulatory approaches require improvements to be made to correct deficiencies and when otherwise warranted. Based on contributions from members of the NEA Committee on Nuclear Regulatory Activities (CNRA), this publication provides an overview of current nuclear regulatory philosophies and approaches, as well as insights into a selection of public perception issues. This publication's intended audience is primarily nuclear safety regulators, but government authorities, nuclear power plant operators and the general public may also be interested. (author)

  8. Evolution of International Space Station Program Safety Review Processes and Tools

    Science.gov (United States)

    Ratterman, Christian D.; Green, Collin; Guibert, Matt R.; McCracken, Kristle I.; Sang, Anthony C.; Sharpe, Matthew D.; Tollinger, Irene V.

    2013-01-01

    The International Space Station Program at NASA is constantly seeking to improve the processes and systems that support safe space operations. To that end, the ISS Program decided to upgrade their Safety and Hazard data systems with 3 goals: make safety and hazard data more accessible; better support the interconnection of different types of safety data; and increase the efficiency (and compliance) of safety-related processes. These goals are accomplished by moving data into a web-based structured data system that includes strong process support and supports integration with other information systems. Along with the data systems, ISS is evolving its submission requirements and safety process requirements to support the improved model. In contrast to existing operations (where paper processes and electronic file repositories are used for safety data management) the web-based solution provides the program with dramatically faster access to records, the ability to search for and reference specific data within records, reduced workload for hazard updates and approval, and process support including digital signatures and controlled record workflow. In addition, integration with other key data systems provides assistance with assessments of flight readiness, more efficient review and approval of operational controls and better tracking of international safety certifications. This approach will also provide new opportunities to streamline the sharing of data with ISS international partners while maintaining compliance with applicable laws and respecting restrictions on proprietary data. One goal of this paper is to outline the approach taken by the ISS Progrm to determine requirements for the new system and to devise a practical and efficient implementation strategy. From conception through implementation, ISS and NASA partners utilized a user-centered software development approach focused on user research and iterative design methods. The user-centered approach used on

  9. Planned activities to improve safety

    International Nuclear Information System (INIS)

    1998-01-01

    This document presents the fulfilling of the Brazilian obligations under the Convention on Nuclear Safety. The Chapter 6 of the document contains some details about the planed activities to safety improvements

  10. Improving safety on rural local and tribal roads safety toolkit.

    Science.gov (United States)

    2014-08-01

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

  11. Canadian hydrogen safety program

    International Nuclear Information System (INIS)

    MacIntyre, I.; Tchouvelev, A.V.; Hay, D.R.; Wong, J.; Grant, J.; Benard, P.

    2007-01-01

    The Canadian hydrogen safety program (CHSP) is a project initiative of the Codes and Standards Working Group of the Canadian transportation fuel cell alliance (CTFCA) that represents industry, academia, government, and regulators. The Program rationale, structure and contents contribute to acceptance of the products, services and systems of the Canadian Hydrogen Industry into the Canadian hydrogen stakeholder community. It facilitates trade through fair insurance policies and rates, effective and efficient regulatory approval procedures and accommodation of the interests of the general public. The Program integrates a consistent quantitative risk assessment methodology with experimental (destructive and non-destructive) failure rates and consequence-of-release data for key hydrogen components and systems into risk assessment of commercial application scenarios. Its current and past six projects include Intelligent Virtual Hydrogen Filling Station (IVHFS), Hydrogen clearance distances, comparative quantitative risk comparison of hydrogen and compressed natural gas (CNG) refuelling options; computational fluid dynamics (CFD) modeling validation, calibration and enhancement; enhancement of frequency and probability analysis, and Consequence analysis of key component failures of hydrogen systems; and fuel cell oxidant outlet hydrogen sensor project. The Program projects are tightly linked with the content of the International Energy Agency (IEA) Task 19 Hydrogen Safety. (author)

  12. Tenaga Nasional Berhad dam safety and surveillance program

    International Nuclear Information System (INIS)

    Jansen Luis; Zulkhairi Abd Talib

    2006-01-01

    This paper discusses the current practice of dam surveillance, which includes dam monitoring which is a process of visual inspections, measuring, processing, compiling and analyzing dam instrumentation data to determine the performance of a dam. The prime objective of the dam surveillance system is to ensure that any occurrence and development of safety deficiencies and problems are quickly detected, identified, analyzed and the required remedial actions are determined and consequently carried out in due time. In brief, the section is responsible to ensure that the dam monitoring and surveillance works are implemented as per scheduled and in accordance with the requirement and guidelines prepared by the dam designers and in accordance with international commission on large dams, ICOLD. The paper also illustrates and recommends an alternative approach for dam surveillance program using risk management approach, which is currently being actively adopted by some countries like USA, Canada, Australia and etc, towards improving the dam safety management and the decision making process. The approach provides a wider area of opportunity, improvements and benefits particular in the evaluation and modifications to the dam performance and safety. The process provides an effective and efficient tool for the decision makers and engineers through a comprehensive evaluation and a good understanding of the hazards, risks and consequences in relation to dam safety investigations. (Author)

  13. Occupational Safety and Health Programs in Career Education.

    Science.gov (United States)

    DiCarlo, Robert D.; And Others

    This resource guide was developed in response to the Occupational Safety and Health Act of 1970 and is intended to assist teachers in implementing courses in occupational safety and health as part of a career education program. The material is a synthesis of films, programed instruction, slides and narration, case studies, safety pamphlets,…

  14. Sandia Laboratories environment and safety programs

    International Nuclear Information System (INIS)

    Zak, B.D.; McGrath, P.E.; Trauth, C.A. Jr.

    1975-01-01

    Sandia, one of ERDA's largest laboratories, is primarily known for its extensive work in the nuclear weapons field. In recent years, however, Sandia's role has expanded to embrace sizeable programs in the energy, resource recovery, and the environment and safety fields. In this latter area, Sandia has programs which address nuclear, fossil fuel, and general environment and safety issues. Here we survey ongoing activities and describe in more detail aa few projects of particular interest. These range from a study of the impact of sealed disposal of radioactive wastes, through reactor safety and fossil fuel plume chemistry, to investigations of the composition and dynamics of the stratosphere

  15. OSHA Training Programs. Module SH-48. Safety and Health.

    Science.gov (United States)

    Center for Occupational Research and Development, Inc., Waco, TX.

    This student module on OSHA (Occupational Safety and Health Act) training programs is one of 50 modules concerned with job safety and health. This module provides a list of OSHA training requirements and describes OSHA training programs and other safety organizations' programs. Following the introduction, 11 objectives (each keyed to a page in the…

  16. Nuclear Regulatory Systems in Africa: Improving Safety and Security Culture Through Education and Training

    International Nuclear Information System (INIS)

    Kazadi Kabuya, F.

    2016-01-01

    The purpose of this paper is to address the important issue of supporting safety and security culture through an educational and training course program designed both for regulatory staff and licensees. Enhancing the safety and security of nuclear facilities may involve assessing the overall effectiveness of the organization's safety culture. Safety Culture implies steps such as identifying and targeting areas requiring attention, putting emphasis on organizational strengths and weaknesses, human attitudes and behaviours that may positively impact an organization's safety culture, resulting in improving workplace safety and developing and maintaining a high level of awareness within these facilities. Following the terrorist attacks of September 11, 2001, international efforts were made towards achieving such goals. This was realized through meetings, summits and training courses events, with main aim to enhance security at facilities whose activities, if attacked, could impact public health and safety. During regulatory oversight inspections undertaken on some licensee's premises, violations of security requirements were identified. They mostly involved inadequate management oversight of security, lack of a questioning attitude, complacency and mostly inadequate training in both security and safety issues. Using training and education approach as a support to raise awareness on safety and security issues in the framework of improving safety and security culture, a tentative training program in nuclear and radiological safety was started in 2002 with the main aim of vulgarizing the regulatory framework. Real first needs for a training course program were identified among radiographers and radiologists with established working experience but with limited knowledge in radiation safety. In the field of industrial uses of radiation the triggering events for introducing and implementing a training program were: the loss of a radioactive source in a mining

  17. Fusion safety program annual report fiscal year 1997

    International Nuclear Information System (INIS)

    Longhurst, G.R.; Anderl, R.A.; Cadwallader, L.C.

    1998-01-01

    This report summarizes the major activities of the Fusion Safety Program in FY 1997. The Idaho National Engineering and Environmental Laboratory (INEEL) is the designated lead laboratory, and Lockheed Martin Idaho Technologies Company is the prime contractor for this program. The Fusion Safety Program was initiated in FY 1979 to perform research and develop data needed to ensure safety in fusion facilities. Activities include experiments, analysis, code development and application, and other forms of research. These activities are conducted at the INEEL, different DOE laboratories, and other institutions. The technical areas covered in this report include chemical reactions and activation product release, tritium safety, risk assessment failure rate database development, and safety code development and application to fusion safety issues. Most of this work has been done in support of the International Thermonuclear Experimental Reactor (ITER) project. Work done for ITER this year has focused on developing the needed information for the Non-site Specific Safety Report (NSSR-2)

  18. Fusion safety program annual report fiscal year 1997

    Energy Technology Data Exchange (ETDEWEB)

    Longhurst, G.R.; Anderl, R.A.; Cadwallader, L.C. [and others

    1998-01-01

    This report summarizes the major activities of the Fusion Safety Program in FY 1997. The Idaho National Engineering and Environmental Laboratory (INEEL) is the designated lead laboratory, and Lockheed Martin Idaho Technologies Company is the prime contractor for this program. The Fusion Safety Program was initiated in FY 1979 to perform research and develop data needed to ensure safety in fusion facilities. Activities include experiments, analysis, code development and application, and other forms of research. These activities are conducted at the INEEL, different DOE laboratories, and other institutions. The technical areas covered in this report include chemical reactions and activation product release, tritium safety, risk assessment failure rate database development, and safety code development and application to fusion safety issues. Most of this work has been done in support of the International Thermonuclear Experimental Reactor (ITER) project. Work done for ITER this year has focused on developing the needed information for the Non-site Specific Safety Report (NSSR-2).

  19. PROPOSAL OF VOIVODESHIP ROAD SAFETY IMPROVEMENT PROGRAMME

    Directory of Open Access Journals (Sweden)

    Tomasz SZCZURASZEK

    2016-07-01

    Full Text Available The article presents a proposal of the ‘GAMBIT KUJAWSKO-POMORSKI’ Road Safety Improvement Programme. The main idea of the Programme is to establish and initiate systems that will be responsible for the most important areas of activity within road safety, including road safety control, supervision, and management systems in the whole Voivodeship. In total, the creation and start of nine such systems has been proposed, namely: the Road Safety Management, the Integrated Road Rescue Service, the Personnel Continuing Education, the Hazardous Road Behaviour Monitoring, the Social Education for Safe Behaviour on Road, the Teaching Personnel Improvement, the Area Development and Planning Process Improvement, the Road Infrastructure Design Quality Improvement, and the Road and Traffic Management Process Efficiency Improvement. The basic aim of each system has been discussed as well as the most important tasks implemented as its part. The Road Safety Improvement Programme for the Kujawsko-Pomorskie Voivodeship presented in this article is a part of the National Road Safety Programme 2013-2020. Moreover, it is not only an original programme in Poland, but also a universal project that may be adapted for other voivodeships as well.

  20. Operational-safety advantages of LMFBR's: the EBR-II experience and testing program

    International Nuclear Information System (INIS)

    Sackett, J.I.; Lindsay, R.W.; Golden, G.H.

    1982-01-01

    LMFBR's contain many inherent characteristics that simplify control and improve operating safety and reliability. The EBR-II design is such that good advantage was taken of these characteristics, resulting in a vary favorable operating history and allowing for a program of off-normal testing to further demonstrate the safe response of LMFBR's to upsets. The experience already gained, and that expected from the future testing program, will contribute to further development of design and safety criteria for LMFBR's. Inherently safe characteristics are emphasized and include natural convective flow for decay heat removal, minimal need for emergency power and a large negative reactivity feedback coefficient. These characteristics at EBR-II allow for ready application of computer diagnosis and control to demonstrate their effectiveness in response to simulated plant accidents. This latter testing objective is an important part in improvements in the man-machine interface

  1. SafetyAnalyst : software tools for safety management of specific highway sites

    Science.gov (United States)

    2010-07-01

    SafetyAnalyst provides a set of software tools for use by state and local highway agencies for highway safety management. SafetyAnalyst can be used by highway agencies to improve their programming of site-specific highway safety improvements. SafetyA...

  2. Fusion Safety Program Annual Report, Fiscal Year 1996

    International Nuclear Information System (INIS)

    Longhurst, G.R.; Anderl, R.A.; Cadwallader, L.C.

    1996-12-01

    This report summarizes the major activities of the Fusion Safety Program in FY 1996. The Idaho National Engineering Laboratory (INEL) is the designated lead laboratory, and Lockheed Martin Idaho Technologies Company is the prime contractor for this program. The Fusion Safety Program was initiated in 1979. The objective is to perform research and develop data needed to ensure safety in fusion facilities. Activities include experiments, analysis, code development and application, and other forms of research. These activities are conducted at the INEL, at other DOE laboratories, and at other institutions. Among the technical areas covered in this report are tritium safety, chemical reactions and activation product release, risk assessment failure rate database development, and safety code development and application to fusion safety issues. Most of this work has been done in support of the International Thermonuclear Experimental Reactor (ITER). Work done for ITER this year has focused on developing the needed information for the Non- Site- Specific Safety Report (NSSR-1). A final area of activity described is development of the new DOE Technical Standards for Safety of Magnetic Fusion Facilities

  3. 78 FR 43091 - Technical Operations Safety Action Program (T-SAP) and Air Traffic Safety Action Program (ATSAP)

    Science.gov (United States)

    2013-07-19

    ... Administration 14 CFR Part 193 [Docket No.: FAA-2013-0375] Technical Operations Safety Action Program (T-SAP) and... Disclosure. SUMMARY: The FAA is proposing that safety information provided to it under the T-SAP, established... to the FAA under the T-SAP and ATSAP, so the FAA can learn about and address aviation safety hazards...

  4. Fast reactor safety program. Progress report, January-March 1980

    International Nuclear Information System (INIS)

    1980-05-01

    The goal of the DOE LMFBR Safety Program is to provide a technology base fully responsive to safety considerations in the design, evaluation, licensing, and economic optimization of LMFBRs for electrical power generation. A strategy is presented that divides safety technology development into seven program elements, which have been used as the basis for the Work Breakdown Structure (WBS) for the Program. These elements include four lines of assurance (LOAs) involving core-related safety considerations, an element supporting non-core-related plant safety considerations, a safety R and D integration element, and an element for the development of test facilities and equipment to be used in Program experiments: LOA-1 (prevent accidents); LOA-2 (limit core damage); LOA-3 (maintain containment integrity); LOA-4 (attenuate radiological consequences); plant considerations; R and D integration; and facility development

  5. Research program on regulatory safety research

    International Nuclear Information System (INIS)

    Mailaender, R.

    2010-02-01

    This paper elaborated for the Swiss Federal Office of Energy (SFOE) presents the synthesis report for 2009 made by the SFOE's program leader on the research program concerning regulatory nuclear safety research, as co-ordinated by the Swiss Nuclear Safety Inspectorate ENSI. Work carried out in various areas is reviewed, including that done on reactor safety, radiation protection and waste disposal as well as human aspects, organisation and safety culture. Work done concerning materials, pressure vessel integrity, transient analysis, the analysis of serious accidents in light-water reactors, fuel and material behaviour, melt cooling and concrete interaction is presented. OECD data bank topics are discussed. Transport and waste disposal research at the Mont Terri rock laboratory is looked at. Requirements placed on the personnel employed in nuclear power stations are examined and national and international co-operation is reviewed

  6. Mochovce NPP safety improvement and completion

    International Nuclear Information System (INIS)

    1997-01-01

    6th Nuclear society information meeting dealt with the completion of the Mochovce NPP with regard to implementation of safety measures. It was aimed to next problems: I. 'Survey' presentation on the situation of the nuclear power industry in partner countries; II. Basic technical presentations; III. Presentations of operators of the other VVER 440/213 NPPs on their activities in the field of safety improvement in relation to IAEA recommendations; IV. Technical solutions of safety improvements ranked with IAEA degree 3 (Report SC 108 VVER); V: Technical solutions of selected Safety Measures ranked with IAEA degree 2 and 1 (Report SC 108 VVER)

  7. High-heat tank safety issue resolution program plan

    International Nuclear Information System (INIS)

    Wang, O.S.

    1993-12-01

    The purpose of this program plan is to provide a guide for selecting corrective actions that will mitigate and/or remediate the high-heat waste tank safety issue for single-shell tank (SST) 241-C-106. This program plan also outlines the logic for selecting approaches and tasks to mitigate and resolve the high-heat safety issue. The identified safety issue for high-heat tank 241-C-106 involves the potential release of nuclear waste to the environment as the result of heat-induced structural damage to the tank's concrete, if forced cooling is interrupted for extended periods. Currently, forced ventilation with added water to promote thermal conductivity and evaporation cooling is used to cool the waste. At this time, the only viable solution identified to resolve this safety issue is the removal of heat generating waste in the tank. This solution is being aggressively pursued as the permanent solution to this safety issue and also to support the present waste retrieval plan. Tank 241-C-106 has been selected as the first SST for retrieval. The program plan has three parts. The first part establishes program objectives and defines safety issues, drivers, and resolution criteria and strategy. The second part evaluates the high-heat safety issue and its mitigation and remediation methods and alternatives according to resolution logic. The third part identifies major tasks and alternatives for mitigation and resolution of the safety issue. Selected tasks and best-estimate schedules are also summarized in the program plan

  8. [Evaluation of a grant program for improving health and safety in small and medium companies in Andalusia (Spain)].

    Science.gov (United States)

    Carrillo Castrillo, Jesús Antonio; Onieva Giménez, Luis; Ruiz Frutos, Carlos

    2012-01-01

    To evaluate a grant program for the development and support of occupational safety projects in small and medium companies (SMC) in Andalusia. The analysis includes data and results of the program between 2006 and 2008. We analyzed the program characteristics in terms of budget, proposals submitted and projects financed. The views of participating companies regarding the program were evaluated through a voluntary and anonymous postal survey. Occupational injury rates in 2006 and 2007 in a subgroup of companies that had obtained a grant in 2006 were calculated. Public investment in the program (> 17 million euros) covered 44% of the investment in occupational health projects proposed by participating companies. Nearly 50% of the projects presented received grant funding. The survey was completed by 573 companies (24% of the submitted questionnaires). Among grantee companies, 89% considered the investment to have been effective and 87% considered that working conditions in the company had improved. Most of the companies (>90%) considered that lack of economic resources is an obstacle for prevention activities and that these kinds of public subsidies are necessary. Occupational injury rates decreased between 2006 and 2007 (incidence rate 0.93; 95%confidence interval, 0.78-1.11). The grant program was viewed positively by participating companies and was accompanied by a reduction of occupational injury rates among grantee companies. These programs should incorporate evaluation criteria and indicators in their design. Copyright belongs to the Societat Catalana de Seguretat i Medicina del Treball.

  9. Teaching children about bicycle safety: an evaluation of the New Jersey Bike School program.

    Science.gov (United States)

    Lachapelle, Ugo; Noland, Robert B; Von Hagen, Leigh Ann

    2013-03-01

    There are multiple health and environmental benefits associated with increasing bicycling among children. However, the use of bicycles is also associated with severe injuries and fatalities. In order to reduce bicycle crashes, a bicycling education program was implemented in selected New Jersey schools and summer camps as part of the New Jersey Safe Routes to School Program. Using a convenience sample of participants to the program, an opportunistic study was designed to evaluate the effectiveness of two bicycle education programs, the first a more-structured program delivered in a school setting, with no on-road component, and the other a less structured program delivered in a summer camp setting that included an on-road component. Tests administered before and after training were designed to assess knowledge acquired during the training. Questions assessed children's existing knowledge of helmet use and other equipment, bicycle safety, as well as their ability to discriminate hazards and understand rules of the road. Participating children (n=699) also completed a travel survey that assessed their bicycling behavior and their perception of safety issues. Response to individual questions, overall pre- and post-training test scores, and changes in test scores were compared using comparison of proportion, t-tests, and ordinary least-squares (OLS) regression. Improvements between the pre-training and post-training test are apparent from the frequency distribution of test results and from t-tests. Both summer camps and school-based programs recorded similar improvements in test results. Children who bicycled with their parents scored higher on the pre-training test but did not improve as much on the post-training test. Without evaluating long-term changes in behavior, it is difficult to ascertain how successful the program is on eventual behavioral and safety outcomes. Copyright © 2012 Elsevier Ltd. All rights reserved.

  10. IRSN research programs concerning reactor safety

    International Nuclear Information System (INIS)

    Bardelay, J.

    2005-01-01

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

  11. Nuclear criticality safety program at the Fuel Cycle Facility

    International Nuclear Information System (INIS)

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

    1994-01-01

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

  12. Summary of NRC LWR safety research programs on fuel behavior, metallurgy/materials and operational safety

    International Nuclear Information System (INIS)

    Bennett, G.L.

    1979-09-01

    The NRC light-water reactor safety-research program is part of the NRC regulatory program for ensuring the safety of nuclear power plants. This paper summarizes the results of NRC-sponsored research into fuel behavior, metallurgy and materials, and operational safety. The fuel behavior research program provides a detailed understanding of the response of nuclear fuel assemblies to postulated off-normal or accident conditions. Fuel behavior research includes studies of basic fuel rod properties, in-reactor tests, computer code development, fission product release and fuel meltdown. The metallurgy and materials research program provides independent confirmation of the safe design of reactor vessels and piping. This program includes studies on fracture mechanics, irradiation embrittlement, stress corrosion, crack growth, and nondestructive examination. The operational safety research provides direct assistance to NRC officials concerned with the operational and operational-safety aspects of nuclear power plants. The topics currently being addressed include qualification testing evaluation, fire protection, human factors, and noise diagnostics

  13. Design and evaluation of simulation scenarios for a program introducing patient safety, teamwork, safety leadership, and simulation to healthcare leaders and managers.

    Science.gov (United States)

    Cooper, Jeffrey B; Singer, Sara J; Hayes, Jennifer; Sales, Michael; Vogt, Jay W; Raemer, Daniel; Meyer, Gregg S

    2011-08-01

    We developed a training program to introduce managers and informal leaders of healthcare organizations to key concepts of teamwork, safety leadership, and simulation to motivate them to act as leaders to improve safety within their sphere of influence. This report describes the simulation scenario and debriefing that are core elements of that program. Twelve teams of clinician and nonclinician managers were selected from a larger set of volunteers to participate in a 1-day, multielement training program. Two simulation exercises were developed: one for teams of nonclinicians and the other for clinicians or mixed groups. The scenarios represented two different clinical situations, each designed to engage participants in discussions of their safety leadership and teamwork issues immediately after the experience. In the scenarios for nonclinicians, participants conducted an anesthetic induction and then managed an ethical situation. The scenario for clinicians simulated a consulting visit to an emergency room that evolved into a problem-solving challenge. Participants in this scenario had a limited time to prepare advice for hospital leadership on how to improve observed safety and cultural deficiencies. Debriefings after both types of scenarios were conducted using principles of "debriefing with good judgment." We assessed the relevance and impact of the program by analyzing participant reactions to the simulation through transcript data and facilitator observations as well as a postcourse questionnaire. The teams generally reported positive perceptions of the relevance and quality of the simulation with varying types and degrees of impact on their leadership and teamwork behaviors. These kinds of clinical simulation exercises can be used to teach healthcare leaders and managers safety leadership and teamwork skills and behaviors.

  14. Variable Speed Limits: Strategies to Improve Safety and Traffic Parameters for a Bottleneck

    Directory of Open Access Journals (Sweden)

    M. Z. Hasanpour

    2017-04-01

    Full Text Available The primary purpose of the speed limit system is to enforce reasonable and safe speed. To reduce secondary problems such as accidents and queuing, Variable Speed Limits (VSL has been suggested. In this paper VSL is used to better safety and traffic parameters. Traffic parameters including speed, queue length and stopping time have been pondering. For VLS, an optimization decision tree algorithm with the function of microscopic simulation was used. The results in case of sub saturated, saturated and supersaturated at a bottleneck are examined and compared with the Allaby logic tree. The results show that the proposed decision tree shows an improved performance in terms of safety and comfort along the highway. The VSL pilot project is part of the Road Safety Improvement Program included in Iran’s road safety action plan that is in the research process in the BHRC Research Institute, Road and Housing & Urban Development Research that is planned for next 10-year Transportation safety view Plan.

  15. [Evaluating training programs on occupational health and safety: questionnaire development].

    Science.gov (United States)

    Zhou, Xiao-Yan; Wang, Zhi-Ming; Wang, Mian-Zhen

    2006-03-01

    To develop a questionnaire to evaluate the quality of training programs on occupational health and safety. A questionnaire comprising five subscales and 21 items was developed. The reliability and validity of the questionnaire was tested. Final validation of the questionnaire was undertaken in 700 workers in an oil refining company. The Cronbach's alpha coefficients of the five subscales ranged from 0.6194 to 0.6611. The subscale-scale Pearson correlation coefficients ranged from 0.568 to 0.834 . The theta coefficients of the five subscales were greater than 0.7. The factor loadings of the five subscales in the principal component analysis ranged from 0.731 to 0.855. Use of the questionnaire in the 700 workers produced a good discriminability, with excellent, good, fair and poor comprising 22.2%, 31.2%, 32.4% and 14.1 respectively. Given the fact that 18.7% of workers had never been trained and 29.7% of workers got one-off training only, the training program scored an average of 57.2. The questionnaire is suitable to be used in evaluating the quality of training programs on occupational health and safety. The oil refining company needs to improve training for their workers on occupational health and safety.

  16. AEC sets five year nuclear safety research program

    International Nuclear Information System (INIS)

    Anon.

    1976-01-01

    The research by the government for the establishment of means of judging the adequacy of safety measures incorporated in nuclear facilities, including setting safety standards and collecting documents of general criteria, and the research by the industry on safety measures and the promotion of safety-related technique are stated in the five year program for 1976-80 reported by subcommittees, Atomic Energy Commission (AEC). Four considerations on the research items incorporated in the program are 1) technical programs relating to the safety of nuclear facilities and the necessary criteria, 2) priority of the relevant items decided according to their impact on circumstances, urgency, the defence-indepth concept and so on, 3) consideration of all relevant data and documents collected, and research subjects necessary to quantify safety measurement, and 4) consideration of technological actualization, the capability of each research body, the budget and the time schedule. In addition, seven major themes decided on the basis of these points are 1) reactivity-initiated accident, 2) LOCA, 3) fuel behavior, 4) structural safety, 5) radioactive release, 6) statistical method of safety evaluation, and 7) seismic characteristics. The committee has deliberated the appropriate division of researches between the government and the industry. A set of tables showing the nuclear safety research plan for 1976-80 are attached. (Iwakiri, K.)

  17. The program of continuous improvements in factory in Juzbado

    International Nuclear Information System (INIS)

    Prieto, M.

    2015-01-01

    This articles describes the historical development of the continuous improvement program at Juzbado Factory, since its beginning to nowadays. The evolution throughout the ideas of Total Quality, ISO, EFQM, Six Sigma, and so on, leading to the present situation in which all these tools and methodologies live together is shown. all this has led to a philosophy and business culture focused on safety, quality and continuous improvement. (Author)

  18. Developing and establishing the validity and reliability of the perceptions toward Aviation Safety Action Program (ASAP) and Line Operations Safety Audit (LOSA) questionnaires

    Science.gov (United States)

    Steckel, Richard J.

    Aviation Safety Action Program (ASAP) and Line Operations Safety Audits (LOSA) are voluntary safety reporting programs developed by the Federal Aviation Administration (FAA) to assist air carriers in discovering and fixing threats, errors and undesired aircraft states during normal flights that could result in a serious or fatal accident. These programs depend on voluntary participation of and reporting by air carrier pilots to be successful. The purpose of the study was to develop and validate a measurement scale to measure U.S. air carrier pilots' perceived benefits and/or barriers to participating in ASAP and LOSA programs. Data from these surveys could be used to make changes to or correct pilot misperceptions of these programs to improve participation and the flow of data. ASAP and LOSA a priori models were developed based on previous research in aviation and healthcare. Sixty thousand ASAP and LOSA paper surveys were sent to 60,000 current U.S. air carrier pilots selected at random from an FAA database of pilot certificates. Two thousand usable ASAP and 1,970 usable LOSA surveys were returned and analyzed using Confirmatory Factor Analysis. Analysis of the data using confirmatory actor analysis and model generation resulted in a five factor ASAP model (Ease of use, Value, Improve, Trust and Risk) and a five factor LOSA model (Value, Improve, Program Trust, Risk and Management Trust). ASAP and LOSA data were not normally distributed, so bootstrapping was used. While both final models exhibited acceptable fit with approximate fit indices, the exact fit hypothesis and the Bollen-Stine p value indicated possible model mis-specification for both ASAP and LOSA models.

  19. Outage Risk Assessment and Management (ORAM) technology to improve outage safety and economics

    International Nuclear Information System (INIS)

    Kalra, S.P.

    2004-01-01

    The Electric Power Research Institute (EPRI) has undertaken an aggressive program, called ORAM (Outage Risk Assessment and Management), to provide utilities with tools and technology to assist in managing risk during the planning and conduct of outages. The ORAM program consists of the following 6 steps: i) Perform utility surveys and visits on shutdown risk management needs, ii) Perform probabilistic shutdown safety assessments (PSSAs) to identify generic insights that can be incorporated into risk management guidelines and identify selected areas for the development of contingency actions, iii) Develop risk management guidelines (RMG's) that provide a systematic approach to the planning and conduct of outages from a safety perspective. Incorporate insights from the shutdown safety assessments and other operating experience into the RMG's. iv) Develop selected contingency actions including a thermalhydraulic tool kit to address higher risk time periods and activities identified in the shutdown safety assessments, v) Develop computer software that integrates all of the above capability into an easy to use tool for effective shutdown operation management for utilities, vi) Provide assistance in the transfer of this technology and the application of these tools. This paper briefly describes the technical approach and tools developed under EPRI's ORAM program and its applications for improving outage safety and economics. (author)

  20. Nature-Based Strategies for Improving Urban Health and Safety.

    Science.gov (United States)

    Kondo, Michelle C; South, Eugenia C; Branas, Charles C

    2015-10-01

    Place-based programs are being noticed as key opportunities to prevent disease and promote public health and safety for populations at-large. As one key type of place-based intervention, nature-based and green space strategies can play an especially large role in improving health and safety for dwellers in urban environments such as US legacy cities that lack nature and greenery. In this paper, we describe the current understanding of place-based influences on public health and safety. We focus on nonchemical environmental factors, many of which are related to urban abandonment and blight. We then review findings from studies of nature-based interventions regarding impacts on health, perceptions of safety, and crime. Based on our findings, we suggest that further research in this area will require (1) refined measures of green space, nature, and health and safety for cities, (2) interdisciplinary science and cross-sector policy collaboration, (3) observational studies as well as randomized controlled experiments and natural experiments using appropriate spatial counterfactuals and mixed methods, and (4) return-on-investment calculations of potential economic, social, and health costs and benefits of urban greening initiatives.

  1. Directory of Academic Programs in Occupational Safety and Health.

    Science.gov (United States)

    Weis, William J., III; And Others

    This booklet describes academic program offerings in American colleges and universities in the area of occupational safety and health. Programs are divided into five major categories, corresponding to each of the core disciplines: (1) occupational safety and health/industrial hygiene, (2) occupational safety, (3) industrial hygiene, (4)…

  2. OPG waterways public safety program

    Energy Technology Data Exchange (ETDEWEB)

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

    2009-07-01

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

  3. Leadership, safety climate, and continuous quality improvement: impact on process quality and patient safety.

    Science.gov (United States)

    McFadden, Kathleen L; Stock, Gregory N; Gowen, Charles R

    2014-10-01

    Successful amelioration of medical errors represents a significant problem in the health care industry. There is a need for greater understanding of the factors that lead to improved process quality and patient safety outcomes in hospitals. We present a research model that shows how transformational leadership, safety climate, and continuous quality improvement (CQI) initiatives are related to objective quality and patient safety outcome measures. The proposed framework is tested using structural equation modeling, based on data collected for 204 hospitals, and supplemented with objective outcome data from the Centers for Medicare and Medicaid Services. The results provide empirical evidence that a safety climate, which is connected to the chief executive officer's transformational leadership style, is related to CQI initiatives, which are linked to improved process quality. A unique finding of this study is that, although CQI initiatives are positively associated with improved process quality, they are also associated with higher hospital-acquired condition rates, a measure of patient safety. Likewise, safety climate is directly related to improved patient safety outcomes. The notion that patient safety climate and CQI initiatives are not interchangeable or universally beneficial is an important contribution to the literature. The results confirm the importance of using CQI to effectively enhance process quality in hospitals, and patient safety climate to improve patient safety outcomes. The overall pattern of findings suggests that simultaneous implementation of CQI initiatives and patient safety climate produces greater combined benefits.

  4. Methods for safety culture improvement

    International Nuclear Information System (INIS)

    Sivintsev, Yu.V.

    1998-01-01

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

  5. Effectiveness of a quality-improvement program in improving management of primary care practices

    Science.gov (United States)

    Szecsenyi, Joachim; Campbell, Stephen; Broge, Bjoern; Laux, Gunter; Willms, Sara; Wensing, Michel; Goetz, Katja

    2011-01-01

    Background: The European Practice Assessment program provides feedback and outreach visits to primary care practices to facilitate quality improvement in five domains (infrastructure, people, information, finance, and quality and safety). We examined the effectiveness of this program in improving management in primary care practices in Germany, with a focus on the domain of quality and safety. Methods: In a before–after study, 102 primary care practices completed a practice assessment using the European Practice Assessment instrument at baseline and three years later (intervention group). A comparative group of 102 practices was included that completed their first assessment using this instrument at the time of the intervention group’s second assessment. Mean scores were based on the proportion of indicators for which a positive response was achieved by all of the practices, on a scale of 0 to 100. Results: We found significant improvements in all domains between the first and second assessments in the intervention group. In the domain of quality and safety, improvements in scores (mean scores were based on the proportion of indicators for which a positive response was achieved by all of the practices, on a scale of 0 to 100) were observed in the following dimensions: complaint management (from a mean score of 51.2 at first assessment to 80.7 at second assessment); analysis of critical incidents (from 79.1 to 89.6); and quality development, quality policy (from 40.7 to 55.6). Overall scores at the time of the second assessment were significantly higher in the intervention group than in the comparative group. Interpretation: Primary care practices that completed the European Practice Assessment instrument twice over a three-year period showed improvements in practice management. Our findings show the value of the quality-improvement cycle in the context of practice assessment and the use of established organizational standards for practice management with the

  6. Fusion Safety Program annual report, fiscal year 1992

    International Nuclear Information System (INIS)

    Holland, D.F.; Cadwallader, L.C.; Herring, J.S.; Longhurst, G.R.; McCarthy, K.A.; Merrill, B.J.; Piet, S.J.

    1993-01-01

    This report summarizes the major activities of the Fusion Safety Program in fiscal year 1992. The Idaho National Engineering Laboratory (INEL) is the designated lead laboratory and EG ampersand G Idaho, Inc. is the prime contractor for this program. The Fusion Safety Program was initiated in 1979. Activities are conducted at the INEL and in participating organizations including the Westinghouse Hanford Company at the Hanford Engineering Development Laboratory, the Massachusetts Institute of Technology, and the University of Wisconsin. The technical areas covered in the report include tritium safety, activation product release, reactions involving beryllium, reactions involving lithium breeding materials, safety of fusion magnet systems, plasma disruptions, risk assessment failure rate data base, and computer code development for reactor transients. Also included in the report is a summary of the safety and environmental studies performed by the INEL for the Tokamak Physics Experiments and the Tokamak Fusion Test Reactor, the safety analysis for the International Thermonuclear Experimental Reactor design, and the technical support for the ARIES commercial reactor design study

  7. Improving patient safety: lessons from rock climbing.

    Science.gov (United States)

    Robertson, Nic

    2012-02-01

    How to improve patient safety remains an intractable problem, despite large investment and some successes. Academics have argued that the root of the problem is a lack of a comprehensive 'safety culture' in hospitals. Other safety-critical industries such as commercial aviation invest heavily in staff training to develop such a culture, but comparable programmes are almost entirely absent from the health care sector. In rock climbing and many other dangerous activities, the 'buddy system' is used to ensure that safety systems are adhered to despite adverse circumstances. This system involves two or more people using simple checks and clear communication to prevent problems causing harm. Using this system as an example could provide a simple, original and entertaining way of introducing medical students to the idea that human factors are central to ensuring patient safety. Teaching the buddy system may improve understanding and acceptance of other patient safety initiatives, and could also be used by junior doctors as a tool to improve the safety of their practice. © Blackwell Publishing Ltd 2012.

  8. Safety improvement of Paks nuclear power plant

    International Nuclear Information System (INIS)

    Vamos, G.

    1999-01-01

    Safety upgrading completed in the early nineties at the Paks NPP include: replacement of steam generator safety valves and control valves; reliability improvement of the electrical supply system; modification of protection logic; enhancement of the fire protection; construction of full scope Training Simulator. Design safety upgrading measures achieved in recent years were concerned with: relocation of steam generator emergency feed-water supply; emergency gas removal from the primary coolant system; hydrogen management in the containment; protection against sumps; preventing of emergency core cooling system tanks from refilling. Increasing seismic resistance, containment assessment, refurbishment of reactor protection system, improving reliability of emergency electrical supply, analysis of internal hazards are now being implemented. Safety upgrading measures which are being prepared include: bleed and feed procedures; reactor over-pressurisation protection in cold state; treatment of steam generator primary to secondary leak accidents. Operational safety improvements are dealing with safety culture, training measures and facilities; symptom based emergency operating procedures; in-service inspection; fire protection. The significance of international cooperation is emphasised in view of achieving nuclear safety standards recognised in EU

  9. 49 CFR 659.19 - System safety program plan: contents.

    Science.gov (United States)

    2010-10-01

    ... implementation of the system safety program. (j) A description of the process used by the rail transit agency to... the rail transit agency to manage safety issues. (d) The process used to control changes to the system... hazard management program. (n) A description of the process used for facilities and equipment safety...

  10. Improvement of the safety level of installations with the generalization of procedures

    International Nuclear Information System (INIS)

    Cornille, Y.; Dupraz, B.; Schektman, N.

    1986-06-01

    The generalization of control procedures to the largest possible spectra of accidental situations which is being developed on pressurized water reactor units will allow to increase the safety level of these installations. This improvement has been quantified for some situations pointing out an appreciable mitigation of meltdown risk which could result. A new improvement is aimed with the definition and the utilization of new procedures ''by states'' which will allow an optimized treatment of situations resulting from multiple failures, now treated in the procedures SPI - SPU - U1. The needs related to these procedures and their development led to joint research and development programs between Electricite de France and the Institute of Protection and Nuclear Safety [fr

  11. Evaluation of implementation an Integrated Safety and Preventive Maintenance System for Improving of Safety Indexes

    Directory of Open Access Journals (Sweden)

    I mohammadfam

    2014-03-01

    Full Text Available Accident analysis shows that one of the main reasons for accidents is non-integration of maintenance units with safety. Merging these two processes through an integrated system can reduce and or eliminate accidents, diseases, and environmental pollution. These issues lead to improvement in organizational performance, as well. The aim of this study is to design and establish an integrated system for obtaining the aforementioned goal. Integration was carried out at Nirou Moharreke Machine Tools Company via Structured System Analysis & Design Method (SSADM. In order to measure the effectiveness of the system, selected indexes were compared using statistical methods prior and after system establishment. Results show that the accident severity index reduced from 135.46 in 2010, to 43.85 in 2012. Moreover, system effectiveness improved equipment reliability and availability (e.g. reliability of the Pfeiffer Milling machine (P (t>50 increased from 0.89 in 2010, to 0.9 in 2012. This system by forecasting various failures, and planning and designing the required operations for preventing occurrence of these failures, plays an important role in improving safety conditions of equipment, and increasing organizational performance, and is capable of presenting an excellent accident prevention program.

  12. EC6 safety design improvements

    Energy Technology Data Exchange (ETDEWEB)

    Yu, S.; Lee, A.G.; Soulard, M. [Candu Energy Inc., Mississauga, ON (Canada)

    2014-07-01

    The Enhanced CANDU 6 (EC6) builds on the proven high performance design such as the Qinshan CANDU 6 reactor, and has made improvements to safety, operational performance, and has incorporated extensive operational feedback. Completion of all three phases of the pre-licensing design review by the Canadian Regulator - the Canadian Nuclear Safety Commission has provided a higher level of assurance that the EC6 reference design has taken modern regulatory requirements and expectations into account and further confirmed that there are no fundamental barriers to licensing the EC6 design in Canada. The EC6 design is based on the defence-in-depth principles in INSAG-10 and provides further safety features that address the lessons learned from Fukushima. With these safety features, the EC6 design has strengthened accident prevention as the first priority in the defence-in-depth strategy, as outlined in INSAG-10. As well, the EC6 design has incorporated further mitigation measures to provide additional protection of the public and the environment if the preventive measures fail. The EC6 design has an appropriate combination of inherent, passive safety characteristics, engineered features and administrative safety measures to effectively prevent and mitigate severe accident progressions. A strong contributor to the robustness and redundancy of CANDU design is the two-group separation philosophy. This ensures a high degree of independence between safety systems as well as physical separation and functional independence in how fundamental safety functions are provided. This paper will describe the following safety features based on the application of defence-in-depth and design approach to prevent beyond design basis events progressing to severe accidents and to mitigate the consequences if it occurs: Improved steam generator heat sink via a more reliable emergency heat removal system; Increased time before manual field actions are required via enhanced capacity of

  13. 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

  14. India's power program and its concern over environmental safety

    International Nuclear Information System (INIS)

    Prasad, G.E.; Mittra, J.

    2001-01-01

    India's need of electrical power is enormous and per capita consumption of power is to be increased at least by ten times to reach the level of world average. Thermal Power generation faces two fold problems. First, there is scarcity of good quality fuel and second, increasing environmental pollution. India's self reliant, three stage, 'closed-fuel-cycle' nuclear power program is promising better solution to the above problems. To ensure Radiation Protection and Safety of Radiation Sources, Indian Nuclear Power program emphasizes upon design and engineering safety by incorporating necessary safety features in the design, operational safety through structured training program and typically through software packages to handle rare unsafe events and regulation by complying safety directives. A health survey among the radiation workers indicates that there is no extra threat to the public from nuclear power program. Based on latest technology, as available in case of nuclear power option, it is quite possible to meet high energy requirement with least impact on the environment.. (authors)

  15. Stakeholder evaluation of an online program to promote physical activity and workplace safety for individuals with disability.

    Science.gov (United States)

    Nery-Hurwit, Mara; Kincl, Laurel; Driver, Simon; Heller, Brittany

    2017-08-01

    Individuals with disabilities face increasing health and employment disparities, including increased risk of morbidity and mortality and decreased earnings, occupational roles, and greater risk of injury at work. Thus, there is a need to improve workplace safety and health promotion efforts for people with disability. The purpose of this study was to obtain stakeholder feedback about an online program, Be Active, Work Safe, which was developed to increase the physical activity and workplace safety practices of individuals with disability. Eight stakeholders (content experts and individuals with disability) evaluated the 8-week online program and provided feedback on accessibility, usability, and content using quantitative and qualitative approaches. Stakeholders suggested changes to the organization, layout and accessibility, and content. This included making a stronger connection between the physical activity and workplace safety components of the program, broadening content to apply to individuals in different vocational fields, and reducing the number of participant assessments. Engaging stakeholders in the development of health promotion programs is critical to ensure the unique issues of the population are addressed and facilitate engagement in the program. Feedback provided by stakeholders improved the program and provided insight on barriers for adoption of the program. Copyright © 2017 Elsevier Ltd. All rights reserved.

  16. Increase plant safety and reduce cost by implementing risk-informed in-service inspection programs

    International Nuclear Information System (INIS)

    Billington, A.; Monette, P.

    2001-01-01

    The idea behind the program is that it is possible to 'inspect less, but inspect better'. In other words, the risk-informed In-Service Inspection (ISI) process is used to improve the effectiveness of examination of piping components, i.e. concentrate inspection resources and enhance inspection strategies on high safety significant locations, and reduce inspection requirements on others. The Westinghouse Owners Group (WOG) risk-informed ISI process has already been applied for full scope (Millstone 3, Surry 1) and limited scope (Beznau, Ringhals 4, Asco, Turkey Point 3). By examining the high safety significant piping segments for the different fluid piping systems, the total piping core damage frequency is reduced. In addition, more than 80% of the risk associated with potential pressure boundary failures is addressed with the WOG risk-informed ISI process, while typically less that 50% of this same risk is addressed by the current inspection programs. The risk-informed ISI processes are used to improve the effectiveness of inspecting safety-significant piping components, to reduce inspection requirements on other piping components, to evaluate improvements to plant availability and enhanced safety measures, including reduction of personnel radiation exposure, and to reduce overall Operation and Maintenance (O and M) costs while maintaining regulatory compliance. A description of the process as well as benefits from past projects is presented, since the methodology is applicable for WWER plant design. (author)

  17. Increase plant safety and reduce cost by implementing risk-informed In-Service Inspection programs

    International Nuclear Information System (INIS)

    Billington, A.; Monette, P.; Doumont, C.

    2000-01-01

    The idea behind the program is that it is possible to 'inspect less, but inspect better'. In other words, the risk-informed In-Service Inspection (ISI) process is used to improve the effectiveness of examination of piping components, i.e. concentrate inspection resources and enhance inspection strategies on high safety significant locations, and reduce inspection requirements on others. The Westinghouse Owners Group (WOG) risk-informed ISI process has already been applied for full scope (Millstone 3, Surry 1) and limited scope (Beznau, Ringhals 4, Asco, Turkey Point 3). By examining the high safety significant piping segments for the different fluid piping systems, the total piping core damage frequency is reduced. In addition, more than 80% of the risk associated with potential pressure boundary failures is addressed with the WOG risk-informed ISI process, while typically less than 50% of this same risk is addressed by the current inspection programs. The risk-informed ISI processes are used: to improve the effectiveness of inspecting safety-significant piping components; to reduce inspection requirements on other piping components; to evaluate improvements to plant availability and enhanced safety measures, including reduction of personnel radiation exposure; and to reduce overall Operation and Maintenance (O and M) costs while maintaining regulatory compliance. A description of the process as well as benefits of past projects is presented, since the methodology is applicable for VVER plant design. (author)

  18. Japan's international cooperation programs on seismic safety of nuclear power plants

    International Nuclear Information System (INIS)

    Sanada, Akira

    1997-01-01

    MITI is promoting many international cooperation programs on nuclear safety area. The seismic safety of nuclear power plants (NPPs) is a one of most important cooperation areas. Experts from MITI and related organization join the multilateral cooperation programs carried out by international organization such as IAEA, OECD/NEA etc. MITI is also promoting bilateral cooperation programs such as information exchange meetings, training programs and seminars on nuclear safety with several countries. Concerning to the cooperation programs on seismic safety of NPPs such as information exchange and training, MITI shall continue and expand these programs. (J.P.N.)

  19. Safety Test Program Summary SNAP 19 Pioneer Heat Source Safety Program

    Energy Technology Data Exchange (ETDEWEB)

    None,

    1971-07-01

    Sixteen heat source assemblies have been tested in support of the SNAP 19 Pioneer Safety Test Program. Seven were subjected to simulated reentry heating in various plasma arc facilities followed by impact on earth or granite. Six assemblies were tested under abort accident conditions of overpressure, shrapnel impact, and solid and liquid propellant fires. Three capsules were hot impacted under Transit capsule impact conditions to verify comparability of test results between the two similar capsule designs, thus utilizing both Pioneer and Transit Safety Test results to support the Safety Analysis Report for Pioneer. The tests have shown the fuel is contained under all nominal accident environments with the exception of minor capsule cracks under severe impact and solid fire environments. No catastrophic capsule failures occurred in this test which would release large quantities of fuel. In no test was fuel visible to the eye following impact or fire. Breached capsules were defined as those which exhibit thoria contamination on its surface following a test, or one which exhibited visible cracks in the post test metallographic analyses.

  20. Effectiveness and safety of wheelchair skills training program in improving the wheelchair skills capacity: a systematic review.

    Science.gov (United States)

    Tu, Chun-Jing; Liu, Lin; Wang, Wei; Du, He-Ping; Wang, Yu-Ming; Xu, Yan-Bing; Li, Ping

    2017-12-01

    To comprehensively assess the effectiveness and safety of wheelchair skills training program in improving wheelchair skills capacity. PubMed, OVID, EBSCO, ScienceDirect, Web of Science, CINAHL, Cochrane Library, Google Scholar, and China Knowledge Resource Integrated Database were searched up to March 2017. Controlled clinical trials that compared a wheelchair skills training program with a control group that received other interventions and used the wheelchair skills test scores to evaluate wheelchair skills capacity were included. Two authors independently screened articles, extracted data, and assessed the methodological quality using the Cochrane risk-of-bias tool in randomized controlled trial (RCT) and methodological index for non-randomized studies. The data results of wheelchair skills test scores were extracted. Data from 455 individuals in 10 RCTs and from 140 participants in seven non-randomized studies were included for meta-analysis using Stata version 12.0 (Stata Corporation, College Station, TX, USA). In the short term (immediately to one week) post-intervention, relative to a control group, manual wheelchair skills training could increase the total wheelchair skills test scores by 13.26% in RCTs (95% confidence interval (CI), 6.19%-20.34%; P skills training and the long-term (3-12 months) advantage of manual wheelchair skills training ( P = 0.755). The limited evidence suggests that wheelchair skills training program is beneficial in the short term, but its long-term effects remain unclear.

  1. Integrated safety assessment report, Haddam Neck Plant (Docket No. 50-213): Integrated Safety Assessment Program: Draft report

    International Nuclear Information System (INIS)

    1987-07-01

    The integrated assessment is conducted on a plant-specific basis to evaluate all licensing actions, licensee initiated plant improvements and selected unresolved generic/safety issues to establish implementation schedules for each item. Procedures allow for a periodic updating of the schedules to account for licensing issues that arise in the future. The Haddam Neck Plant is one of two plants being reviewed under the pilot program. This report indicates how 82 topics selected for review were addressed, and presents the staff's recommendations regarding the corrective actions to resolve the 82 topics and other actions to enhance plant safety. 135 refs., 4 figs., 5 tabs

  2. Improving resident engagement in quality improvement and patient safety initiatives at the bedside: the Advocate for Clinical Education (ACE).

    Science.gov (United States)

    Schleyer, Anneliese M; Best, Jennifer A; McIntyre, Lisa K; Ehrmantraut, Ross; Calver, Patty; Goss, J Richard

    2013-01-01

    Quality improvement (QI) and patient safety (PS) are essential competencies in residency training; however, the most effective means to engage physicians remains unclear. The authors surveyed all medicine and surgery physicians at their institution to describe QI/PS practices and concurrently implemented the Advocate for Clinical Education (ACE) program to determine if a physician-centered program in the context of educational structures and at the point of care improved performance. The ACE rounded with medicine and surgery teams and provided individual and team-level education and feedback targeting 4 domains: professionalism, infection control, interpreter use, and pain assessment. In a pilot, the ACE observed 2862 physician-patient interactions and 178 physicians. Self-reported compliance often was greater than the behaviors observed. Following ACE implementation, observed professionalism behaviors trended toward improvement; infection control also improved. Physicians were highly satisfied with the program. The ACE initiative is one coaching/feedback model for engaging residents in QI/PS that may warrant further study.

  3. Implementation of an Enhanced Measurement Control Program for handling nuclear safety samples at WSRC

    International Nuclear Information System (INIS)

    Boler-Melton, C.; Holland, M.K.

    1991-01-01

    In the separation and purification of nuclear material, nuclear criticality safety (NCS) is of primary concern. The primary nuclear criticality safety controls utilized by the Savannah River Site (SRS) Separations Facilities involve administrative and process equipment controls. Additional assurance of NCS is obtained by identifying key process hold points where sampling is used to independently verify the effectiveness of production control. Nuclear safety measurements of samples from these key process locations provide a high degree of assurance that processing conditions are within administrative and procedural nuclear safety controls. An enhanced procedure management system aimed at making improvements in the quality, safety, and conduct of operation was implemented for Nuclear Safety Sample (NSS) receipt, analysis, and reporting. All procedures with nuclear safety implications were reviewed for accuracy and adequate detail to perform the analytical measurements safely, efficiently, and with the utmost quality. Laboratory personnel worked in a ''Deliberate Operating'' mode (a systematic process requiring continuous expert oversight during all phases of training, testing, and implementation) to initiate the upgrades. Thus, the effort to revise and review nuclear safety sample procedures involved a team comprised of a supervisor, chemist, and two technicians for each procedure. Each NSS procedure was upgraded to a ''Use Every Time'' (UET) procedure with sign-off steps to ensure compliance with each step for every nuclear safety sample analyzed. The upgrade program met and exceeded both the long and short term customer needs by improving measurement reliability, providing objective evidence of rigid adherence to program principles and requirements, and enhancing the system for independent verification of representative sampling from designated NCS points

  4. Improved safety in ski jumping.

    Science.gov (United States)

    Wester, K

    1988-01-01

    Among approximately 2,600 licensed Norwegian ski jumpers, only three injuries that caused a permanent medical disability of at least 10% were incurred during the 5 year period from 1982 through 1986. When compared to the previous 5 year period (1977 to 1981), a dramatic improvement in safety is seen, as both number and severity of such injuries were markedly reduced. There are several probable reasons for this improved safety record: better preparation of the jumps, the return to using only one standard heel block, and the fact that coaches are being more responsible, especially with younger jumpers.

  5. 76 FR 74723 - New Car Assessment Program (NCAP); Safety Labeling

    Science.gov (United States)

    2011-12-01

    ... [Docket No. NHTSA 2010-0025] RIN 2127-AK51 New Car Assessment Program (NCAP); Safety Labeling AGENCY... NHTSA's regulation on vehicle labeling of safety rating information to reflect the enhanced NCAP ratings... Traffic Safety Administration under the enhanced NCAP testing and rating program. * * * * * (e) * * * (4...

  6. Preliminary Performance Analysis Program Development for Safety System with Safeguard Vessel

    International Nuclear Information System (INIS)

    Kang, Han-Ok; Lee, Jun; Park, Cheon-Tae; Yoon, Ju-Hyeon; Park, Keun-Bae

    2007-01-01

    SMART is an advanced modular integral type pressurized water reactor for a seawater desalination and an electricity production. Major components of the reactor coolant system such as the pressurizer, Reactor Coolant Pump (RCP), and steam generators are located inside the reactor vessel. The SMART can fundamentally eliminate the possibility of large break loss of coolant accidents (LBLOCAs), improve the natural circulation capability, and better accommodate and thus enhance a resistance to a wide range of transients and accidents. The safety goals of the SMART are enhanced through highly reliable safety systems such as the passive residual heat removal system (PRHRS) and the safeguard vessel coupled with the passive safety injection feature. The safeguard vessel is a steel-made, leak-tight pressure vessel housing the RPV, SIT, and the associated valves and pipelines. A primary function of the safeguard vessel is to confine any radioactive release from the primary circuit within the vessel under DBAs related to loss of the integrity of the primary system. A preliminary performance analysis program for a safety system using the safeguard vessel is developed in this study. The developed program is composed of several subroutines for the reactor coolant system, passive safety injection system, safeguard vessel including the pressure suppression pool, and PRHRS. A small break loss of coolant accident at the upper part of a reactor is analyzed and the results are discussed

  7. Patient Safety Culture and the Ability to Improve: A Proof of Concept Study on Hand Hygiene.

    Science.gov (United States)

    Caris, Martine G; Kamphuis, Pim G A; Dekker, Mireille; de Bruijne, Martine C; van Agtmael, Michiel A; Vandenbroucke-Grauls, Christina M J E

    2017-11-01

    OBJECTIVE To investigate whether the safety culture of a hospital unit is associated with the ability to improve. DESIGN Qualitative investigation of safety culture on hospital units following a before-and-after trial on hand hygiene. SETTING VU University Medical Center, a tertiary-care hospital in the Netherlands. METHODS With support from hospital management, we implemented a hospital-wide program to improve compliance. Over 2 years, compliance was measured through direct observation, twice before, and 4 times after interventions. We analyzed changes in compliance from baseline, and selected units to evaluate safety culture using a positive deviance approach: the hospital unit with the highest hand hygiene compliance and 2 units that showed significant improvement (21% and 16%, respectively) were selected as high performing. Another 2 units showed no improvement and were selected as low performing. A blinded, independent observer conducted interviews with unit management, physicians, and nurses, based on the Hospital Survey on Patient Safety Culture. Safety culture was categorized as pathological (lowest level), reactive, bureaucratic, proactive, or generative (highest level). RESULTS Overall, 3 units showed a proactive or generative safety culture and 2 units had bureaucratic or pathological safety cultures. When comparing compliance and interview results, high-performing units showed high levels of safety culture, while low-performing units showed low levels of safety culture. CONCLUSIONS Safety culture is associated with the ability to improve hand hygiene. Interventions may not be effective when applied in units with low levels of safety culture. Although additional research is needed to corroborate our findings, the safety culture on a unit can benefit from enhancement strategies such as team-building exercises. Strengthening the safety culture before implementing interventions could aid improvement and prevent nonproductive interventions. Infect Control

  8. India's power programs and its concern over environmental safety

    International Nuclear Information System (INIS)

    Prasad, G.E.; Mittra, J.; Sarma, M.S.R.

    2000-01-01

    India's need for electrical power is enormous and per capita consumption of power is to be increased at least by 10 times to reach the level of the world average. Thermal power generation faces two-fold problems. First, there is scarcity of good quality fuel and second, increasing environmental pollution. India 's self reliant, . three stage, 'closed-fuel-cycle' nuclear power program is promising a better solution to the above problems. To ensure Radiation Protection and Safety of Radiation Sources, the Indian Nuclear Power program emphasizes upon design and engineering safety by incorporating' necessary safety features in the design, operational safety through a structured training program and typically through software packages to handle rare unsafe events and regulation by complying safety directives. A health survey among the radiation workers indicates that there is no extra threat to the public from the nuclear power program. Based on the latest technology, as available in case of the nuclear power option, it is quite possible to meet high energy requirements with least impact on the environment. (authors)

  9. A tool for safety evaluations of road improvements.

    Science.gov (United States)

    Peltola, Harri; Rajamäki, Riikka; Luoma, Juha

    2013-11-01

    Road safety impact assessments are requested in general, and the directive on road infrastructure safety management makes them compulsory for Member States of the European Union. However, there is no widely used, science-based safety evaluation tool available. We demonstrate a safety evaluation tool called TARVA. It uses EB safety predictions as the basis for selecting locations for implementing road-safety improvements and provides estimates of safety benefits of selected improvements. Comparing different road accident prediction methods, we demonstrate that the most accurate estimates are produced by EB models, followed by simple accident prediction models, the same average number of accidents for every entity and accident record only. Consequently, advanced model-based estimates should be used. Furthermore, we demonstrate regional comparisons that benefit substantially from such tools. Comparisons between districts have revealed significant differences. However, comparisons like these produce useful improvement ideas only after taking into account the differences in road characteristics between areas. Estimates on crash modification factors can be transferred from other countries but their benefit is greatly limited if the number of target accidents is not properly predicted. Our experience suggests that making predictions and evaluations using the same principle and tools will remarkably improve the quality and comparability of safety estimations. Copyright © 2013 Elsevier Ltd. All rights reserved.

  10. The Armstrong Institute: An Academic Institute for Patient Safety and Quality Improvement, Research, Training, and Practice.

    Science.gov (United States)

    Pronovost, Peter J; Holzmueller, Christine G; Molello, Nancy E; Paine, Lori; Winner, Laura; Marsteller, Jill A; Berenholtz, Sean M; Aboumatar, Hanan J; Demski, Renee; Armstrong, C Michael

    2015-10-01

    Academic medical centers (AMCs) could advance the science of health care delivery, improve patient safety and quality improvement, and enhance value, but many centers have fragmented efforts with little accountability. Johns Hopkins Medicine, the AMC under which the Johns Hopkins University School of Medicine and the Johns Hopkins Health System are organized, experienced similar challenges, with operational patient safety and quality leadership separate from safety and quality-related research efforts. To unite efforts and establish accountability, the Armstrong Institute for Patient Safety and Quality was created in 2011.The authors describe the development, purpose, governance, function, and challenges of the institute to help other AMCs replicate it and accelerate safety and quality improvement. The purpose is to partner with patients, their loved ones, and all interested parties to end preventable harm, continuously improve patient outcomes and experience, and eliminate waste in health care. A governance structure was created, with care mapped into seven categories, to oversee the quality and safety of all patients treated at a Johns Hopkins Medicine entity. The governance has a Patient Safety and Quality Board Committee that sets strategic goals, and the institute communicates these goals throughout the health system and supports personnel in meeting these goals. The institute is organized into 13 functional councils reflecting their behaviors and purpose. The institute works daily to build the capacity of clinicians trained in safety and quality through established programs, advance improvement science, and implement and evaluate interventions to improve the quality of care and safety of patients.

  11. 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…

  12. HTGR safety research program

    International Nuclear Information System (INIS)

    Barsell, A.W.; Olsen, B.E.; Silady, F.A.

    1981-01-01

    An HTGR safety research program is being performed supporting and guided in priorities by the AIPA Probabilistic Risk Study. Analytical and experimental studies have been conducted in four general areas where modeling or data assumptions contribute to large uncertainties in the consequence assessments and thus, in the risk assessment for key core heat-up accident scenarios. Experimental data have been obtained on time-dependent release of fission products from the fuel particles, and plateout characteristics of condensible fission products in the primary circuit. Potential failure modes of primarily top head PCRV components as well as concrete degradation processes have been analyzed using a series of newly developed models and interlinked computer programs. Containment phenomena, including fission product deposition and potential flammability of liberated combustible gases have been studied analytically. Lastly, the behaviour of boron control material in the core and reactor subcriticality during core heatup have been examined analytically. Research in these areas has formed the basis for consequence updates in GA-A15000. Systematic derivation of future safety research priorities is also discussed. (author)

  13. Analysis of School Food Safety Programs Based on HACCP Principles

    Science.gov (United States)

    Roberts, Kevin R.; Sauer, Kevin; Sneed, Jeannie; Kwon, Junehee; Olds, David; Cole, Kerri; Shanklin, Carol

    2014-01-01

    Purpose/Objectives: The purpose of this study was to determine how school districts have implemented food safety programs based on HACCP principles. Specific objectives included: (1) Evaluate how schools are implementing components of food safety programs; and (2) Determine foodservice employees food-handling practices related to food safety.…

  14. ALWR - regulatory stabilization through simplicity, margin, and improved safety

    International Nuclear Information System (INIS)

    Vine, G.; Gray, S.

    1989-01-01

    The Electric Power Research Institute Advanced Light Water Reactor (ALWR) program is discussed with respect to the following topics: fundamental acceptance criteria for the ALWR; program approach; utility steering committee technical guidance; safety principles; utility requirements document; design bases; generic safety issue resolution; reactor accidents prevention and mitigation; and programmatic plans

  15. Total safety management: An approach to improving safety culture

    International Nuclear Information System (INIS)

    Blush, S.M.

    1993-01-01

    A little over 4 yr ago, Admiral James D. Watkins became Secretary of Energy. President Bush, who had appointed him, informed Watkins that his principal task would be to clean up the nuclear weapons complex and put the US Department of Energy (DOE) back in the business of producing tritium for the nation's nuclear deterrent. Watkins recognized that in order to achieve these objectives, he would have to substantially improve the DOE's safety culture. Safety culture is a relatively new term. The International Atomic Energy Agency (IAEA) used it in a 1986 report on the root causes of the Chernobyl nuclear accident. In 1990, the IAEA's International Nuclear Safety Advisory Group issued a document focusing directly on safety culture. It provides guidelines to the international nuclear community for measuring the effectiveness of safety culture in nuclear organizations. Safety culture has two principal aspects: an organizational framework conducive to safety and the necessary organizational and individual attitudes that promote safety. These obviously go hand in hand. An organization must create the right framework to foster the right attitudes, but individuals must have the right attitudes to create the organizational framework that will support a good safety culture. The difficulty in developing such a synergistic relationship suggests that achieving and sustaining a strong safety culture is not easy, particularly in an organization whose safety culture is in serious disrepair

  16. Patient safety--worker safety: building a culture of safety to improve healthcare worker and patient well-being.

    Science.gov (United States)

    Yassi, Annalee; Hancock, Tina

    2005-01-01

    Patient safety within the Canadian healthcare system is currently a high national priority, which merits a comprehensive understanding of the underlying causes of adverse events. Not least among these is worker health and safety, which is linked to patient outcomes. Healthcare workers have a high risk of workplace injuries and more mental health problems than most other occupational groups. Many healthcare professionals feel fatigued, stressed, in pain, or at risk of illness or injury-factors they feel impede their ability to provide consistent quality care. With this background, the Occupational Health and Safety Agency for Healthcare (OHSAH) in British Columbia, jointly governed by healthcare unions and healthcare employers, launched several major initiatives to improve the healthcare workplace. These included the promotion of safe patient handling, adaptive clothing, scheduled toileting, stroke management training, measures to improve management of aggressive behaviour and, of course, infection control-all intended to improve the safety of workers, but also to improve patient safety and quality of care. Other projects also explicitly promoting physical and mental health at work, as well as patient safety are also underway. Results of the projects are at various stages of completion, but ample evidence has already been obtained to indicate that looking after the well-being of healthcare workers results in safer and better quality patient care. While more research is needed, our work to date suggests that a comprehensive systems approach to promoting a climate of safety, which includes taking into account workplace organizational factors and physical and psychological hazards for workers, is the best way to improve the healthcare workplace and thereby patient safety.

  17. Development of a safety communication and recognition program for construction.

    Science.gov (United States)

    Sparer, Emily H; Herrick, Robert F; Dennerlein, Jack T

    2015-05-01

    Leading-indicator-based (e.g., hazard recognition) incentive programs provide an alternative to controversial lagging-indicator-based (e.g., injury rates) programs. We designed a leading-indicator-based safety communication and recognition program that incentivized safe working conditions. The program was piloted for two months on a commercial construction worksite and then redesigned using qualitative interview and focus group data from management and workers. We then ran the redesigned program for six months on the same worksite. Foremen received detailed weekly feedback from safety inspections, and posters displayed worksite and subcontractor safety scores. In the final program design, the whole site, not individual subcontractors, was the unit of analysis and recognition. This received high levels of acceptance from workers, who noted increased levels of site unity and team-building. This pilot program showed that construction workers value solidarity with others on site, demonstrating the importance of health and safety programs that engage all workers through a reliable and consistent communication infrastructure. © The Author(s) 2015 Reprints and permissions: sagepub.co.uk/journalsPermissions.nav.

  18. Fusion Safety Program. Annual report, FY 1982

    International Nuclear Information System (INIS)

    Crocker, J.G.; Cohen, S.

    1983-07-01

    The Fusion Safety Program major activities for Fiscal Year 1982 are summarized in this report. The program was started in FY-79, with the Idaho National Engineering Laboratory (INEL) designated as lead laboratory and EG and G Idaho, Inc., named as prime contractor to implement this role. The report contains four sections: EG and G Idaho, Inc., Activities at INEL includes major portions of papers dealing with ongoing work in tritium implantation experiments, tritium risk assessment, transient code development, heat transfer and fluid flow analysis, and high temperature oxidation and mobilization of structural material experiments. The section Outside Contracts includes studies of superconducting magnet safety conducted by Argonne National Laboratory, experiments concerning superconductor safety issues performed by the Francis Bitter Magnet Laboratory of the Massachusetts Institute of Technology (MIT) to verify analytical work, a continuation of safety and environmental studies by MIT, a summary of lithium safety experiments at Hanford Engineering Development Laboratory, and the results of tritium gas conversion to oxide experiments at Oak Ridge National Laboratory. A List of Publications and Proposed FY-83 Activities are also presented

  19. A program for thai rubber tappers to improve the cost of occupational health and safety.

    Science.gov (United States)

    Arphorn, Sara; Chaonasuan, Porntip; Pruktharathikul, Vichai; Singhakajen, Vajira; Chaikittiporn, Chalermchai

    2010-01-01

    The purposes of this research were to determine the cost of occupational health and safety and work-related health problems, accidents, injuries and illnesses in rubber tappers by implementing a program in which rubber tappers were provided training on self-care in order to reduce and prevent work-related accidents, injuries and illnesses. Data on costs for healthcare, the prevention and the treatment of work-related accidents, injuries and illnesses were collected by interview using a questionnaire. The findings revealed that there was no relationship between what was spent on healthcare and the prevention of work-related accidents, injuries and illnesses and that spent on the treatment of work-related accidents, injuries and illnesses. The proportion of the injured subjects after the program implementation was significantly less than that before the program implementation (p<0.001). The level of pain after the program implementation was significantly less than that before the program implementation (p<0.05). The treatment costs incurred after the program implementation were significantly less than those incurred before the program implementation (p<0.001). It was demonstrated that this program raised the health awareness of rubber tappers. It strongly empowered the leadership in health promotion for the community.

  20. Research reactor management. Safety improvement activities in HANARO

    International Nuclear Information System (INIS)

    Wu, Jong-Sup; Jung, Hoan-Sung; Hong, Sung Taek; Ahn, Guk-Hoon

    2012-01-01

    Safety activities in HANARO have been continuously conducted to enhance its safe operation. Great effort has been placed on a normalization and improvement of the safety attitude of the regular staff and other employees working at the reactor and other experimental facilities. This paper introduces the activities on safety improvement that were performed over the last few years. (author)

  1. Comparing Occupational Health and Safety Management System Programming with Injury Rates in Poultry Production.

    Science.gov (United States)

    Autenrieth, Daniel A; Brazile, William J; Douphrate, David I; Román-Muñiz, Ivette N; Reynolds, Stephen J

    2016-01-01

    Effective methods to reduce work-related injuries and illnesses in animal production agriculture are sorely needed. One approach that may be helpful for agriculture producers is the adoption of occupational health and safety management systems. In this replication study, the authors compared the injury rates on 32 poultry growing operations with the level of occupational health and safety management system programming at each farm. Overall correlations between injury rates and programming level were determined, as were correlations between individual management system subcomponents to ascertain which parts might be the most useful for poultry producers. It was found that, in general, higher levels of occupational health and safety management system programming were associated with lower rates of workplace injuries and illnesses, and that Management Leadership was the system subcomponent with the strongest correlation. The strength and significance of the observed associations were greater on poultry farms with more complete management system assessments. These findings are similar to those from a previous study of the dairy production industry, suggesting that occupational health and safety management systems may hold promise as a comprehensive way for producers to improve occupational health and safety performance. Further research is needed to determine the effectiveness of such systems to reduce farm work injuries and illnesses. These results are timely given the increasing focus on occupational safety and health management systems.

  2. A web-based tool for the Comprehensive Unit-based Safety Program (CUSP).

    Science.gov (United States)

    Pronovost, Peter J; King, Jay; Holzmueller, Christine G; Sawyer, Melinda; Bivens, Shauna; Michael, Michelle; Haig, Kathy; Paine, Lori; Moore, Dana; Miller, Marlene

    2006-03-01

    An organization's ability to change is driven by its culture, which in turn has a significant impact on safety. The six-step Comprehensive Unit-Based Safety Program (CUSP) is intended to improve local culture and safety. A Web-based project management tool for CUSP was developed and then pilot tested at two hospitals. HOW ECUSP WORKS: Once a patient safety concern is identified (step 3), a unit-level interdisciplinary safety committee determines issue criticality and starts up the projects (step 4), which are managed using project management tools within eCUSP (step 5). On a project's completion, the results are disseminated through a shared story (step 6). OSF St. Joseph's Medical Center-The Medical Birthing Center (Bloomington, Illinois), identified 11 safety issues, implemented 11 projects, and created 9 shared stories--including one for its Armband Project. The Johns Hopkins Hospital (Baltimore) Medical Progressive Care (MPC4) Unit identified 5 safety issues and implemented 4 ongoing projects, including the intravenous (IV) Tubing Compliance Project. The eCUSP tool's success depends on an organizational commitment to creating a culture of safety.

  3. Multi-approach model for improving agrochemical safety among rice farmers in Pathumthani, Thailand

    Directory of Open Access Journals (Sweden)

    Siriwong W

    2012-07-01

    safety precautions and the use of faulty protective gear. After 6 months, the intervention program showed significant improvements in the overall scores on knowledge, beliefs, behaviors, and home pesticide safety in the study group (P < 0.05. Therefore, this intervention model is effective in improving agrochemical safety behaviors among Khlong Seven Community rice farmers. These findings demonstrate that a multi-approach model for improving agrochemical safety behaviors can lead to sustainable prevention of agrochemical hazards for farmers.Keywords: rice farmer, agrochemical safety, community-based intervention, model

  4. Laboratory services series: a safety program for service groups in a national research and development laboratory (1965--1974)

    International Nuclear Information System (INIS)

    Winget, R.H.

    1975-11-01

    The experiences of a ten-year period of developing a safety program for craft and labor groups supporting a major laboratory are summarized with tabulations of types of injuries or accidents, improvements noted over the decade, and educational and safety recognition efforts

  5. 29 CFR 1960.12 - Dissemination of occupational safety and health program information.

    Science.gov (United States)

    2010-07-01

    ... 29 Labor 9 2010-07-01 2010-07-01 false Dissemination of occupational safety and health program... OCCUPATIONAL SAFETY AND HEALTH PROGRAMS AND RELATED MATTERS Administration § 1960.12 Dissemination of occupational safety and health program information. (a) Copies of the Act, Executive Order 12196, program...

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

    OpenAIRE

    Adjekum, Daniel Kwasi

    2014-01-01

    An assessment of the perceptions of respondents on the safety culture at an accredited Part 141 four year collegiate aviation program was conducted as part of the implementation of a safety management system (SMS). The Collegiate Aviation Program Safety Culture Assessment Survey (CAPSCAS), which was modified and revalidated from the existing Commercial Aviation Safety Survey (CASS), was used. Participants were drawn from flight students and certified flight instructors in the program. The sur...

  7. Improving patient safety culture in Saudi Arabia (2012-2015): trending, improvement and benchmarking.

    Science.gov (United States)

    Alswat, Khalid; Abdalla, Rawia Ahmad Mustafa; Titi, Maher Abdelraheim; Bakash, Maram; Mehmood, Faiza; Zubairi, Beena; Jamal, Diana; El-Jardali, Fadi

    2017-08-02

    Measuring patient safety culture can provide insight into areas for improvement and help monitor changes over time. This study details the findings of a re-assessment of patient safety culture in a multi-site Medical City in Riyadh, Kingdom of Saudi Arabia (KSA). Results were compared to an earlier assessment conducted in 2012 and benchmarked with regional and international studies. Such assessments can provide hospital leadership with insight on how their hospital is performing on patient safety culture composites as a result of quality improvement plans. This paper also explored the association between patient safety culture predictors and patient safety grade, perception of patient safety, frequency of events reported and number of events reported. We utilized a customized version of the patient safety culture survey developed by the Agency for Healthcare Research and Quality. The Medical City is a tertiary care teaching facility composed of two sites (total capacity of 904 beds). Data was analyzed using SPSS 24 at a significance level of 0.05. A t-Test was used to compare results from the 2012 survey to that conducted in 2015. Two adopted Generalized Estimating Equations in addition to two linear models were used to assess the association between composites and patient safety culture outcomes. Results were also benchmarked against similar initiatives in Lebanon, Palestine and USA. Areas of strength in 2015 included Teamwork within units, and Organizational Learning-Continuous Improvement; areas requiring improvement included Non-Punitive Response to Error, and Staffing. Comparing results to the 2012 survey revealed improvement on some areas but non-punitive response to error and Staffing remained the lowest scoring composites in 2015. Regression highlighted significant association between managerial support, organizational learning and feedback and improved survey outcomes. Comparison to international benchmarks revealed that the hospital is performing at or

  8. System Safety Program Plan for Project W-314, tank farm restoration and safe operations

    International Nuclear Information System (INIS)

    Boos, K.A.

    1996-01-01

    This System Safety Program Plan (SSPP) outlines the safety analysis strategy for project W-314, ''Tank Farm Restoration and Safe Operations.'' Project W-314 will provide capital improvements to Hanford's existing Tank Farm facilities, with particular emphasis on infrastructure systems supporting safe operation of the double-shell activities related to the project's conceptual Design Phase, but is planned to be updated and maintained as a ''living document'' throughout the life of the project to reflect the current safety analysis planning for the Tank Farm Restoration and Safe Operations upgrades. This approved W-314 SSPP provides the basis for preparation/approval of all safety analysis documentation needed to support the project

  9. Effective radiological safety program for electron linear accelerators

    International Nuclear Information System (INIS)

    Swanson, W.P.

    1980-10-01

    An outline is presented of some of the main elements of an electron accelerator radiological safety program. The discussion includes types of accelerator facilities, types of radiations to be anticipated, activity induced in components, air and water, and production of toxic gases. Concepts of radiation shielding design are briefly discussed and organizational aspects are considered as an integral part of the overall safety program

  10. Darlington refurbishment - performance improvement programs goals and experience

    Energy Technology Data Exchange (ETDEWEB)

    Mitchell, N. [Ontario Power Generation, Toronto, ON (Canada)

    2015-07-01

    This paper discusses the refurbishment program at the Darlington site. The program focuses on safety, integrity, excellence and personnel. Worker safety and public safety are of the highest priority. Success resulted from collaborative engineering interface, collaborative front end planning, highly competent people and respectful relationship with partners and regulators.

  11. 41 CFR 128-1.8006 - Seismic Safety Program requirements.

    Science.gov (United States)

    2010-07-01

    ... 41 Public Contracts and Property Management 3 2010-07-01 2010-07-01 false Seismic Safety Program requirements. 128-1.8006 Section 128-1.8006 Public Contracts and Property Management Federal Property Management Regulations System (Continued) DEPARTMENT OF JUSTICE 1-INTRODUCTION 1.80-Seismic Safety Program...

  12. Fusion Safety Program annual report, Fiscal Year 1993

    International Nuclear Information System (INIS)

    Longhurst, G.R.; Cadwallader, L.C.; Dolan, T.J.; Herring, J.S.; McCarthy, K.A.; Merrill, B.J.; Motloch, C.G.; Petti, D.A.

    1993-12-01

    This report summarizes the major activities of the Fusion Safety Program in Fiscal Year 1993. The Idaho National Engineering Laboratory (INEL) has been designated by DOE as the lead laboratory for fusion safety, and EG ampersand G Idaho, Inc., is the prime contractor for INEL operations. The Fusion Safety Program was initiated in 1979. Activities are conducted at the INEL and in participating organizations, including universities and private companies. Technical areas covered in the report include tritium safety, beryllium safety, activation product release, reactions involving potential plasma-facing materials, safety of fusion magnet systems, plasma disruptions and edge physics modeling, risk assessment failure rates, computer codes for reactor transient analysis, and regulatory support. These areas include work completed in support of the International Thermonuclear Experimental Reactor (ITER). Also included in the report are summaries of the safety and environmental studies performed at the INEL for the Tokamak Physics Experiment and the Tokamak Fusion Test Reactor projects at the Princeton Plasma Physics Laboratory and a summary of the technical support for the ARIES/PULSAR commercial reactor design studies

  13. [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.

  14. Improving the safety of future nuclear fission power plants

    International Nuclear Information System (INIS)

    Frisch, W.; Gros, G.

    2001-01-01

    The main objectives and principles in nuclear fission reactor safety are presented, e.g. the defence in depth strategy and technical principles such as redundancy, diversity and physical separation. After a brief historical review of the continuous development of safety improvement, the most recent international discussion is presented. This includes mainly the international activities within IAEA and its International Nuclear Safety Advisory Group (INSAG). The safety improvement, presented in recommendations of IAEA and INSAG is expressed as an improvement of all elements and all levels of the defence in depth concept. Special emphasis is put on improvement of the highest level, which requires the implementation of means to mitigate consequences of accidents with severe core damage. The different future concepts are briefly characterised. Some examples from the French-German safety approach are taken to demonstrate how requirements for safety improvement by means of an enhancement of the defence in depth principle are developed

  15. Implementation of a patient safety program at a tertiary health system: A longitudinal analysis of interventions and serious safety events.

    Science.gov (United States)

    Cropper, Douglas P; Harb, Nidal H; Said, Patricia A; Lemke, Jon H; Shammas, Nicolas W

    2018-04-01

    We hypothesize that implementation of a safety program based on high reliability organization principles will reduce serious safety events (SSE). The safety program focused on 7 essential elements: (a) safety rounding, (b) safety oversight teams, (c) safety huddles, (d) safety coaches, (e) good catches/safety heroes, (f) safety education, and (g) red rule. An educational curriculum was implemented focusing on changing high-risk behaviors and implementing critical safety policies. All unusual occurrences were captured in the Midas system and investigated by risk specialists, the safety officer, and the chief medical officer. A multidepartmental committee evaluated these events, and a root cause analysis (RCA) was performed. Events were tabulated and serious safety event (SSE) recorded and plotted over time. Safety success stories (SSSs) were also evaluated over time. A steady drop in SSEs was seen over 9 years. Also a rise in SSSs was evident, reflecting on staff engagement in the program. The parallel change in SSEs, SSSs, and the implementation of various safety interventions highly suggest that the program was successful in achieving its goals. A safety program based on high-reliability organization principles and made a core value of the institution can have a significant positive impact on reducing SSEs. © 2018 American Society for Healthcare Risk Management of the American Hospital Association.

  16. The awareness of employees in safety culture through the improved nuclear safety culture evaluation method

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Young Ga; Sung, Chan Ho; Jung, Yeon Sub [KHNP Central Research Institute, Daejeon (Korea, Republic of)

    2012-10-15

    After the Chernobyl nuclear accident in 1986, nuclear safety culture terminology was at first introduced emphasizing the importance of employees' attitude and organizational safety. The concept of safety culture was spread by INSAG 4 published in 1991. From that time, IAEA had provided the service of ASCOT for the safety culture assessment. However, many people still are thinking that safety culture is abstract and is not clear. It is why the systematic and reliable assessment methodology was not developed. Assessing safety culture is to identify what is the basic assumption for any organization to accept unconsciously. Therefore, it is very difficult to reach a meaningful conclusion by a superficial investigation alone. KHNP had been doing the safety culture assessment which was based on ASCOT methodology every 2 years. And this result had contributed to improving safety culture. But this result could not represent the level of organization's safety culture due to the limitation of method. So, KHNP has improved the safety culture method by benchmarking the over sea assessment techniques in 2011. The effectiveness of this improved methodology was validated through a pilot assessment. In this paper, the level of employees' safety culture awareness was analyzed by the improved method and reviewed what is necessary for the completeness and objectivity of the nuclear safety culture assessment methodology.

  17. The awareness of employees in safety culture through the improved nuclear safety culture evaluation method

    International Nuclear Information System (INIS)

    Kim, Young Ga; Sung, Chan Ho; Jung, Yeon Sub

    2012-01-01

    After the Chernobyl nuclear accident in 1986, nuclear safety culture terminology was at first introduced emphasizing the importance of employees' attitude and organizational safety. The concept of safety culture was spread by INSAG 4 published in 1991. From that time, IAEA had provided the service of ASCOT for the safety culture assessment. However, many people still are thinking that safety culture is abstract and is not clear. It is why the systematic and reliable assessment methodology was not developed. Assessing safety culture is to identify what is the basic assumption for any organization to accept unconsciously. Therefore, it is very difficult to reach a meaningful conclusion by a superficial investigation alone. KHNP had been doing the safety culture assessment which was based on ASCOT methodology every 2 years. And this result had contributed to improving safety culture. But this result could not represent the level of organization's safety culture due to the limitation of method. So, KHNP has improved the safety culture method by benchmarking the over sea assessment techniques in 2011. The effectiveness of this improved methodology was validated through a pilot assessment. In this paper, the level of employees' safety culture awareness was analyzed by the improved method and reviewed what is necessary for the completeness and objectivity of the nuclear safety culture assessment methodology

  18. Nuclear Criticality Safety Organization qualification program. Revision 4

    International Nuclear Information System (INIS)

    Carroll, K.J.; Taylor, R.G.; Worley, C.A.

    1997-01-01

    The Nuclear Criticality Safety Organization (NCSO) is committed to developing and maintaining a staff of highly qualified personnel to meet the current and anticipated needs in Nuclear Criticality Safety (NCS) at the Oak Ridge Y-12 Plant. This document defines the Qualification Program to address the NCSO technical and managerial qualification as required by the Y-12 Training Implementation Matrix (TIM). It is implemented through a combination of LMES plant-wide training courses and professional nuclear criticality safety training provided within the organization. This Qualification Program is applicable to technical and managerial NCSO personnel, including temporary personnel, sub-contractors and/or LMES employees on loan to the NCSO, who perform the NCS tasks or serve NCS-related positions as defined in sections 5 and 6 of this program

  19. Nuclear criticality safety specialist training and qualification programs

    International Nuclear Information System (INIS)

    Hopper, C.M.

    1993-01-01

    Since the beginning of the Nuclear Criticality Safety Division of the American Nuclear Society (ANS) in 1967, the nuclear criticality safety (NCS) community has sought to provide an exchange of information at a national level to facilitate the education and development of NCS specialists. In addition, individual criticality safety organizations within government contractor and licensed commercial nonreactor facilities have developed training and qualification programs for their NCS specialists. However, there has been substantial variability in the content and quality of these program requirements and personnel qualifications, at least as measured within the government contractor community. The purpose of this paper is to provide a brief, general history of staff training and to describe the current direction and focus of US DOE guidance for the content of training and qualification programs designed to develop NCS specialists

  20. Engineering and Safety Partnership Enhances Safety of the Space Shuttle Program (SSP)

    Science.gov (United States)

    Duarte, Alberto

    2007-01-01

    Project Management must use the risk assessment documents (RADs) as tools to support their decision making process. Therefore, these documents have to be initiated, developed, and evolved parallel to the life of the project. Technical preparation and safety compliance of these documents require a great deal of resources. Updating these documents after-the-fact not only requires substantial increase in resources - Project Cost -, but this task is also not useful and perhaps an unnecessary expense. Hazard Reports (HRs), Failure Modes and Effects Analysis (FMEAs), Critical Item Lists (CILs), Risk Management process are, among others, within this category. A positive action resulting from a strong partnership between interested parties is one way to get these documents and related processes and requirements, released and updated in useful time. The Space Shuttle Program (SSP) at the Marshall Space Flight Center has implemented a process which is having positive results and gaining acceptance within the Agency. A hybrid Panel, with equal interest and responsibilities for the two larger organizations, Safety and Engineering, is the focal point of this process. Called the Marshall Safety and Engineering Review Panel (MSERP), its charter (Space Shuttle Program Directive 110 F, April 15, 2005), and its Operating Control Plan emphasizes the technical and safety responsibilities over the program risk documents: HRs; FMEA/CILs; Engineering Changes; anomalies/problem resolutions and corrective action implementations, and trend analysis. The MSERP has undertaken its responsibilities with objectivity, assertiveness, dedication, has operated with focus, and has shown significant results and promising perspectives. The MSERP has been deeply involved in propulsion systems and integration, real time technical issues and other relevant reviews, since its conception. These activities have transformed the propulsion MSERP in a truly participative and value added panel, making a

  1. EUROSAFE Forum for nuclear safety. Towards Convergence of Technical Nuclear Safety Practices in Europe. Safety Improvements - Reasons, Strategies, Implementation

    Energy Technology Data Exchange (ETDEWEB)

    Erven, Ulrich (ed.) [Gesellschaft fuer Anlagen- und Reaktorsicherheit, GRS mbH, Schwertnergasse 1, 50667 Koeln (Germany); Cherie, Jean-Bernard (ed.) [Institut de Radioprotection et de Surete Nucleaire, IRSN, BP 17, 92262 Fontenay-aux-Roses Cedex (France); Boeck, Benoit De (ed.) [Association Vincotte Nuclear, AVN, Rue Walcourt 148, 1070 Bruxelles (Belgium)

    2005-07-01

    The EUROSAFE Forum for Nuclear Safety is part of the EUROSAFE approach, which consists of two further elements: the EUROSAFE Tribune and the EUROSAFE Web site. The general aim of EUROSAFE is to contribute to fostering the convergence of technical nuclear safety practices in a broad European context. This is done by providing technical safety and research organisations, safety authorities, power utilities, the rest of the industry and non-governmental organisations mainly from the European Union and East-European countries, and international organisations with a platform for the presentation of recent analyses and R and D in the field of nuclear safety. The goal is to share experiences, to exchange technical and scientific opinions, and to conduct debates on key issues in the fields of nuclear safety and radiation protection. The EUROSAFE Forum on 2005 focused on Safety Improvements, Reasons - Strategies - Implementation, from the point of view of the authorities, TSOs and industry. Latest work in nuclear installation safety and research, waste management, radiation safety as well as nuclear material and nuclear facilities security carried out by GRS, IRSN, AVN and their partners in the European Union, Switzerland and Eastern Europe are presented. A high level of nuclear safety is a priority for the countries of Europe. The technical safety organisations play an important role in contributing to that objective through appropriate approaches to major safety issues as part of their assessments and research activities. The challenges to nuclear safety are international. Changes in underlying technologies such as instrumentation and control, the impact of electricity market deregulation, demands for improved safety and safety management, the ageing of nuclear facilities, waste management, maintaining and improving scientific and technical knowledge, and the need for greater transparency - these are all issues where the value of an international approach is gaining

  2. EUROSAFE Forum for nuclear safety. Towards Convergence of Technical Nuclear Safety Practices in Europe. Safety Improvements - Reasons, Strategies, Implementation

    Energy Technology Data Exchange (ETDEWEB)

    Erven, Ulrich [Gesellschaft fuer Anlagen- und Reaktorsicherheit, GRS mbH, Schwertnergasse 1, 50667 Koeln (Germany); Cherie, Jean-Bernard [Institut de Radioprotection et de Surete Nucleaire, IRSN, BP 17, 92262 Fontenay-aux-Roses Cedex (France); Boeck, Benoit De [Association Vincotte Nuclear, AVN, Rue Walcourt 148, 1070 Bruxelles (Belgium)

    2005-07-01

    The EUROSAFE Forum for Nuclear Safety is part of the EUROSAFE approach, which consists of two further elements: the EUROSAFE Tribune and the EUROSAFE Web site. The general aim of EUROSAFE is to contribute to fostering the convergence of technical nuclear safety practices in a broad European context. This is done by providing technical safety and research organisations, safety authorities, power utilities, the rest of the industry and non-governmental organisations mainly from the European Union and East-European countries, and international organisations with a platform for the presentation of recent analyses and R and D in the field of nuclear safety. The goal is to share experiences, to exchange technical and scientific opinions, and to conduct debates on key issues in the fields of nuclear safety and radiation protection. The EUROSAFE Forum on 2005 focused on Safety Improvements, Reasons - Strategies - Implementation, from the point of view of the authorities, TSOs and industry. Latest work in nuclear installation safety and research, waste management, radiation safety as well as nuclear material and nuclear facilities security carried out by GRS, IRSN, AVN and their partners in the European Union, Switzerland and Eastern Europe are presented. A high level of nuclear safety is a priority for the countries of Europe. The technical safety organisations play an important role in contributing to that objective through appropriate approaches to major safety issues as part of their assessments and research activities. The challenges to nuclear safety are international. Changes in underlying technologies such as instrumentation and control, the impact of electricity market deregulation, demands for improved safety and safety management, the ageing of nuclear facilities, waste management, maintaining and improving scientific and technical knowledge, and the need for greater transparency - these are all issues where the value of an international approach is gaining

  3. Twenty years of improvements in LWR safety

    International Nuclear Information System (INIS)

    Franks, S. III; Mulkey, J.P.; Moonka, A.

    1996-01-01

    Substantial improvements have been made in the safety of light-water reactors in the US during the past two decades, making currently operating reactors safer than ever before. Safety improvements have resulted both from regulatory and operational changes and from new knowledge and technology. The US Nuclear Regulatory Commission, the US Department of Energy, and the American nuclear power industry have worked together and with the international community to enhance the safety of existing plants and to incorporate lessons learned from prior operation into designs for a new generation of advanced, inherently safer reactors

  4. Japan`s international cooperation programs on seismic safety of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Sanada, Akira [Agency of Natural Resources and Energy, Tokyo (Japan)

    1997-03-01

    MITI is promoting many international cooperation programs on nuclear safety area. The seismic safety of nuclear power plants (NPPs) is a one of most important cooperation areas. Experts from MITI and related organization join the multilateral cooperation programs carried out by international organization such as IAEA, OECD/NEA etc. MITI is also promoting bilateral cooperation programs such as information exchange meetings, training programs and seminars on nuclear safety with several countries. Concerning to the cooperation programs on seismic safety of NPPs such as information exchange and training, MITI shall continue and expand these programs. (J.P.N.)

  5. A BWR Safety and Operability Improvements

    International Nuclear Information System (INIS)

    Sawyer, Craig D.

    1993-01-01

    The A BWR is the culmination of 30 years of design, development and operating experience of BWRs around the world. It represents across the board improvements is safety, operation and maintenance practices (O and M), economics, radiation exposure and rad waste generation. More than ten years and $20m5 went into the design and development of its new features, and it is now under construction in Japan. This paper concentrates on the safety and operability improvements. In the safety area, more than a decade improvement in core damage frequency (CDFR) has been assessed by formal PIRA techniques, with CDFR less than 10 -6 /year. Severe accident mitigation has also been formally addressed in the design. Plant operations were simplified by incorporation of better materials, optimum use of redundancy in mechanical and electrical equipment so that on-line maintenance can be performed, by better arrangements which account for required maintenance practices, and by an advanced control room

  6. Ostomy Home Skills Program

    Medline Plus

    Full Text Available ... and Safety Inspiring Quality Initiative Resources Continuous Quality Improvement ACS Clinical Scholars in Residence AHRQ Safety Program ... Enrollment Webinars ACS NSQIP ACS National Surgical Quality Improvement Program ACS National Surgical Quality Improvement Program About ...

  7. Improvement program of state supervision system for radioactive and nuclear installations

    International Nuclear Information System (INIS)

    Cardenas, J.

    1993-01-01

    The current program begins as part of a policy to take care of the development of the cuban nuclear program and with the objective of improving the state supervision system of nuclear and radioactive facilities on the basis of the national experience, good skills internationally accepted and taking into account IAEA recommendations. The program develops the following topics: reorientation and restructure of state supervision, review of the current nuclear legislature, update of regulations of facility safety and qualification and training of state supervision personnel

  8. 78 FR 48029 - Improving Chemical Facility Safety and Security

    Science.gov (United States)

    2013-08-07

    ... Improving Chemical Facility Safety and Security By the authority vested in me as President by the... at reducing the safety risks and security risks associated with hazardous chemicals. However... to further improve chemical facility safety and security in coordination with owners and operators...

  9. 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.

  10. Developing an integrated dam safety program

    International Nuclear Information System (INIS)

    Nielsen, N. M.; Lampa, J.

    1996-01-01

    An effort has been made to demonstrate that dam safety is an integral part of asset management which, when properly done, ensures that all objectives relating to safety and compliance, profitability, stakeholders' expectations and customer satisfaction, are achieved. The means to achieving this integration of the dam safety program and the level of effort required for each core function have been identified using the risk management approach to pinpoint vulnerabilities, and subsequently to focus priorities. The process is considered appropriate for any combination of numbers, sizes and uses of dams, and is designed to prevent exposure to unacceptable risks. 5 refs., 1 tab

  11. Technical specification improvement through safety margin considerations

    International Nuclear Information System (INIS)

    Howard, R.C.; Jansen, R.L.

    1986-01-01

    Westinghouse has developed an approach for utilizing safety analysis margin considerations to improve plant operability through technical specification revision. This approach relies on the identification and use of parameter interrelations and sensitivities to identify acceptable operating envelopes. This paper summarizes technical specification activities to date and presents the use of safety margin considerations as another viable method to obtain technical specification improvement

  12. Improving plant state information for better operational safety

    International Nuclear Information System (INIS)

    Girard, C.; Olivier, E.; Grimaldi, X.

    1994-01-01

    Nuclear Power Plant (NPP) safety is strongly dependent on components' reliability and particularly on plant state information reliability. This information, used by the plant operators in order to produce appropriate actions, have to be of a high degree of confidence, especially in accidental conditions where safety is threatened. In this perspective, FRAMATOME, EDF and CEA have started a joint research program to prospect different solutions aiming at a better reliability for critical information needed to safety operate the plant. This paper gives the main results of this program and describes the developments that have been made in order to assess reliability of different information systems used in a Nuclear Power Plant. (Author)

  13. Research and development program in reactor safety for NUCLEBRAS

    International Nuclear Information System (INIS)

    Pinheiro, R.B.; Resende Lobo, A.A. de; Horta, J.A.L.; Avelar Esteves, F. de; Lepecki, W.P.S.; Mohr, K.; Selvatici, E.

    1984-01-01

    With technical assistance from the IAEA, it was established recently an analytical and experimental Research and Development Program for NUCLEBRAS in the area of reactor safety. The main objectives of this program is to make possible, with low investments, the active participation of NUCLEBRAS in international PWR safety research. The analytical and experimental activities of the program are described with some detail, and the main results achieved up to now are presented. (Author) [pt

  14. Ostomy Home Skills Program

    Medline Plus

    Full Text Available ... Quality and Safety Inspiring Quality Initiative Resources Continuous Quality Improvement ACS Clinical Scholars in Residence AHRQ Safety Program ... ISCR Enrollment Webinars ACS NSQIP ACS National Surgical Quality Improvement Program ACS National Surgical Quality Improvement Program About ...

  15. Seismic safety margin research program. Program plan, Revision I

    International Nuclear Information System (INIS)

    Smith, P.D.; Tokarz, F.J.; Bernreuter, D.L.; Cummings, G.E.; Chou, C.K.; Vagliente, V.N.

    1978-01-01

    The overall objective of the SSMRP is to develop mathematical models that realistically predict the probability of radioactive releases from seismically induced events in nuclear power plants. These models will be used for four purposes: (1) To perform sensitivity studies to determine the weak links in seismic methodology. The weak links will then be improved by research and development. (2) To estimate the probability of release for a plant. It is believed that the major difficulty in the program will be to obtain acceptably small confidence limits on the probability of release. (3) To estimate the conservatisms in the Standard Review Plan (SRP) seismic design methodology. This will be done by comparing the results of the SRP methodology and the methodology resulting from the research and development in (1). (4) To develop an improved seismic design methodology based on probability. The Phase I objective proposed in this report is to develop mathematical models which will accomplish the purposes No. 1 and No. 2 with simplified assumptions such as linear elastic analysis, limited assessment on component fragility (considering only accident sequences leading to core melt), and simplified safety system

  16. The Nordic safety program on accident consequence assessment

    International Nuclear Information System (INIS)

    Tveten, U.

    1988-01-01

    One important part of Nordic cooperation is partially funded by the Nordic Council of Ministers, namely the work performed within the Nordic Safety Program (often referred to as the NKA projects). NKA is the Nordic abbreviation of the Nordic Liaison Committee on Atomic Energy. One program area in the present four-year period is concerned with problems related to reactor accident consequence assessment, and contains almost twenty projects covering a wide range of subjects. The author is program coordinator for this program area. The program will be completed in 1989. The program was strongly influenced by Chernobyl, and a number of new projects were included in the program in 1986. Involved in the program are these Nordic institutions: Riso National Laboratory (Denmark). Technical Research Centre of Finland. Finnish Centre for Radiation and Nuclear Safety. Finnish Meteorological Institute. Institute for Energy Technology (Norway). Agricultural University of Norway. Meteorological Institute of Norway. Studsvik Energiteknik AB (Sweden). National Defence Research Laboratory (Sweden)

  17. Systems Analysis of NASA Aviation Safety Program: Final Report

    Science.gov (United States)

    Jones, Sharon M.; Reveley, Mary S.; Withrow, Colleen A.; Evans, Joni K.; Barr, Lawrence; Leone, Karen

    2013-01-01

    A three-month study (February to April 2010) of the NASA Aviation Safety (AvSafe) program was conducted. This study comprised three components: (1) a statistical analysis of currently available civilian subsonic aircraft data from the National Transportation Safety Board (NTSB), the Federal Aviation Administration (FAA), and the Aviation Safety Information Analysis and Sharing (ASIAS) system to identify any significant or overlooked aviation safety issues; (2) a high-level qualitative identification of future safety risks, with an assessment of the potential impact of the NASA AvSafe research on the National Airspace System (NAS) based on these risks; and (3) a detailed, top-down analysis of the NASA AvSafe program using an established and peer-reviewed systems analysis methodology. The statistical analysis identified the top aviation "tall poles" based on NTSB accident and FAA incident data from 1997 to 2006. A separate examination of medical helicopter accidents in the United States was also conducted. Multiple external sources were used to develop a compilation of ten "tall poles" in future safety issues/risks. The top-down analysis of the AvSafe was conducted by using a modification of the Gibson methodology. Of the 17 challenging safety issues that were identified, 11 were directly addressed by the AvSafe program research portfolio.

  18. Management of radioactive material safety programs at medical facilities. Final report

    International Nuclear Information System (INIS)

    Camper, L.W.; Schlueter, J.; Woods, S.

    1997-05-01

    A Task Force, comprising eight US Nuclear Regulatory Commission and two Agreement State program staff members, developed the guidance contained in this report. This report describes a systematic approach for effectively managing radiation safety programs at medical facilities. This is accomplished by defining and emphasizing the roles of an institution's executive management, radiation safety committee, and radiation safety officer. Various aspects of program management are discussed and guidance is offered on selecting the radiation safety officer, determining adequate resources for the program, using such contractual services as consultants and service companies, conducting audits, and establishing the roles of authorized users and supervised individuals; NRC's reporting and notification requirements are discussed, and a general description is given of how NRC's licensing, inspection and enforcement programs work

  19. 29 CFR 1960.80 - Secretary's evaluations of agency occupational safety and health programs.

    Science.gov (United States)

    2010-07-01

    ... EMPLOYEE OCCUPATIONAL SAFETY AND HEALTH PROGRAMS AND RELATED MATTERS Evaluation of Federal Occupational Safety and Health Programs § 1960.80 Secretary's evaluations of agency occupational safety and health... evaluating an agency's occupational safety and health program. To accomplish this, the Secretary shall...

  20. Fusion Safety Program annual report: Fiscal year 1987

    International Nuclear Information System (INIS)

    Holland, D.F.; Herring, J.S.; Longhurst, G.R.; Lyon, R.E.; Merrill, B.J.; Piet, S.J.

    1988-02-01

    This report summarizes the Fusion Safety Program major activities in fiscal year 1987. The Idaho National Engineering Laboratory (INEL) is the designated lead laboraotry and EG and G Idaho, Inc., is the prime contractor for this program, which was initiated in 1979. Activities are conducted at the INEL and in participating laboratories including the Hanford Engineering Development Laboratory (HEDL), the Massachusetts Institute of Technology (MIT), and the University of Wisconsin. The technical areas covered in the report include tritium safety, activation product release, reactions involving lithium breeding materials, safety of fusion magnet systems, plasma disruptions, risk assessment methodology, computer codes development for reactor transients, and fusion waste management. Also included in the report is a summary of the safety and environmental analysis and conventional facilities design performed by INEL for the Compact Ignition Tokamak design project, the safety analysis and documentation performed for the Tokamak Ignition/Burn Experimental Reactor design, and the technical support provided to the Environmental Safety and Economics Committee (ESECOM). 42 refs., 17 figs., 4 tabs

  1. QUEST®: A Data-Driven Collaboration to Improve Quality, Efficiency, Safety, and Transparency in Acute Care.

    Science.gov (United States)

    Crimmins, Mary M; Lowe, Timothy J; Barrington, Monica; Kaylor, Courtney; Phipps, Terri; Le-Roy, Charlene; Brooks, Tammy; Jones, Mashekia; Martin, John

    2016-06-01

    In 2008 Premier (Premier, Inc., Charlotte, North Carolina) began its Quality, Efficiency, and Safety with Transparency (QUEST®) collaborative, which is an acute health care organization program focused on improving quality and reducing patient harm. Retrospective performance data for QUEST hospitals were used to establish trends from the third quarter (Q3; July–September) of 2006 through Q3 2015. The study population included past and present members of the QUEST collaborative (N = 356), with each participating hospital considered a member. The QUEST program engages with member hospitals through a routine-coaching structure, sprints, minicollaboratives, and face-to-face meetings. Cost and efficiency data showed reductions in adjusted cost per discharge for hospitals between Q3 2013 (mean, $8,296; median, $8,459) and Q3 2015 (mean, $8,217; median, $7,895). Evidence-based care (EBC) measures showed improvement from baseline (Q3 2006; mean, 77%; median, 79%) to Q3 2015 (mean, 95%; median, 96%). Observed-to-expected (O/E) mortality improved from 1% to 22% better-than-expected outcomes on average. The QUEST safety harm composite score showed moderate reduction from Q1 2009 to Q3 2015, as did the O/E readmission rates--from Q1 2010 to Q3 2015--with improvement from a 5% to an 8% better-than-expected score. Quantitative and qualitative evaluation of QUEST collaborative hospitals indicated that for the 2006-2015 period, QUEST facilities reduced cost per discharge, improved adherence with evidence-based practice, reduced safety harm composite score, improved patient experience, and reduced unplanned readmissions.

  2. Radiotherapy professionals faced with the obligation of treatments safety improvement

    International Nuclear Information System (INIS)

    2011-01-01

    The occurrence of a major accident in Epinal (2006), followed by one in Toulouse (2007), led the Ministry of Health to mobilize the whole actors in radiotherapy in order to define national measures intended to improve health care security. Compiled in the so-called 'road map', these measures were presented in November 2007, and implemented in the 2009-2013 cancer programme. The French Institute for Radiological Protection and Nuclear Safety (IRSN) undertook a study aiming at assessing the effects of the above-mentioned measures on organization and safety management of radiotherapy facilities, but also on treatment achievement procedures and health professionals. More specifically, IRSN sought to examine the ability of health professionals to take into account new safety demands and to adapt their practices accordingly. With these purposes objectives, a qualitative study using the methods of ergonomics and sociology of organizations was completed in 2009-2010. The results of the study presented in this report show an effective improvement of health care safety along with a variable integration of safety measures depending on radiotherapy facilities and units. In particular, integration depends on 1) the governance mode of the health care facility, more or less conducive to promoting safety, 2) the pre-existence of a safety culture and safety organization, and 3) the facility commitment to health care safety improvement actions. The study also reveals that the implementation of new safety demands and the changes they involve create new constraints, which put pressure on health professionals and may threaten the durability of the improvements made. In order to facilitate the appropriation and implementation by radiotherapy units of the measures meant to improve health care safety, IRSN identifies 6 lines of thought: - strengthen coordination between institutional actors in order to ensure the consistency of the requests addressed to the facilities and limit their

  3. High-heat tank safety issue resolution program plan. Revision 2

    International Nuclear Information System (INIS)

    Wang, O.S.

    1994-12-01

    The purpose of this program plan is to provide a guide for selecting corrective actions that will mitigate and/or remediate the high-heat waste tank safety issue for single-shell tank 241-C-106. The heat source of approximately 110,000 Btu/hr is the radioactive decay of the stored waste material (primarily 90 Sr) inadvertently transferred into the tank in the later 1960s. Currently, forced ventilation, with added water to promote thermal conductivity and evaporation cooling, is used for heat removal. The method is very effective and economical. At this time, the only viable solution identified to permanently resolve this safety issue is the removal of heat-generating waste in the tank. This solution is being aggressively pursued as the only remediation method to this safety issue, and tank 241-C-106 has been selected as the first single-shell tank for retrieval. The current cooling method and other alternatives are addressed in this program as means to mitigate this safety issue before retrieval. This program plan has three parts. The first part establishes program objectives and defines safety issue, drivers, and resolution criteria and strategy. The second part evaluates the high-heat safety issue and its mitigation and remediation methods and other alternatives according to resolution logic. The third part identifies major tasks and alternatives for mitigation and resolution of the safety issue. A table of best-estimate schedules for the key tasks is also included in this program plan

  4. Operating experience: safety perspective

    International Nuclear Information System (INIS)

    Piplani, Vivek; Krishnamurthy, P.R.; Kumar, Neeraj; Upadhyay, Devendra

    2015-01-01

    Operating Experience (OE) provides valuable information for improving NPP safety. This may include events, precursors, deviations, deficiencies, problems, new insights to safety, good practices, lessons and corrective actions. As per INSAG-10, an OE program caters as a fundamental means for enhancing the defence-in-depth at NPPs and hence should be viewed as ‘Continuous Safety Performance Improvement Tool’. The ‘Convention on Nuclear Safety’ also recognizes the OE as a tool of high importance for enhancing the NPP safety and its Article 19 mandates each contracting party to establish an effective OE program at operating NPPs. The lessons drawn from major accidents at Three Mile Island, Chernobyl and Fukushima Daiichi NPPs had prompted nuclear stalwarts to change their safety perspective towards NPPs and to frame sound policies on issues like safety culture, severe accident prevention and mitigation. An effective OE program, besides correcting current/potential problems, help in proactively improving the NPP design, operating and maintenance procedures, practices, training, etc., and thus plays vital role in ensuring safe and efficient operation of NPPs. Further it enhances knowledge with regard to equipment operating characteristics, system performance trends and provides data for quantitative and qualitative safety analysis. Besides all above, an OE program inculcates a learning culture in the organisation and thus helps in continuously enhancing the expertise, technical competency and knowledge base of its staff. Nuclear and Radiation Facilities in India are regulated by Atomic Energy Regulatory Board (AERB). Operating Plants Safety Division (OPSD) of AERB is involved in managing operating experience activities. This paper provides insights about the operating experience program of OPSD, AERB (including its on-line data base namely OPSD STAR) and its utilisation in improving the regulations and safety at Indian NPPs/projects. (author)

  5. 29 CFR 1960.79 - Self-evaluations of occupational safety and health programs.

    Science.gov (United States)

    2010-07-01

    ... 29 Labor 9 2010-07-01 2010-07-01 false Self-evaluations of occupational safety and health programs. 1960.79 Section 1960.79 Labor Regulations Relating to Labor (Continued) OCCUPATIONAL SAFETY AND HEALTH... AND HEALTH PROGRAMS AND RELATED MATTERS Evaluation of Federal Occupational Safety and Health Programs...

  6. Management of a comprehensive radiation safety program in a major American University and affiliated academic medical center

    International Nuclear Information System (INIS)

    Yoshizumi, T.T.; Reiman, R.E.; Vylet, V.; Clapp, J.R.; Thomann, W.R.; Lyles, K.W.

    2000-01-01

    Duke University, which operates under eight radiation licenses issued by the State of North Carolina, consists of a leading medical center including extensive inpatient and outpatient facilities, a medical school, biomedical research labs, and an academic campus including two major accelerator facilities. The Nuclear Medicine and Radiation Oncology departments handle over 40,000 diagnostic and therapeutic procedures annually, including approximately 160 radioiodine therapeutic cases. In biomedical research labs, about 300 professors are authorized to use radioactive materials. Over 2,000 radiation workers are identified on campus. Over the past two years, we have transformed the existing radiation safety program into a more responsive and more accountable one. Simultaneously, the institutional 'culture' changed, and the Radiation Safety Division came to be viewed as a helpful ally by investigators. The purpose of this paper is to present our experiences that have made this transformation possible. Our initiatives included; (a) defining short-term and long-term goals; (b) establishing a definitive chain of authority; (c) obtaining an external review by a consultant Health Physicist; (d) improving existing radiation safety programs; (e) reorganizing the Radiation Safety Division, with creation of multidisciplinary professional staff positions; (f) implementing campus-wide radiation safety training, (g) increasing technician positions; (h) establishing monthly medical center radiation safety executive meeting. As a result progress made at the Divisional level includes; (a) culture change by recruiting professionals with academic credentials and recent college graduates; (b) implementing weekly staff meetings and monthly quality assurance meetings; (c) achieving academic prominence by publishing and presenting papers in national meetings; (d) senior staff achieving faculty appointments with academic departments; (e) senior staff participating in graduate student

  7. A program approach for site safety at oil spills

    International Nuclear Information System (INIS)

    Whipple, F.L.; Glenn, S.P.; Ocken, J.J.; Ott, G.L.

    1993-01-01

    When OSHA developed the hazardous waste operations (Hazwoper) regulations (29 CFR 1910.120) members of the response community envisioned a separation of oil and open-quotes hazmatclose quotes response operations. Organizations that deal with oil spills have had difficulty applying Hazwoper regulations to oil spill operations. This hinders meaningful implementation of the standard for their personnel. We should approach oil spills with the same degree of caution that is applied to hazmat response. Training frequently does not address the safety of oil spill response operations. Site-specific safety and health plans often are neglected or omitted. Certain oils expose workers to carcinogens, as well as chronic and acute hazards. Significant physical hazards are most important. In responding to oil spills, the hazards must be addressed. It is the authors' contention that a need exists for safety program at oil spill sites. Gone are the days of labor pool hires cleaning up spills in jeans and sneakers. The key to meaningful programs for oil spills requires application of controls focused on relevant safety risks rather than minimal chemical exposure hazards. Working with concerned reviewers from other agencies and organizations, the authors have developed a general safety and health program for oil spill response. It is intended to serve as the basis for organizations to customize their own written safety and health program (required by OSHA). It also provides a separate generic site safety plan for emergency phase oil spill operations (check-list) and long term post-emergency phase operations

  8. Surveillance of adverse effects following vaccination and safety of immunization programs.

    Science.gov (United States)

    Waldman, Eliseu Alves; Luhm, Karin Regina; Monteiro, Sandra Aparecida Moreira Gomes; Freitas, Fabiana Ramos Martin de

    2011-02-01

    The aim of the review was to analyze conceptual and operational aspects of systems for surveillance of adverse events following immunization. Articles available in electronic format were included, published between 1985 and 2009, selected from the PubMed/Medline databases using the key words "adverse events following vaccine surveillance", "post-marketing surveillance", "safety vaccine" and "Phase IV clinical trials". Articles focusing on specific adverse events were excluded. The major aspects underlying the Public Health importance of adverse events following vaccination, the instruments aimed at ensuring vaccine safety, and the purpose, attributes, types, data interpretation issues, limitations, and further challenges in adverse events following immunization were describe, as well as strategies to improve sensitivity. The review was concluded by discussing the challenges to be faced in coming years with respect to ensuring the safety and reliability of vaccination programs.

  9. Integrated program of using of Probabilistic Safety Analysis in Spain

    International Nuclear Information System (INIS)

    1998-01-01

    Since 25 June 1986, when the CSN (Nuclear Safety Conseil) approve the Integrated Program of Probabilistic Safety Analysis, this program has articulated the main activities of CSN. This document summarize the activities developed during these years and reviews the Integrated programme

  10. Construction safety program for the National Ignition Facility

    International Nuclear Information System (INIS)

    Cerruti, S.J.

    1997-01-01

    The Construction Safety Program (CSP) for NIF sets forth the responsibilities, guidelines, rules, policies and regulations for all workers involved in the construction, special equipment installation, acceptance testing, and initial activation and operation of NIF at LLNL during the construction period of NIF. During this period, all workers are required to implement measures to create a universal awareness which promotes safe practice at the work site, and which will achieve NIF's management objectives in preventing accidents and illnesses. Construction safety for NIF is predicated on everyone performing their jobs in a manner which prevents job-related disabling injuries and illnesses. The CSP outlines the minimum environment, safety, and health (ES ampersand H) standards, LLNL policies and the Construction Industry Institute (CII) Zero Injury Techniques requirements that all workers at the NIF construction site shall adhere to during the construction period of NIF. It identifies the safety requirements which the NIF organizational Elements, construction contractors and construction subcontractors must include in their safety plans for the construction period of NIF, and presents safety protocols and guidelines which workers shall follow to assure a safe and healthful work environment. The CSP also identifies the ES ampersand H responsibilities of LLNL employees, non-LLNL employees, construction contractors, construction subcontractors, and various levels of management within the NIF Program at LLNL. In addition, the CSP contains the responsibilities and functions of ES ampersand H support organizations and administrative groups, and describes their interactions with the NIF Program

  11. Construction safety program for the National Ignition Facility

    Energy Technology Data Exchange (ETDEWEB)

    Cerruti, S.J.

    1997-01-01

    The Construction Safety Program (CSP) for NIF sets forth the responsibilities, guidelines, rules, policies and regulations for all workers involved in the construction, special equipment installation, acceptance testing, and initial activation and operation of NIF at LLNL during the construction period of NIF. During this period, all workers are required to implement measures to create a universal awareness which promotes safe practice at the work site, and which will achieve NIF`s management objectives in preventing accidents and illnesses. Construction safety for NIF is predicated on everyone performing their jobs in a manner which prevents job-related disabling injuries and illnesses. The CSP outlines the minimum environment, safety, and health (ES&H) standards, LLNL policies and the Construction Industry Institute (CII) Zero Injury Techniques requirements that all workers at the NIF construction site shall adhere to during the construction period of NIF. It identifies the safety requirements which the NIF organizational Elements, construction contractors and construction subcontractors must include in their safety plans for the construction period of NIF, and presents safety protocols and guidelines which workers shall follow to assure a safe and healthful work environment. The CSP also identifies the ES&H responsibilities of LLNL employees, non-LLNL employees, construction contractors, construction subcontractors, and various levels of management within the NIF Program at LLNL. In addition, the CSP contains the responsibilities and functions of ES&H support organizations and administrative groups, and describes their interactions with the NIF Program.

  12. Improving nuclear safety of VVER-440 units

    International Nuclear Information System (INIS)

    Nochev, T.; Sabinov, S.

    2001-01-01

    In this paper authors deals with improvement of nuclear safety of WWER-440 units in Kozloduy NPP. Main directions for improving nuclear safety of WWER-440 units were: - to expand number of the design accident; - to increase reliability of equipment important for the safety; - to decrease the probability of initiating events; - improvements the integrity of the primary circuit (application LBB concept, qualification of the pressure safety valves to avoid pressurized thermal shock); - improvement of the fire protection; - improvement of the operation including upgrading and improvement of operational documents, implementation of new system for training the operators and etc.; - reassessment of the seismic response of the plant. Main actions were made at NPP Kozloduy to increase nuclear safety of VVER-440 units. 1. Modernization of Emergency High Pressure Safety Injection System. The modernization includes dividing of independent channels with reservation of active elements. Pumps were exchanged with more effective and reliable ones. HPSIS was increased reliability in general through decrease number of active elements and exchanged with passive. 2. For the purpose of avoiding fast cooling at the primary circuit and obtaining thermal shock of reactor vessel, Main Safety Insulation Valves are installed at NPP Kozloduy. 3. Modernization of Emergency power supplies AC. Oil breakers VMP-10 are exchanged with gas FS-4. 4. Generator breakers are installed to decrease probability of loss power supply and blackout. They provide reliable power supply to the system important for the safety in case of failure on generator. 5. I and C system has been qualified and optimized. 6. Reassessments of Limiting Conditions of Operation and new scram signals have been introduced. 7. An operators-oriented Informational System has been developed. It includes ensuring and updating of equipment data, new informational support of operator and etc. 8. A new auxiliary independent system for

  13. Management of radioactive material safety programs at medical facilities. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Camper, L.W.; Schlueter, J.; Woods, S. [and others

    1997-05-01

    A Task Force, comprising eight US Nuclear Regulatory Commission and two Agreement State program staff members, developed the guidance contained in this report. This report describes a systematic approach for effectively managing radiation safety programs at medical facilities. This is accomplished by defining and emphasizing the roles of an institution`s executive management, radiation safety committee, and radiation safety officer. Various aspects of program management are discussed and guidance is offered on selecting the radiation safety officer, determining adequate resources for the program, using such contractual services as consultants and service companies, conducting audits, and establishing the roles of authorized users and supervised individuals; NRC`s reporting and notification requirements are discussed, and a general description is given of how NRC`s licensing, inspection and enforcement programs work.

  14. Safer Roads: Comparisons Between Road Assessment Program and Composite Road Safety Index Method

    Directory of Open Access Journals (Sweden)

    Mohd Razelan Intan Suhana

    2017-01-01

    Full Text Available In most countries, crash statistics have becoming very crucial in evaluating road’s safety level. In Malaysia, these data are very important in deciding crash-prone areas known as black spot where specific road improvements plan will be proposed. However due to the unavailability of reliable crash data in many developing countries, appropriate road maintenance measures are facing great troubles. In light of that, several proactive methods in defining road’s safety level such as Road Assessment Program (RAP have emerged. This research aim to compare two proactive methods that have been tested in Malaysian roads ; road assessment program and road environment risk index which was developed based on composite index theory in defining road’s safety level. Composite road environment risk index was combining several crucial environment indicators, assigning weight and aggregating the individual index together to form a single value representing the road’s safety level. Based on the results, it can be concluded that both road assessment program and composite road environment risk index are contradicted in six different ways such as type of speed used, type of analysis used and their final outcomes. However, with an aim to promote safer roads, these two methods can be used concurrently as the outcomes in both methods seems to fulfil each other’s gap very well.

  15. Research program on regulatory safety research - Synthesis report 2008

    International Nuclear Information System (INIS)

    Mailaender, R

    2009-06-01

    This report for the Swiss Federal Office of Energy (SFOE) summarises the program's main points of interest, work done in the year 2008 and the results obtained. The main points of the research program, which is co-ordinated by the Swiss Federal Nuclear Safety Inspectorate ENSI, are discussed. Topics covered concern reactor safety as well as human, organisational and safety aspects. Work done in several areas concerning reactor safety and materials as well as interactions in severe accidents in light-water reactors is described. Radiation protection, the transport and disposal of radioactive wastes and safety culture are also looked at. Finally, national and international co-operation is briefly looked at and work to be done in 2009 is reviewed. The report is completed with a list of research and development projects co-ordinated by ENSI

  16. Leadership Actions to Improve Nuclear Safety Culture

    International Nuclear Information System (INIS)

    Clewett, L.K.

    2016-01-01

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

  17. Fast reactor test facilities in the US safety program

    International Nuclear Information System (INIS)

    Avery, R.; Dickerman, C.E.; Lennox, D.H.; Rose, D.

    1979-01-01

    The needs for safety information derivable from in-pile programs are reviewed, and the correlation made with existing and planned capability. In view of the current status of the U.S. breeder program, emphasis is given in the review to the impact of different fast breeder options on the required program and facilities. It is concluded that facility needs are somewhat independent of specific fast breeder concept, even though the relative emphasis on the various safety issues will differ. 8 refs

  18. Beyond safety accountability

    CERN Document Server

    Geller, E Scott

    2001-01-01

    Written in an easy-to-read conversational tone, Beyond Safety Accountability explains how to develop an organizational culture that encourages people to be accountable for their work practices and to embrace a higher sense of personal responsibility. The author begins by thoroughly explaining the difference between safety accountability and safety responsibility. He then examines the need of organizations to improve safety performance, discusses why such performance improvement can be achieved through a continuous safety process, as distinguished from a safety program, and provides the practic

  19. Operation safety at Ignalina NPP

    International Nuclear Information System (INIS)

    Zheltobriukh, G.

    1999-01-01

    An improvement of operational safety at Ignalina NPP covers: improvement of management structure and safety culture; symptom-based emergency operating procedures; staff training and full scope simulator; program of components ageing; metal inspection; improvement of fire safety. The first plan of Ignalina NPP Safety culture development for 1997 purposed to the SAR recommendation implementation was prepared and approved by the General Director

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

    Science.gov (United States)

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

    2016-10-01

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

  1. A reliability program approach to operational safety

    International Nuclear Information System (INIS)

    Mueller, C.J.; Bezella, W.A.

    1985-01-01

    A Reliability Program (RP) model based on proven reliability techniques is being formulated for potential application in the nuclear power industry. Methods employed under NASA and military direction, commercial airline and related FAA programs were surveyed and a review of current nuclear risk-dominant issues conducted. The need for a reliability approach to address dependent system failures, operating and emergency procedures and human performance, and develop a plant-specific performance data base for safety decision making is demonstrated. Current research has concentrated on developing a Reliability Program approach for the operating phase of a nuclear plant's lifecycle. The approach incorporates performance monitoring and evaluation activities with dedicated tasks that integrate these activities with operation, surveillance, and maintenance of the plant. The detection, root-cause evaluation and before-the-fact correction of incipient or actual systems failures as a mechanism for maintaining plant safety is a major objective of the Reliability Program. (orig./HP)

  2. Seismic safety margin assessment program (Annual safety research report, JFY 2010)

    International Nuclear Information System (INIS)

    Suzuki, Kenichi; Iijima, Toru; Inagaki, Masakatsu; Taoka, Hideto; Hidaka, Shinjiro

    2011-01-01

    Seismic capacity test data, analysis method and evaluation code provided by Seismic Safety Margin Assessment Program have been utilized for the support of seismic back-check evaluation of existing plants. The summary of the program in 2010 is as follows. 1. Component seismic capacity test and quantitative seismic capacity evaluation. Many seismic capacity tests of various snubbers were conducted and quantitative seismic capacities were evaluated. One of the emergency diesel generator partial-model seismic capacity tests was conducted and quantitative seismic capacity was evaluated. Some of the analytical evaluations of piping-system seismic capacities were conducted. 2. Analysis method for minute evaluation of component seismic response. The difference of seismic response of large components such as primary containment vessel and reactor pressure vessel when they were coupled with 3-dimensional FEM building model or 1-dimensional lumped mass building model, was quantitatively evaluated. 3. Evaluation code for quantitative evaluation of seismic safety margin of systems, structures and components. As the example, quantitative evaluation of seismic safety margin of systems, structures and components were conducted for the reference plant. (author)

  3. Integrated safety assessment report: Integrated Safety Assessment Program: Millstone Nuclear Power Station, Unit 1 (Docket No. 50-245): Draft report

    International Nuclear Information System (INIS)

    1987-04-01

    The Integrated Safety Assessment Program (ISAP) was initiated in November 1984, by the US Nuclear Regulatory Commission to conduct integrated assessments for operating nuclear power reactors. The integrated assessment is conducted in a plant-specific basis to evaluate all licensing actions, licensee initiated plant improvements and selected unresolved generic/safety issues to establish implementation schedules for each item. In addition, procedures will be established to allow for a periodic updating of the schedules to account for licensing issues that arise in the future. This report documents the review of Millstone Nuclear Power Station, Unit No. 1, operated by Northeast Nuclear Energy Company (located in Waterford, Connecticut). Millstone Nuclear Power Station, Unit No. 1, is one of two plants being reviewed under the pilot program for ISAP. This report indicates how 85 topics selected for review were addressed. This report presents the staff's recommendations regarding the corrective actions to resolve the 85 topics and other actions to enhance plant safety. The report is being issued in draft form to obtain comments from the licensee, nuclear safety experts, and the Advisory Committee for Reactor Safeguards (ACRS). Once those comments have been resolved, the staff will present its positions, along with a long-term implementation schedule from the licensee, in the final version of this report

  4. PROPOSAL OF VOIVODESHIP ROAD SAFETY IMPROVEMENT PROGRAMME

    OpenAIRE

    Tomasz SZCZURASZEK; Jan KEMPA

    2016-01-01

    The article presents a proposal of the ‘GAMBIT KUJAWSKO-POMORSKI’ Road Safety Improvement Programme. The main idea of the Programme is to establish and initiate systems that will be responsible for the most important areas of activity within road safety, including road safety control, supervision, and management systems in the whole Voivodeship. In total, the creation and start of nine such systems has been proposed, namely: the Road Safety Management, the Integrated Road Rescue Service, the ...

  5. Correlation between safety climate and contractor safety assessment programs in construction.

    Science.gov (United States)

    Sparer, Emily H; Murphy, Lauren A; Taylor, Kathryn M; Dennerlein, Jack T

    2013-12-01

    Contractor safety assessment programs (CSAPs) measure safety performance by integrating multiple data sources together; however, the relationship between these measures of safety performance and safety climate within the construction industry is unknown. Four hundred and one construction workers employed by 68 companies on 26 sites and 11 safety managers employed by 11 companies completed brief surveys containing a nine-item safety climate scale developed for the construction industry. CSAP scores from ConstructSecure, Inc., an online CSAP database, classified these 68 companies as high or low scorers, with the median score of the sample population as the threshold. Spearman rank correlations evaluated the association between the CSAP score and the safety climate score at the individual level, as well as with various grouping methodologies. In addition, Spearman correlations evaluated the comparison between manager-assessed safety climate and worker-assessed safety climate. There were no statistically significant differences between safety climate scores reported by workers in the high and low CSAP groups. There were, at best, weak correlations between workers' safety climate scores and the company CSAP scores, with marginal statistical significance with two groupings of the data. There were also no significant differences between the manager-assessed safety climate and the worker-assessed safety climate scores. A CSAP safety performance score does not appear to capture safety climate, as measured in this study. The nature of safety climate in construction is complex, which may be reflective of the challenges in measuring safety climate within this industry. Am. J. Ind. Med. 56:1463-1472, 2013. © 2013 Wiley Periodicals, Inc. © 2013 Wiley Periodicals, Inc.

  6. Heat stress management program improving worker health and operational effectiveness: a case study.

    Science.gov (United States)

    Huss, Rosalyn G; Skelton, Scott B; Alvis, Kimberly L; Shane, Leigh A

    2013-03-01

    Heat stress monitoring is a vital component of an effective health and safety program when employees work in exceptionally warm environments. Workers at hazardous waste sites often wear personal protective equipment (PPE), which increases the body heat stress load. No specific Occupational Safety and Health Administration (OSHA) regulations address heat stress; however, OSHA does provide several guidance documents to assist employers in addressing this serious workplace health hazard. This article describes a heat stress and surveillance plan implemented at a hazardous waste site as part of the overall health and safety program. The PPE requirement for work at this site, coupled with extreme environmental temperatures, made heat stress a significant concern. Occupational health nurses and industrial hygienists developed a monitoring program for heat stress designed to prevent the occurrence of significant heat-related illness in site workers. The program included worker education on the signs of heat-related illness and continuous physiologic monitoring to detect early signs of heat-related health problems. Biological monitoring data were collected before workers entered the exclusion zone and on exiting the zone following decontamination. Sixty-six site workers were monitored throughout site remediation. More than 1,700 biological monitoring data points were recorded. Outcomes included improved worker health and safety, and increased operational effectiveness. Copyright 2013, SLACK Incorporated.

  7. A Pilot Program Integrating Hepatitis B Virus (HBV) Screening into an Outpatient Endoscopy Unit Improves HBV Screening Among an Ethnically Diverse Safety-Net Hospital.

    Science.gov (United States)

    Campbell, Brendan; Lopez, Aristeo; Liu, Benny; Bhuket, Taft; Wong, Robert J

    2018-01-01

    Safety-net hospitals are enriched in ethnic minorities and provide opportunities for high-impact hepatitis B virus (HBV) screening. We aim to evaluate the impact of a pilot program integrating HBV screening into outpatient endoscopy among urban safety-net populations. From July 2015 to May 2017, consecutive adults undergoing outpatient endoscopy were prospectively assessed for HBV screening eligibility using US Preventative Services Task Force guidelines. Rates of prior HBV screening were assessed, and those eligible but not screened were offered HBV testing. Multivariate logistic regression models evaluated predictors of test acceptance among eligible patients. Among 1557 patients (47.1% male, 69.4% foreign born), 65.1% were eligible for HBV screening, among which 24.5% received prior screening. In our pilot screening program in the endoscopy unit, 91.4% (n = 855) of eligible patients accepted HBV testing. However, only 55.3% (n = 415) of those that accepted actually completed HBV testing. While there was a trend toward higher rates of test acceptance among African-Americans compared to non-Hispanic whites (OR 3.31, 95% CI 0.96-11.38, p = 0.06), no other sex-specific or race/ethnicity-specific disparities in HBV test acceptance were observed. Among those who completed HBV testing, we identified 10 new patients with chronic HBV (2.4% prevalence). Only 24.5% of eligible patients received prior HBV screening among our cohort. Our pilot program integrating HBV screening into outpatient endoscopy successfully tested an additional 415 patients, improving overall HBV screening from 24.5 to 75.6%. Integrating HBV testing into non-traditional settings has potential to bridge the gap in HBV screening among safety-net systems.

  8. 41 CFR 128-1.8009 - Review of Seismic Safety Program.

    Science.gov (United States)

    2010-07-01

    ... 41 Public Contracts and Property Management 3 2010-07-01 2010-07-01 false Review of Seismic Safety Program. 128-1.8009 Section 128-1.8009 Public Contracts and Property Management Federal Property Management Regulations System (Continued) DEPARTMENT OF JUSTICE 1-INTRODUCTION 1.80-Seismic Safety Program...

  9. Current role of the USNRC safety research program in support of the regulatory process

    International Nuclear Information System (INIS)

    Levine, S.

    1979-01-01

    The current role of the USNRC's safety research program is shown. Some aspects of this role in the wake of the TMI accident are discused as well as some historical perspective on the development of USNRC's program, its relationship with the NRC mission, an overview of the program activities and some recent research results, and finally the impact of the TMI accident in clarifiying needs for expedited and new research activities, including the need for a greatly enhanced use of probabilistic analysis techniques to improve the coherence of its regulatory process. (author)

  10. Probabilistic studies for a safety assurance program

    International Nuclear Information System (INIS)

    Iyer, S.S.; Davis, J.F.

    1985-01-01

    The adequate supply of energy is always a matter of concern for any country. Nuclear power has played, and will continue to play an important role in supplying this energy. However, safety in nuclear power production is a fundamental prerequisite in fulfilling this role. This paper outlines a program to ensure safe operation of a nuclear power plant utilizing the Probabilistic Safety Studies

  11. Overview of the Nuclear Regulatory Commission's safety research program

    International Nuclear Information System (INIS)

    Beckjord, E.S.

    1989-01-01

    Accomplishments during 1988 of the Office of Nuclear Regulatory Research and the program of safety research are highlighted, and plans, expections, and needs of the next year and beyond are discussed. Topics discussed include: ECCS Appendix K Revision; pressurized thermal shock; NUREG-1150, or the PRA method performance document; resolution of station blackout; severe accident integration plan; nuclear safety research review committee; and program management

  12. An innovative program to increase safety culture for workers on a nuclear power plant

    International Nuclear Information System (INIS)

    Schryvers, Vincent

    2007-01-01

    Full text: To implement the WENRA harmonized guidelines and the IAEA reference guides, Electrabel has recently introduced a major training program for both its own staff and the contractors working on the sites of its Nuclear Power Plants. This training program stresses the importance of safety culture on both theoretical and practical level and is mostly focused on the behavioural aspects during activities performed at the site of a Nuclear Power Plant. Further emphasis is put on radiation protection, industrial safety, environmental protection and explosion prevention. The training scheme for both the staff of Electrabel and contractors typically contains a theoretical part introducing the basic concepts of nuclear safety and safety culture and a practical exercise in a simulated environment. A novel element in the training cycle is the use of a simulated environment, where the actual working conditions in the nuclear part of the installation are simulated. This mock-up installation enables the workers to train the nuclear safety constraints linked to the actual installation and to enhance safety culture by responding on simulated problems and changing conditions possibly being encountered during an intervention at the real working site. To analyze the behaviour of the future workers, the activities are videotaped and commented for further improvement. A refresh of the training courses is implemented after 3 years.Although this training program has only been in operation for just 6 months, the response of the contractors and the staff to this training has been enthusiastic. At this moment, more than 1.000 workers have successfully completed the training course. (author)

  13. Seismic safety margins research program. Phase I final report - Overview

    International Nuclear Information System (INIS)

    Smith, P.D.; Dong, R.G.; Bernreuter, D.L.; Bohn, M.P.; Chuang, T.Y.; Cummings, G.E.; Johnson, J.J.; Mensing, R.W.; Wells, J.E.

    1981-04-01

    The Seismic Safety Margins Research Program (SSMRP) is a multiyear, multiphase program whose overall objective is to develop improved methods for seismic safety assessments of nuclear power plants, using a probabilistic computational procedure. The program is being carried out at the Lawrence Livermore National Laboratory and is sponsored by the U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research. Phase I of the SSMRP was successfully completed in January 1981: A probabilistic computational procedure for the seismic risk assessment of nuclear power plants has been developed and demonstrated. The methodology is implemented by three computer programs: HAZARD, which assesses the seismic hazard at a given site, SMACS, which computes in-structure and subsystem seismic responses, and SEISIM, which calculates system failure probabilities and radioactive release probabilities, given (1) the response results of SMACS, (2) a set of event trees, (3) a family of fault trees, (4) a set of structural and component fragility descriptions, and (5) a curve describing the local seismic hazard. The practicality of this methodology was demonstrated by computing preliminary release probabilities for Unit 1 of the Zion Nuclear Power Plant north of Chicago, Illinois. Studies have begun aimed at quantifying the sources of uncertainty in these computations. Numerous side studies were undertaken to examine modeling alternatives, sources of error, and available analysis techniques. Extensive sets of data were amassed and evaluated as part of projects to establish seismic input parameters and to produce the fragility curves. (author)

  14. Guidance for implementing an environmental, safety, and health-assurance program. Volume 15. A model plan for line organization environmental, safety, and health-assurance programs

    Energy Technology Data Exchange (ETDEWEB)

    Ellingson, A.C.; Trauth, C.A. Jr.

    1982-01-01

    This is 1 of 15 documents designed to illustrate how an Environmental, Safety and Health (ES and H) Assurance Program may be implemented. The generic definition of ES and H Assurance Programs is given in a companion document entitled An Environmental, Safety and Health Assurance Program Standard. This particular document presents a model operational-level ES and H Assurance Program that may be used as a guide by an operational-level organization in developing its own plan. The model presented here reflects the guidance given in the total series of 15 documents.

  15. Canadian Nuclear Safety Commission's intern program

    International Nuclear Information System (INIS)

    Gilmour, P.E.

    2002-01-01

    The Intern Program was introduced at the Canadian Nuclear Safety Commission, Canada's Nuclear Regulator in response to the current competitive market for engineers and scientists and the CNSC's aging workforce. It is an entry level staff development program designed to recruit and train new engineering and science graduates to eventually regulate Canada's nuclear industry. The program provides meaningful work experience and exposes the interns to the general work activities of the Commission. It also provides them with a broad awareness of the regulatory issues in which the CNSC is involved. The intern program is a two-year program focusing on the operational areas and, more specifically, on the generalist functions of project officers. (author)

  16. Preventing hospital-acquired venous thromboembolism: Improving patient safety with interdisciplinary teamwork, quality improvement analytics, and data transparency.

    Science.gov (United States)

    Schleyer, Anneliese M; Robinson, Ellen; Dumitru, Roxana; Taylor, Mark; Hayes, Kimberly; Pergamit, Ronald; Beingessner, Daphne M; Zaros, Mark C; Cuschieri, Joseph

    2016-12-01

    Hospital-acquired venous thromboembolism (HA-VTE) is a potentially preventable cause of morbidity and mortality. Despite high rates of venous thromboembolism (VTE) prophylaxis in accordance with an institutional guideline, VTE remains the most common hospital-acquired condition in our institution. To improve the safety of all hospitalized patients, examine current VTE prevention practices, identify opportunities for improvement, and decrease rates of HA-VTE. Pre/post assessment. Urban academic tertiary referral center, level 1 trauma center, safety net hospital; all patients. We formed a multidisciplinary VTE task force to review all HA-VTE events, assess prevention practices relative to evidence-based institutional guidelines, and identify improvement opportunities. The task force developed an electronic tool to facilitate efficient VTE event review and designed decision-support and reporting tools, now integrated into the electronic health record, to bring optimal VTE prevention practices to the point of care. Performance is shared transparently across the institution. Harborview benchmarks process and outcome performance, including patient safety indicators and core measures, against hospitals nationally using Hospital Compare and Vizient data. Our program has resulted in >90% guideline-adherent VTE prevention and zero preventable HA-VTEs. Initiatives have resulted in a 15% decrease in HA-VTE and a 21% reduction in postoperative VTE. Keys to success include the multidisciplinary approach, clinical roles of task force members, senior leadership support, and use of quality improvement analytics for retrospective review, prospective reporting, and performance transparency. Ongoing task force collaboration with frontline providers is critical to sustained improvements. Journal of Hospital Medicine 2016;11:S38-S43. © 2016 Society of Hospital Medicine. © 2016 Society of Hospital Medicine.

  17. Improving the safety of LWR power plants. Final report

    International Nuclear Information System (INIS)

    1980-04-01

    This report documents the results of the Study to identify current, potential research issues and efforts for improving the safety of Light Water Reactor (LWR) power plants. This final report describes the work accomplished, the results obtained, the problem areas, and the recommended solutions. Specifically, for each of the issues identified in this report for improving the safety of LWR power plants, a description is provided in detail of the safety significance, the current status (including information sources, status of technical knowledge, problem solution and current activities), and the suggestions for further research and development. Further, the issues are ranked for action into high, medium, and low priority with respect to primarily (a) improved safety (e.g. potential reduction in public risk and occupational exposure), and secondly (b) reduction in safety-related costs

  18. RISMC advanced safety analysis project plan: FY2015 - FY2019. Light Water Reactor Sustainability Program

    International Nuclear Information System (INIS)

    Szilard, Ronaldo H; Smith, Curtis L; Youngblood, Robert

    2014-01-01

    In this report, the Advanced Safety Analysis Program (ASAP) objectives and value proposition is described. ASAP focuses on modernization of nuclear power safety analysis (tools, methods and data); implementing state-of-the-art modeling techniques (which include, for example, enabling incorporation of more detailed physics as they become available); taking advantage of modern computing hardware; and combining probabilistic and mechanistic analyses to enable a risk informed safety analysis process. The modernized tools will maintain the current high level of safety in our nuclear power plant fleet, while providing an improved understanding of safety margins and the critical parameters that affect them. Thus, the set of tools will provide information to inform decisions on plant modifications, refurbishments, and surveillance programs, while improving economics. The set of tools will also benefit the design of new reactors, enhancing safety per unit cost of a nuclear plant. As part of the discussion, we have identified three sets of stakeholders, the nuclear industry, the Department of Energy (DOE), and associated oversight organizations. These three groups would benefit from ASAP in different ways. For example, within the DOE complex, the possible applications that are seen include the safety of experimental reactors, facility life extension, safety-by-design in future generation advanced reactors, and managing security for the storage of nuclear material. This report provides information in five areas: (1) A value proposition (@@@why is this important?@@@) that will make the case for stakeholder's use of the ASAP research and development (R&D) products; (2) An identification of likely end users and pathway to adoption of enhanced tools by the end-users; (3) A proposed set of practical and achievable @@use case@@@ demonstrations; (4) A proposed plan to address ASAP verification and validation (V&V) needs; and (5) A proposed schedule for the multi-year ASAP.

  19. Health IT for Patient Safety and Improving the Safety of Health IT.

    Science.gov (United States)

    Magrabi, Farah; Ong, Mei-Sing; Coiera, Enrico

    2016-01-01

    Alongside their benefits health IT applications can pose new risks to patient safety. Problems with IT have been linked to many different types of clinical errors including prescribing and administration of medications; as well as wrong-patient, wrong-site errors, and delays in procedures. There is also growing concern about the risks of data breach and cyber-security. IT-related clinical errors have their origins in processes undertaken to design, build, implement and use software systems in a broader sociotechnical context. Safety can be improved with greater standardization of clinical software and by improving the quality of processes at different points in the technology life cycle, spanning design, build, implementation and use in clinical settings. Oversight processes can be set up at a regional or national level to ensure that clinical software systems meet specific standards. Certification and regulation are two mechanisms to improve oversight. In the absence of clear standards, guidelines are useful to promote safe design and implementation practices. Processes to identify and mitigate hazards can be formalised via a safety management system. Minimizing new patient safety risks is critical to realizing the benefits of IT.

  20. High-temperature gas-cooled reactor safety-reliability program plan

    Energy Technology Data Exchange (ETDEWEB)

    1981-03-01

    The purpose of this document is to present a safety plan as part of an overall program plan for the design and development of the High Temperature Gas-Cooled Reactor (HTGR). This plan is intended to establish a logical framework for identifying the technology necessary to demonstrate that the requisite degree of public risk safety can be achieved economically. This plan provides a coherent system safety approach together with goals and success criterion as part of a unifying strategy for licensing a lead reactor plant in the near term. It is intended to provide guidance to program participants involved in producing a technology base for the HTGR that is fully responsive to safety consideration in the design, evaluation, licensing, public acceptance, and economic optimization of reactor systems.

  1. Lessons learned from the safety assistance program for soviet-designed reactors

    International Nuclear Information System (INIS)

    Steinberg, N.

    1999-01-01

    Two examples of nuclear power situation were compared in this conference paper - the situation in Lithuania and the situation in the Ukraine. Based on the examples mentioned, author conclude that the effectiveness of the Multi-National Safety Assistance Program for Soviet -Designed Reactors in a given recipient country does not depend, in practice, on engineering issues. The principal aspects that determine this effectiveness are: first, the level of safety culture in the country, beginning at the Governmental level but also at the level of the senior managers of nuclear power. The other important factor which contributes is the availability of a well-developed national program for upgrading NPP safety. The economical well-being of nuclear power and of the country as a whole also has a major effect on the effectiveness of the western technical assistance programs that are trying to upgrade reactor safety in a particular recipient country. And finally, international community should have well coordinated and well substantiated safety assistance program for specific country

  2. Reactor safety research program. A description of current and planned reactor safety research sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research

    International Nuclear Information System (INIS)

    1975-06-01

    The reactor safety research program, sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, is described in terms of its program objectives, current status, and future plans. Elements of safety research work applicable to water reactors, fast reactors, and gas cooled reactors are presented together with brief descriptions of current and planned test facilities. (U.S.)

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

    Science.gov (United States)

    Sparer, Emily; Dennerlein, Jack

    2013-01-01

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

  4. Developing a disaster education program for community safety and resilience: The preliminary phase

    Science.gov (United States)

    Nifa, Faizatul Akmar Abdul; Abbas, Sharima Ruwaida; Lin, Chong Khai; Othman, Siti Norezam

    2017-10-01

    Resilience encompasses both the principles of preparedness and reaction within the dynamic systems and focuses responses on bridging the gap between pre-disaster activities and post-disaster intervention and among structural/non-structural mitigation. Central to this concept is the ability of the affected communities to recover their livelihood and inculcating necessary safety practices during the disaster and after the disaster strikes. While these ability and practices are important to improve the community safety and resilience, such factors will not be effective unless the awareness is present among the community. There have been studies conducted highlighting the role of education in providing awareness for disaster safety and resilience from a very young age. However for Malaysia, these area of research has not been fully explored and developed based on the specific situational and geographical factors of high-risk flood disaster locations. This paper explores the importance of disaster education program in Malaysia and develops into preliminary research project which primary aim is to design a flood disaster education pilot program in Kampung Karangan Primary School, Kelantan, Malaysia.

  5. MedWatch, the FDA Safety Information and Adverse Event Reporting Program

    Science.gov (United States)

    ... Reporting Program MedWatch: The FDA Safety Information and Adverse Event Reporting Program Share Tweet Linkedin Pin it ... approved information that can help patients avoid serious adverse events. Potential Signals of Serious Risks/New Safety ...

  6. Water reactor safety research program. A description of current and planned research

    International Nuclear Information System (INIS)

    1978-07-01

    The U.S. Nuclear Regulatory Commission (NRC) sponsors confirmatory safety research on lightwater reactors in support of the NRC regulatory program. The principal responsibility of the NRC, as implemented through its regulatory program is to ensure that public health, public safety, and the environment are adequately protected. The NRC performs this function by defining conditions for the use of nuclear power and by ensuring through technical review, audit, and follow-up that these conditions are met. The NRC research program provides technical information, independent of the nuclear industry, to aid in discharging these regulatory responsibilities. The objectives of NRC's research program are the following: (1) to maintain a confirmatory research program that supports assurance of public health and safety, and public confidence in the regulatory program, (2) to provide objectively evaluated safety data and analytical methods that meet the needs of regulatory activities, (3) to provide better quantified estimates of the margins of safety for reactor systems, fuel cycle facilities, and transportation systems, (4) to establish a broad and coherent exchange of safety research information with other Federal agencies, industry, and foreign organization. Current and planned research toward these goals is described

  7. Development of nuclear safety issues program

    Energy Technology Data Exchange (ETDEWEB)

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

    2006-12-15

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

  8. Development of nuclear safety issues program

    International Nuclear Information System (INIS)

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

    2006-12-01

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

  9. Applying health education theory to patient safety programs: three case studies.

    Science.gov (United States)

    Gilkey, Melissa B; Earp, Jo Anne L; French, Elizabeth A

    2008-04-01

    Program planning for patient safety is challenging because intervention-oriented surveillance data are not yet widely available to those working in this nascent field. Even so, health educators are uniquely positioned to contribute to patient safety intervention efforts because their theoretical training provides them with a guide for designing and implementing prevention programs. This article demonstrates the utility of applying health education concepts from three prominent patient safety campaigns, including the concepts of risk perception, community participation, and social marketing. The application of these theoretical concepts to patient safety programs suggests that health educators possess a knowledge base and skill set highly relevant to patient safety and that their perspective should be increasingly brought to bear on the design and evaluation of interventions that aim to protect patients from preventable medical error.

  10. Improving Safety through Human Factors Engineering.

    Science.gov (United States)

    Siewert, Bettina; Hochman, Mary G

    2015-10-01

    Human factors engineering (HFE) focuses on the design and analysis of interactive systems that involve people, technical equipment, and work environment. HFE is informed by knowledge of human characteristics. It complements existing patient safety efforts by specifically taking into consideration that, as humans, frontline staff will inevitably make mistakes. Therefore, the systems with which they interact should be designed for the anticipation and mitigation of human errors. The goal of HFE is to optimize the interaction of humans with their work environment and technical equipment to maximize safety and efficiency. Special safeguards include usability testing, standardization of processes, and use of checklists and forcing functions. However, the effectiveness of the safety program and resiliency of the organization depend on timely reporting of all safety events independent of patient harm, including perceived potential risks, bad outcomes that occur even when proper protocols have been followed, and episodes of "improvisation" when formal guidelines are found not to exist. Therefore, an institution must adopt a robust culture of safety, where the focus is shifted from blaming individuals for errors to preventing future errors, and where barriers to speaking up-including barriers introduced by steep authority gradients-are minimized. This requires creation of formal guidelines to address safety concerns, establishment of unified teams with open communication and shared responsibility for patient safety, and education of managers and senior physicians to perceive the reporting of safety concerns as a benefit rather than a threat. © RSNA, 2015.

  11. 42 CFR 9.10 - Occupational Health and Safety Program (OHSP) and biosafety requirements.

    Science.gov (United States)

    2010-10-01

    ... 42 Public Health 1 2010-10-01 2010-10-01 false Occupational Health and Safety Program (OHSP) and... SANCTUARY SYSTEM § 9.10 Occupational Health and Safety Program (OHSP) and biosafety requirements. (a) How are employee Occupational Health and Safety Program risks and concerns addressed? The sanctuary shall...

  12. 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...

  13. Review of the DOE Packaging and Transportation Safety Program

    International Nuclear Information System (INIS)

    Snyder, B.J.; Cece, J.M.

    1992-12-01

    This report documents the results of a year-long self-assessment of DOE-EH transportation and packaging safety activities. The self-assessment was initiated in September 1991 and concluded in August 1992. The self-assessment identified several significant issues, some of which have been resolved by EH. Also, improvements in the EH program were made during the course of the self-assessment. The report reflects the status of the EH transportation and packaging safety activities at the conclusion of the self-assessment. This report consists of several sections which discuss background, objectives and description of the review. Another section includes summary discussion and key conclusions. Appendix A, Issues, Observations and Recommendations, lists fifteen issues, including appropriate observations and recommendations. A Corrective Action Plan, which documents EH managements resolve to implement the agreed-upon recommendations, is included. The Corrective Action Plan reflects the status of completed and planned actions as of the date of the report

  14. FMCSA safety program effectiveness measurement : Roadside Intervention Effectiveness Model, fiscal year 2010 : [analysis brief].

    Science.gov (United States)

    2014-11-01

    Two of the Federal Motor Carrier Safety Administrations (FMCSAs) key safety programs are the Roadside Inspection and Traffic Enforcement programs. The Roadside Inspection program consists of roadside inspections performed by qualified safety in...

  15. Management Oversight and Risk Tree (MORT): a new system safety program

    International Nuclear Information System (INIS)

    Clark, J.L.

    Experiences of Aerojet Nuclear Company (ANC), in the development and implementation of a system safety program for ANC and for the Energy Research and Development Administration (ERDA) are discussed. Aerojet Nuclear is the prime operating contractor for ERDA, formerly AEC, at the Idaho National Engineering Laboratory. The ERDA sponsored ''MORT'' system safety program is described along with the process whereby formal system safety methods are incorporated into a stable organization. Specifically, a discussion is given of initial development of MORT; pilot program trials conducted at ANC; implementation methodology; and reaction of the ANC organization. (auth)

  16. FMCSA safety program effectiveness measurement : Roadside Intervention Effectiveness Model FY 2012, [analysis brief].

    Science.gov (United States)

    2016-02-01

    Roadside Inspection and Traffic Enforcement are two of : the Federal Motor Carrier Safety Administrations : (FMCSAs) key safety programs. The Roadside : Inspection Program consists of roadside inspections : performed by qualified safety inspect...

  17. Recipe Modification Improves Food Safety Practices during Cooking of Poultry.

    Science.gov (United States)

    Maughan, Curtis; Godwin, Sandria; Chambers, Delores; Chambers, Edgar

    2016-08-01

    Many consumers do not practice proper food safety behaviors when preparing food in the home. Several approaches have been taken to improve food safety behaviors among consumers, but there still is a deficit in actual practice of these behaviors. The objective of this study was to assess whether the introduction of food safety instructions in recipes for chicken breasts and ground turkey patties would improve consumers' food safety behaviors during preparation. In total, 155 consumers in two locations (Manhattan, KS, and Nashville, TN) were asked to prepare a baked chicken breast and a ground turkey patty following recipes that either did or did not contain food safety instructions. They were observed to track hand washing and thermometer use. Participants who received recipes with food safety instructions (n = 73) demonstrated significantly improved food safety preparation behaviors compared with those who did not have food safety instructions in the recipe (n = 82). In addition, the majority of consumers stated that they thought the recipes with instructions were easy to use and that they would be likely to use similar recipes at home. This study demonstrates that recipes could be a good source of food safety information for consumers and that they have the potential to improve behaviors to reduce foodborne illness.

  18. Improving commercial motor vehicle safety in Oregon.

    Science.gov (United States)

    2010-08-01

    This study addressed the primary functions of the Oregon Department of Transportations (ODOTs) Motor Carrier Safety Assistance Program (MCSAP), which is administered by the Motor Carrier Transportation Division (MCTD). The study first documente...

  19. Montana Highway Safety Improvement Program : an RSPCB Peer Exchange

    Science.gov (United States)

    2011-05-01

    This report provides a summary of a peer-to-peer (P2P) videoconference sponsored by the : Montana Department of Transportation (MDT) and the Federal Highway Administration : (FHWA) Office of Safety. The videoconference format provided a low-cost oppo...

  20. 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

  1. FMCSA safety program effectiveness measurement : roadside intervention effectiveness model FY 2011 : [analysis brief].

    Science.gov (United States)

    2015-06-01

    Roadside Inspection and Traffic Enforcement are two of the Federal Motor Carrier Safety Administrations (FMCSAs) key safety programs. The Roadside Inspection program consists of roadside inspections performed by qualified safety inspectors. The...

  2. Occupational Safety and Health Program at the West Valley Demonstration Project

    International Nuclear Information System (INIS)

    L. M. Calderon

    1999-01-01

    The West Valley Nuclear Services Co. LLC (WVNS) is committed to provide a safe, clean, working environment for employees, and to implement U.S. Department of Energy (DOE) requirements affecting worker safety. The West Valley Demonstration Project (WVDP) Occupational Safety and Health Program is designed to protect the safety, health, and well-being of WVDP employees by identifying, evaluating, and controlling biological, chemical, and physical hazards in the work place. Hazards are controlled within the requirements set forth in the reference section at the end of this report. It is the intent of the WVDP Occupational Safety and Health Program to assure that each employee is provided with a safe and healthy work environment. This report shows the logical path toward ensuring employee safety in planning work at the WVDP. In general, planning work to be performed safely includes: combining requirements from specific programs such as occupational safety, industrial hygiene, radiological control, nuclear safety, fire safety, environmental protection, etc.; including WVDP employees in the safety decision-making processes; pre-planning using safety support re-sources; and integrating the safety processes into the work instructions. Safety management principles help to define the path forward for the WVDP Occupational Safety and Health Program. Roles, responsibilities, and authority of personnel stem from these ideals. WVNS and its subcontractors are guided by the following fundamental safety management principles: ''Protection of the environment, workers, and the public is the highest priority. The safety and well-being of our employees, the public, and the environment must never be compromised in the aggressive pursuit of results and accomplishment of work product. A graded approach to environment, safety, and health in design, construction, operation, maintenance, and deactivation is incorporated to ensure the protection of the workers, the public, and the environment

  3. Does the accreditation of private dental practices work? Time to rethink how accreditation can improve patient safety.

    Science.gov (United States)

    Jean, Gillian

    2017-10-09

    Accreditation to demonstrate engagement with the National Safety and Quality Health Service Standards (Standards) is compulsory for most hospital and healthcare settings, but to date remains voluntary for private dental practices (PDPs). The regulatory framework governing the dental profession lacks a proactive element to drive improvements in quality and safety of care, and an accreditation scheme can strengthen existing regulation. The current model of accreditation operating in accordance with the Australian Health Service Safety and Quality Accreditation Scheme (Scheme) is based on the Standards, which were written for a hospital model of healthcare service. The majority of PDPs are small office-based businesses with clear leadership structure and employing six staff or fewer. The Scheme is overly bureaucratic given the simplicity of the PDP business model. This article considers whether accreditation has a proven track record of improving quality of service and offers opinions about how a more appropriate safety management program for PDPs may look. What is known about the topic? There has been minimal research about the impact of accreditation schemes in improving patient safety in PDP. What does this paper add? This paper proposes a redesign of the Scheme to make it more relevant to PDPs. The paper offers strategies to minimise duplication of purpose between accreditation and existing legislation; and to strengthen critical elements of accreditation to improve effects on patient safety. What are the implications for practitioners? A redesigned accreditation scheme will support dental practitioners to implement a quality assurance system with improved efficiency, reduced administrative burden, and optimised patient safety.

  4. Quality Improvement in Otolaryngology Residency: Survey of Program Directors.

    Science.gov (United States)

    Bowe, Sarah N

    2016-02-01

    The Clinical Learning Environment Review focuses on the responsibility of the sponsoring institution for quality and patient safety. Very little information is known regarding the status of quality improvement (QI) education during otolaryngology training. The purpose of this survey is to evaluate the extent of resident and faculty participation in QI and identify opportunities for both resident curriculum and faculty development. Cross-sectional survey A 15-item survey was distributed to all 106 otolaryngology program directors. The survey was developed after an informal review of the literature regarding education in QI and patient safety. Questions were directed at the format and content of the QI curriculum, as well as barriers to implementation. There was a 39% response rate. Ninety percent of responding program directors considered education in QI important or very important to a resident's future success. Only 23% of responding programs contained an educational curriculum in QI, and only 33% monitored residents' individual outcome measures. Barriers to implementation of a QI program included inadequate number of faculty with expertise in QI (75%) and competing resident educational demands (90%). Every program director considered morbidity and mortality conferences as an integral component in QI education. Program directors recognize the importance of QI in otolaryngology practice. Unfortunately, this survey identifies a distinct lack of resources in support of these educational goals. The results highlight the need to generate a comprehensive and stepwise approach to QI for faculty development and resident instruction. © American Academy of Otolaryngology—Head and Neck Surgery Foundation 2015.

  5. A Program Applying Professional Safety Basics in Construction Projects

    Directory of Open Access Journals (Sweden)

    Entisar Kadhim Rasheed

    2016-04-01

    Full Text Available When industrial and constructional renaissance started in the world, the great interest was going on towards the equipment’s, which was the first mean for production. After industry was settled the interest was going on towards the men ship which manpower on which the production depends. It was approved that it represents the basic part in all of the processes and the protection of those individuals against dangers of these equipment’s, industry and its accidents was the basic things which was studied in many researches until it crystallized in general principles for all industries and other take care in each industry. The professional safety is concerned as restrict which aims to take care of humanitarian and material principles also to raise the production of these principles, in the aspect of safety, health and providing the suitable healthy condition to the worker so he can feel safety, confidence and sociological settle, this will increase the production. So In order to maintain the manpower of business risks and to enable them to fulfill their role better to increase production and improve the quality and maintain the machine and supporting the national economy and keep pace with industrial developments and technological came the idea of research to focus on the importance of studying the subject of occupational safety by conducting a field survey to see the reality of professional safety in the relevant departments and work sites and through a questionnaire on the subject and conduct personal interviews with those concerned in this area and to prepare a program for the application of professional safety for each resource (labor, machines, materials, money in construction sites and departments concerned.

  6. Seismic Safety Margins Research Program: Phase II program plan (FY 83-FY 84)

    International Nuclear Information System (INIS)

    Bohn, M.P.; Bernreuter, D.L.; Cover, L.E.; Johnson, J.J.; Shieh, L.C.; Shukla, S.N.; Wells, J.E.

    1982-01-01

    The Seismic Safety Margins Research Program (SSMRP) is an NRC-funded, multiyear program conducted by Lawrence Livermore National Laboratory (LLNL). Its goal is to develop a complete, fully coupled analysis procedure (including methods and computer codes) for estimating the risk of an earthquake-caused radioactive release from a commercial nuclear power plant. The analysis procedure is based upon a state-of-the-art evaluation of the current seismic analysis and design process and explicitly includes the uncertainties inherent in such a process. The results will be used to improve seismic licensing requirements for nuclear power plants. As currently planned, the SSMRP will be completed in September, 1984. This document presents the program plan for work to be done during the remainder of the program. In Phase I of the SSMRP, the necessary tools (both computer codes and data bases) for performing a detailed seismic risk analysis were identified and developed. Demonstration calculations were performed on the Zion Nuclear Power Plant. In the remainder of the program (Phase II) work will be concentrated on developing a simplified SSMRP methodology for routine probabilistic risk assessments, quantitative validation of the tools developed and application of the simplified methodology to a Boiling Water Reactor. (The Zion plant is a pressurized water reactor.) In addition, considerable effort will be devoted to making the codes and data bases easily accessible to the public

  7. The Impact of a Patient Safety Program on Medical Error Reporting

    Science.gov (United States)

    2005-05-01

    307 The Impact of a Patient Safety Program on Medical Error Reporting Donald R. Woolever Abstract Background: In response to the occurrence of...a sentinel event—a medical error with serious consequences—Eglin U.S. Air Force (USAF) Regional Hospital developed and implemented a patient safety...communication, teamwork, and reporting. Objective: To determine the impact of a patient safety program on patterns of medical error reporting. Methods: This

  8. Improvement of the Patient Safety Culture in the Primary Health Care Corporation - Qatar.

    Science.gov (United States)

    El Zoghbi, Mohamad; Farooq, Saad; Abulaban, Ali; Taha, Heba; Ajanaz, Sajna; Aljasmi, Jawaher; Ahmad, Shakil; Said, Hana

    2018-04-17

    Primary Health Care Corporation (PHCC) is the public primary health care provider in Qatar. Having a patient safety culture (PSC) is the keystone to enabling a continuous process to improve the quality of services and to reduce errors. The objective of this study was to assess the impact of accreditation, quality improvement trainings, and patient safety (PS) trainings on the improvement of the PSC at the PHCC in Qatar. The Medical Office Survey on Patient Safety Culture from the Agency for Healthcare Research and Quality was used in 2012 and 2015 to assess the culture of PS and health care quality in the 21 health centers. The results of the two surveys were compared using the χ test. A P value of less than 0.05 was considered significant. Out of 2689 staff working in the 21 health centers, 1810 (67.3%) completed the survey in 2012, and 2616 (70.0%) of 3735 completed the survey in 2015. The comparison between 2012 and 2015 survey's results showed a statistically significant improvement for all the 10 dimensions (P < 0.05). Although a statistically significant difference was observed between 2012 and 2015 results for work pressure and pace, three of the four questions of the work pressure and pace dimension presented nonsignificant differences. The survey was a good tool to raise awareness on PS and quality issues at PHCC. There is evidence that the implementation of accreditation program, the quality improvement trainings, and PS trainings helped the organization improve its PS culture.

  9. Sociological refigurations of patient safety; ontologies of improvement and 'acting with' quality collaboratives in healthcare.

    Science.gov (United States)

    Zuiderent-Jerak, Teun; Strating, Mathilde; Nieboer, Anna; Bal, Roland

    2009-12-01

    The increasing focus on patient safety in the field of health policy is accompanied by research programs that articulate the role of the social sciences as one of contributing to enhancing safety in healthcare. Through these programs, new approaches to studying safety are facing a narrow definition of 'usefulness' in which researchers are to discover the factors that support or hamper the implementation of existing policy agendas. This is unfortunate since such claims for useful involvement in predefined policy agendas may undo one of the strongest assets of good social science research: the capacity to complexify the taken-for-granted conceptualizations of the object of study. As an alternative to this definition of 'usefulness', this article proposes a focus on multiple ontologies in the making when studying patient safety. Through such a focus, the role of social scientists becomes the involvement in refiguring the problem space of patient safety, the relations between research subjects and objects, and the existing policy agendas. This role gives medical sociologists the opportunity to focus on the question of which practices of 'effective care' are being enacted through different approaches for dealing with patient safety and what their consequences are for the care practices under study. In order to explore these questions, this article draws on empirical material from an ongoing evaluation of a large quality improvement collaborative for the care sectors in the Netherlands. It addresses how issues like 'effectiveness' and 'client participation' are at present articulated in this collaborative and shows that alternative figurations of these notions dissolve many 'implementation problems' presently experienced. Further it analyzes how such a focus of medical sociology on multiple ontologies engenders new potential for exploring particular spaces for 'acting with' quality improvement agents.

  10. SSI sensitivity studies and model improvements for the US NRC Seismic Safety Margins Research Program. Rev. 1

    International Nuclear Information System (INIS)

    Johnson, J.J.; Maslenikov, O.R.; Benda, B.J.

    1984-10-01

    The Seismic Safety Margins Research Program (SSMRP) is a US NRC-funded program conducted by Lawrence Livermore National Laboratory. Its goal is to develop a complete fully coupled analysis procedure for estimating the risk of an earthquake-induced radioactive release from a commercial nuclear power plant. In Phase II of the SSMRP, the methodology was applied to the Zion nuclear power plant. Three topics in the SSI analysis of Zion were investigated and reported here - flexible foundation modeling, structure-to-structure interaction, and basemat uplift. The results of these investigations were incorporated in the SSMRP seismic risk analysis. 14 references, 51 figures, 13 tables

  11. The role of Aboriginal family workers in delivering a child safety focused home visiting program for Aboriginal families in an urban region of NSW.

    Science.gov (United States)

    Clapham, Kathleen; Bennett-Brook, Keziah; Hunter, Kate

    2018-05-09

    Aboriginal Australian children experience higher rates of injury than other Australian children. However few culturally acceptable programs have been developed or evaluated. The Illawarra Aboriginal Medical Service (IAMS) developed the Safe Homes Safe Kids program as an injury prevention program targeting disadvantaged Aboriginal families with children aged 0-5 in an urban region of NSW. Delivered by Aboriginal Family Workers the program aims to reduce childhood injury by raising awareness of safety in the home. A program evaluation was conducted to determine the effectiveness of the home visiting model as an injury prevention program. This paper reports on the qualitative interviews which explored the ways in which clients, IAMS staff, and external service providers experienced the program and assessed its delivery by the Aboriginal Family Workers. A qualitative program evaluation was conducted between January 2014 and June 2015. We report here on the semi-structured interviews undertaken with 34 individuals. The results show increased client engagement in the program; improved child safety knowledge and skills; increased access to services; improved attitudes to home and community safety; and changes in the home safety environment. Safe Homes Safe Kids provides a culturally appropriate child safety program delivered by Aboriginal Family Workers to vulnerable families. Clients, IAMS staff, and external service were satisfied with the family workers' delivery of the program and the holistic model of service provision. SO WHAT?: This promising program could be replicated in other Aboriginal health services to address unintentional injury to vulnerable Aboriginal children. This article is protected by copyright. All rights reserved. This article is protected by copyright. All rights reserved.

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

    International Nuclear Information System (INIS)

    2008-01-01

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

  13. Development of a Food Safety and Nutrition Education Program for Adolescents by Applying Social Cognitive Theory.

    Science.gov (United States)

    Lee, Jounghee; Jeong, Soyeon; Ko, Gyeongah; Park, Hyunshin; Ko, Youngsook

    2016-08-01

    The purpose of this study was to develop an educational model regarding food safety and nutrition. In particular, we aimed to develop educational materials, such as middle- and high-school textbooks, a teacher's guidebook, and school posters, by applying social cognitive theory. To develop a food safety and nutrition education program, we took into account diverse factors influencing an individual's behavior, such as personal, behavioral, and environmental factors, based on social cognitive theory. We also conducted a pilot study of the educational materials targeting middle-school students (n = 26), high-school students (n = 24), and dietitians (n = 13) regarding comprehension level, content, design, and quality by employing the 5-point Likert scale in May 2016. The food safety and nutrition education program covered six themes: (1) caffeine; (2) food additives; (3) foodborne illness; (4) nutrition and meal planning; (5) obesity and eating disorders; and (6) nutrition labeling. Each class activity was created to improve self-efficacy by setting one's own goal and to increase self-control by monitoring one's dietary intake. We also considered environmental factors by creating school posters and leaflets to educate teachers and parents. The overall evaluation score for the textbook was 4.0 points among middle- and high-school students, and 4.5 points among dietitians. This study provides a useful program model that could serve as a guide to develop educational materials for nutrition-related subjects in the curriculum. This program model was created to increase awareness of nutrition problems and self-efficacy. This program also helped to improve nutrition management skills and to promote a healthy eating environment in middle- and high-school students.

  14. Randomized controlled trial to determine the effectiveness of an interactive multimedia food safety education program for clients of the special supplemental nutrition program for women, infants, and children.

    Science.gov (United States)

    Trepka, Mary Jo; Newman, Frederick L; Davila, Evelyn P; Matthew, Karen J; Dixon, Zisca; Huffman, Fatma G

    2008-06-01

    Pregnant women and the very young are among those most susceptible to foodborne infections and at high risk of a severe outcome from foodborne infections. To determine if interactive multimedia is a more effective method than pamphlets for delivering food safety education to Special Supplemental Nutrition Program for Women, Infants, and Children (WIC) clients. A randomized controlled trial of WIC clients was conducted. Self-reported food safety practices were compared between pre- and postintervention questionnaires completed >or=2 months after the intervention. Pregnant WIC clients or female caregivers (usually mothers) of WIC clients who were 18 years of age or older and able to speak and read English were recruited from an inner-city WIC clinic. Participants were randomized to receive food safety pamphlets or complete an interactive multimedia food safety education program on a computer kiosk. Change from pre- to postintervention food safety scores. A mean food safety score was determined for each participant for the pre- and postintervention questionnaires. The scores were used in a two-group repeated measures analysis of variance. Of the 394 participants, 255 (64.7%) completed the postintervention questionnaire. Satisfaction with the program was high especially among those with no education beyond high school. When considering a repeated measures analysis of variance model with the two fixed between-subject effects of group and age, a larger improvement in score in the interactive multimedia group than in the pamphlet group (P=0.005) was found, but the size of the group effect was small (partial eta(2)=0.033). Women aged 35 years or older in the interactive multimedia group had the largest increase in score. The interactive multimedia was well-accepted and resulted in improved self-reported food safety practices, suggesting that interactive multimedia is an effective option for food safety education in WIC clinics.

  15. Commercial Crew Program Crew Safety Strategy

    Science.gov (United States)

    Vassberg, Nathan; Stover, Billy

    2015-01-01

    The purpose of this presentation is to explain to our international partners (ESA and JAXA) how NASA is implementing crew safety onto our commercial partners under the Commercial Crew Program. It will show them the overall strategy of 1) how crew safety boundaries have been established; 2) how Human Rating requirements have been flown down into programmatic requirements and over into contracts and partner requirements; 3) how CCP SMA has assessed CCP Certification and CoFR strategies against Shuttle baselines; 4) Discuss how Risk Based Assessment (RBA) and Shared Assurance is used to accomplish these strategies.

  16. 78 FR 14912 - International Aviation Safety Assessment (IASA) Program Change

    Science.gov (United States)

    2013-03-08

    ... Aviation Safety Assessment (IASA) Program Change AGENCY: Federal Aviation Administration (FAA), DOT. ACTION..., into the U.S., or codeshare with a U.S. air carrier, complies with international aviation safety... subject to that country's aviation safety oversight can serve the United States using its own aircraft or...

  17. Identification and characterization of passive safety system and inherent safety feature building blocks for advanced light-water reactors

    International Nuclear Information System (INIS)

    Forsberg, C.W.

    1989-01-01

    Oak Ridge National Laboratory (ORNL) is investigating passive and inherent safety options for Advanced Light-Water Reactors (ALWRs). A major activity in 1989 includes identification and characterization of passive safety system and inherent safety feature building blocks, both existing and proposed, for ALWRs. Preliminary results of this work are reported herein. This activity is part of a larger effort by the US Department of Energy, reactor vendors, utilities, and others in the United States to develop improved LWRs. The Advanced Boiling Water Reactor (ABWR) program and the Advanced Pressurized Water Reactor (APWR) program have as goals improved, commercially available LWRs in the early 1990s. The Advanced Simplified Boiling Water Reactor (ASBWR) program and the AP-600 program are developing more advanced reactors with increased use of passive safety systems. It is planned that these reactors will become commercially available in the mid 1990s. The ORNL program is an exploratory research program for LWRs beyond the year 2000. Desired long-term goals for such reactors include: (1) use of only passive and inherent safety, (2) foolproof against operator errors, (3) malevolence resistance against internal sabotage and external assault and (4) walkaway safety. The acronym ''PRIME'' [Passive safety, Resilient operation, Inherent safety, Malevolence resistance, and Extended (walkaway) safety] is used to summarize these desired characteristics. Existing passive and inherent safety options are discussed in this document

  18. Experience of safety and performance improvement for fuel handling equipment

    International Nuclear Information System (INIS)

    Gyoon Chang, Sang; Hee Lee, Dae

    2014-01-01

    The purpose of this study is to provide experience of safety and performance improvement of fuel handling equipment for nuclear power plants in Korea. The fuel handling equipment, which is used as an important part of critical processes during the refueling outage, has been improved to enhance safety and to optimize fuel handling procedures. Results of data measured during the fuel reloading are incorporated into design changes. The safety and performance improvement for fuel handling equipment could be achieved by simply modifying the components and improving the interlock system. The experience provided in this study can be useful lessons for further improvement of the fuel handling equipment. (authors)

  19. 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.

  20. Organizational factors influencing improvements in safety

    International Nuclear Information System (INIS)

    Marcus, A.; Nichols, M.L.; Olson, J.; Osborn, R.; Thurber, J.

    1992-01-01

    Research reported here seeks to identify the key organizational factors that influence safety-related performance indicators in nuclear power plants over time. It builds upon organizational factors identified in NUREG/CR-5437, and begins to develop a theory of safety-related performance and performance improvement based on economic and behavioral theories of the firm. Central to the theory are concepts of past performance, problem recognition, resource availability, resource allocation, and business strategies that focus attention. Variables which reflect those concepts are combined in statistical models and tested for their ability to explain scrams, safety system actuations, significant events, safety system failures, radiation exposure, and critical hours. Results show the performance indicators differ with respect to the sets of variables which serve as the best predictors of future performance, and past performance is the most consistent predictor of future performance

  1. Can we improve patient safety?

    Science.gov (United States)

    Corbally, Martin Thomas

    2014-01-01

    Despite greater awareness of patient safety issues especially in the operating room and the widespread implementation of surgical time out World Health Organization (WHO), errors, especially wrong site surgery, continue. Most such errors are due to lapses in communication where decision makers fail to consult or confirm operative findings but worryingly where parental concerns over the planned procedure are ignored or not followed through. The WHO Surgical Pause/Time Out aims to capture these errors and prevent them, but the combination of human error and complex hospital environments can overwhelm even robust safety structures and simple common sense. Parents are the ultimate repository of information on their child's condition and planned surgery but are traditionally excluded from the process of Surgical Pause and Time Out, perhaps to avoid additional stress. In addition, surgeons, like pilots, are subject to the phenomenon of "plan-continue-fail" with potentially disastrous outcomes. If we wish to improve patient safety during surgery and avoid wrong site errors then we must include parents in the Surgical Pause/Time Out. A recent pilot study has shown that neither staff nor parents found it added to their stress, but, moreover, 100% of parents considered that it should be a mandatory component of the Surgical Pause nor does it add to the stress of surgery. Surgeons should be required to confirm that the planned procedure is in keeping with the operative findings especially in extirpative surgery and this "step back" should be incorporated into the standard Surgical Pause. It is clear that we must improve patient safety further and these simple measures should add to that potential.

  2. Applying principles from safety science to improve child protection.

    Science.gov (United States)

    Cull, Michael J; Rzepnicki, Tina L; O'Day, Kathryn; Epstein, Richard A

    2013-01-01

    Child Protective Services Agencies (CPSAs) share many characteristics with other organizations operating in high-risk, high-profile industries. Over the past 50 years, industries as diverse as aviation, nuclear power, and healthcare have applied principles from safety science to improve practice. The current paper describes the rationale, characteristics, and challenges of applying concepts from the safety culture literature to CPSAs. Preliminary efforts to apply key principles aimed at improving child safety and well-being in two states are also presented.

  3. 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

  4. The experiences of research reactor accident to safety improvement

    International Nuclear Information System (INIS)

    Wiranto, S.

    1999-01-01

    The safety of reactor operation is the main factor in order that the nuclear technology development program can be held according the expected target. Several experience with research reactor incidents must be learned and understood by the nuclear program personnel, especially for operators and supervisors of RSG-GA. Siwabessy. From the incident experience of research reactor in the world, which mentioned in the book 'Experience with research reactor incidents' by IAEA, 1995, was concluded that the main cause of research reactor accidents is understandless about the safety culture by the nuclear installation personnel. With learn, understand and compare between this experiences and the condition of RSG GA Siwabessy is expended the operators and supervisors more attention about the safety culture, so that RSG GA Siwabessy can be operated successfull, safely according the expected target

  5. Program of nuclear criticality safety experiment at JAERI

    International Nuclear Information System (INIS)

    Kobayashi, Iwao; Tachimori, Shoichi; Takeshita, Isao; Suzaki, Takenori; Ohnishi, Nobuaki

    1983-11-01

    JAERI is promoting the nuclear criticality safety research program, in which a new facility for criticality safety experiments (Criticality Safety Experimental Facility : CSEF) is to be built for the experiments with solution fuel. One of the experimental researches is to measure, collect and evaluate the experimental data needed for evaluation of criticality safety of the nuclear fuel cycle facilities. Another research area is a study of the phenomena themselves which are incidental to postulated critical accidents. Investigation of the scale and characteristics of the influences caused by the accident is also included in this research. The result of the conceptual design of CSEF is summarized in this report. (author)

  6. Evaluation of a five-year Bloomberg Global Road Safety Program in Turkey.

    Science.gov (United States)

    Gupta, S; Hoe, C; Özkan, T; Lajunen, T J; Vursavas, F; Sener, S; Hyder, A A

    2017-03-01

    Turkey was included in the Bloomberg Philanthropies funded Global Road Safety Program (2010-14) with Ankara and Afyonkarahisar (Afyon) selected for interventions to manage speed and encourage seat-belt use. The objectives of this study are to present the monitoring and evaluation findings of seat-belt use and speed in Afyon and Ankara over the five years and to assess overall impact of the program on road traffic injury, and death rates in Turkey. Quasi-experimental before after without comparison. In collaboration with the Middle East Technical University, roadside observations and interviews were coupled with secondary data to monitor changes in risk factors and outcomes at the two intervention sites. The percentage of seat-belt use among drivers and front-seat passengers in Afyon and Ankara increased significantly between 2010 and 2014 with increased self-reported use and preceded by an increase in tickets (fines) for not using seat belts. There were uneven improvements in speed reduction. In Afyon, the average speed increased significantly from 46.3 km/h in 2012 to about 52.7 km/h in 2014 on roads where the speed limits were 50 km/h. In Ankara, the average speed remained less than 55 km/h during the program period (range: 50-54 km/h; P < 0.005) for roads where the speed limits were 50 km/h; however, the average speed on roads with speed limits of 70 km/h decreased significantly from 80.6 km/h in 2012 to 68.44 km/h in 2014 (P < 0.005). The program contributed to increase in seat-belt use in Afyon and Ankara and by drawing political attention to the issue can contribute to improvements in road safety. We are optimistic that the visible motivation within Turkey to substantially reduce road traffic injuries will lead to increased program implementation matched with a robust evaluation program, with suitable controls. Copyright © 2017 The Authors. Published by Elsevier Ltd.. All rights reserved.

  7. Effectiveness of the IMPACT:Ability program to improve safety and self-advocacy skills in high school students with disabilities.

    Science.gov (United States)

    Dryden, Eileen M; Desmarais, Jeffery; Arsenault, Lisa

    2014-12-01

    Individuals with disabilities experience higher rates of abuse than the nondisabled. Few evidence-based prevention interventions have been published despite a need for such work. This study evaluated Ability, a safety and self-advocacy training for individuals with cognitive and/or physical disabilities. A quasi-experimental design was used to assess change in safety and self-advocacy knowledge, confidence, and behaviors among special education high school students in Boston, MA. Instruments were interviewer-administered at 3 time points. Analysis of covariance (ANCOVA) was used to compare change between the intervention (N = 21) and wait-list (N = 36) groups. Repeated measures analysis was used to test change in the complete sample (N = 57). Students were diverse (58% males, 82% nonwhite) with a range of disabilities. Significantly greater improvement in key outcomes, including safety and self-advocacy knowledge, confidence, and behavior, were observed in intervention students compared to the wait-list group. Results in the complete sample showed evidence of further improvements in students' sense of safety and general self-efficacy. These findings are encouraging given the effects were demonstrated in a heterogeneous urban population. Ability may be an effective safety and self-advocacy training for students with disabilities. Further research will be required to determine effectiveness within particular subpopulations of students. © 2014, American School Health Association.

  8. Sanitation & Safety for Child Feeding Programs.

    Science.gov (United States)

    Florida State Dept. of Health and Rehabilitative Services, Tallahassee.

    In the interest of promoting good health, sanitation, and safety practices in the operation of child feeding programs, this bulletin discusses practices in personal grooming and wearing apparel; the purchasing, storage, handling, and serving of food; sanitizing equipment and utensils; procedures to follow in case of a food poisoning outbreak; some…

  9. Safety Critical Java for Robotics Programming

    DEFF Research Database (Denmark)

    Thomsen, Bent; Luckow, Kasper Søe; Bøgholm, Thomas

    2015-01-01

    This paper introduces Safety Critical Java (SCJ) and argues its readiness for robotics programming. We give an overview of the work done at Aalborg University and elsewhere on SCJl, some of its implementations in the form of the JOP, FijiVM and HVM and some of the tools, especially WCA, Teta...

  10. Multidisciplinary training program to create new breed of radiation monitor: the health and safety technician

    International Nuclear Information System (INIS)

    Vance, W.F.

    1979-01-01

    A multidiscipline training program established to create a new monitor, theHealth and Safety Technician, is described. The training program includes instruction in fire safety, explosives safety, industrial hygiene, industrial safety, health physics, and general safety practices

  11. Environment Health & Safety Research Program. Organization and 1979-1980 Publications

    Energy Technology Data Exchange (ETDEWEB)

    None

    1981-01-01

    This document was prepared to assist readers in understanding the organization of Pacific Northwest Laboratory, and the organization and functions of the Environment, Health and Safety Research Program Office. Telephone numbers of the principal management staff are provided. Also included is a list of 1979 and 1980 publications reporting on work performed in the Environment, Health and Safety Research Program, as well as a list of papers submitted for publication.

  12. Interface management: Effective communication to improve process safety

    International Nuclear Information System (INIS)

    Kelly, Brian; Berger, Scott

    2006-01-01

    Failure to successfully communicate maintenance activities, abnormal conditions, emergency response procedures, process hazards, and hundreds of other items of critical information can lead to disaster, regardless of the thoroughness of the process safety management system. Therefore, a well-functioning process safety program depends on maintaining successful communication interfaces between each involved employee or stakeholder and the many other employees or stakeholders that person must interact with. The authors discuss a process to identify the critical 'Interfaces' between the many participants in a process safety management system, and then to establish a protocol for each critical interface

  13. Fusion-Reactor-Safety Research Program. Annual report, Fiscal Year 1981

    International Nuclear Information System (INIS)

    Crocker, J.G.; Cohen, S.

    1982-07-01

    The report contains four sections: Outside Contracts includes the continuation of the General Atomic Co. low-activation materials safety study, water-cooled transport activation products study by Pacific Northwest Laboratory (PNL), studies of superconducting magnet safety conducted by Argonne National Laboratory (ANL) coupled with a new experimental superconducting magnet study program by Massachusetts Institute of Technology (MIT) to verify analytical work, a continuation of safety methodology work by MIT, portions of papers on lithium safety studies conducted at Hanford Engineering Development Laboratory (HEDL), and a new program to study tritium gas conversion to tritiated water at Oak Ridge National Laboratory (ORNL). The section EG and G idaho, Inc., Activities at INEL includes adaptations of papers of ongoing work in transient code development, tritium systems risk assessment, heat transfer activities, and a summary of a workshop on safety in design. A List of Publications and Proposed FY-82 Activities are also presented

  14. Ostomy Home Skills Program

    Medline Plus

    Full Text Available ... Quality Standard Optimal Resources for Surgical Quality and Safety Inspiring Quality Initiative Resources Continuous Quality Improvement ACS Clinical Scholars in Residence AHRQ Safety Program for ISCR AHRQ Safety Program for ISCR ...

  15. The role of individual diligence in improving safety.

    Science.gov (United States)

    Corbett, Angus; Travaglia, Jo; Braithwaite, Jeffrey

    2011-01-01

    This paper aims to be a theoretical examination of the role of individuals in sponsoring and facilitating effective, systemic change in organisations. Using reports of a number of high-profile initiatives to improve patient safety, it seeks to analyse the role of individual health care professionals in developing and facilitating new systems of care that improve safety and quality. The paper uses recent work in sociology that is concerned with the phenomenon of "sociological citizenship". The authors test whether successful initiators of change in health care can be described as sociological citizens. This notion of sociological citizens is applied to a number of highly successful initiatives to improve safety and quality to extrapolate the factors associated with individual clinician leadership, which may have affected the success of such endeavours. In each of the examples analysed the initiators of change can be characterised as sociological citizens. In reviewing the roles of these charismatic individuals it is evident that they see the relational interdependence between the individuals and organisations and that they use this information to achieve both professional and organisational objectives. The paper uses a case study method to investigate the usefulness of the role of sociological citizenship in interventions that aim to improve patient safety. The paper reviews the key concepts and uses of the concept of sociological citizenship to produce a framework against which the case studies were assessed. The authors suggest that a goal of policy for improving patient safety should be directed to the problem of how hospitals and health care organisations can create the conditions for encouraging the individual diligence and care that is needed to support reliable, safe health care practices. Improving the safety and quality of health care is an important public health initiative. It has also proven to be difficult to achieve sustained reductions in the harm

  16. Patient handover in orthopaedics, improving safety using Information Technology.

    Science.gov (United States)

    Pearkes, Tim

    2015-01-01

    Good inpatient handover ensures patient safety and continuity of care. An adjunct to this is the patient list which is routinely managed by junior doctors. These lists are routinely created and managed within Microsoft Excel or Word. Following the merger of two orthopaedic departments into a single service in a new hospital, it was felt that a number of safety issues within the handover process needed to be addressed. This quality improvement project addressed these issues through the creation and implementation of a new patient database which spanned the department, allowing trouble free, safe, and comprehensive handover. Feedback demonstrated an improved user experience, greater reliability, continuity within the lists and a subsequent improvement in patient safety.

  17. NASA's aviation safety research and technology program

    Science.gov (United States)

    Fichtl, G. H.

    1977-01-01

    Aviation safety is challenged by the practical necessity of compromising inherent factors of design, environment, and operation. If accidents are to be avoided these factors must be controlled to a degree not often required by other transport modes. The operational problems which challenge safety seem to occur most often in the interfaces within and between the design, the environment, and operations where mismatches occur due to ignorance or lack of sufficient understanding of these interactions. Under this report the following topics are summarized: (1) The nature of operating problems, (2) NASA aviation safety research, (3) clear air turbulence characterization and prediction, (4) CAT detection, (5) Measurement of Atmospheric Turbulence (MAT) Program, (6) Lightning, (7) Thunderstorm gust fronts, (8) Aircraft ground operating problems, (9) Aircraft fire technology, (10) Crashworthiness research, (11) Aircraft wake vortex hazard research, and (12) Aviation safety reporting system.

  18. Flooding Experiments and Modeling for Improved Reactor Safety

    International Nuclear Information System (INIS)

    Solmos, M.; Hogan, K.J.; VIerow, K.

    2008-01-01

    Countercurrent two-phase flow and 'flooding' phenomena in light water reactor systems are being investigated experimentally and analytically to improve reactor safety of current and future reactors. The aspects that will be better clarified are the effects of condensation and tube inclination on flooding in large diameter tubes. The current project aims to improve the level of understanding of flooding mechanisms and to develop an analysis model for more accurate evaluations of flooding in the pressurizer surge line of a Pressurized Water Reactor (PWR). Interest in flooding has recently increased because Countercurrent Flow Limitation (CCFL) in the AP600 pressurizer surge line can affect the vessel refill rate following a small break LOCA and because analysis of hypothetical severe accidents with the current flooding models in reactor safety codes shows that these models represent the largest uncertainty in analysis of steam generator tube creep rupture. During a hypothetical station blackout without auxiliary feedwater recovery, should the hot leg become voided, the pressurizer liquid will drain to the hot leg and flooding may occur in the surge line. The flooding model heavily influences the pressurizer emptying rate and the potential for surge line structural failure due to overheating and creep rupture. The air-water test results in vertical tubes are presented in this paper along with a semi-empirical correlation for the onset of flooding. The unique aspects of the study include careful experimentation on large-diameter tubes and an integrated program in which air-water testing provides benchmark knowledge and visualization data from which to conduct steam-water testing

  19. Safety improvement and results of commissioning of Mochovce NPP WWER 440/213

    International Nuclear Information System (INIS)

    Lipar, M.

    1998-01-01

    Mochovce NPP is the last one of this kind and compared to its predecessors, it is characterized by several modifications which contribute to the improvement of the safety level. In addition based on Nuclear Regulatory Authority requirements and based on documents: - IAEA - Safety Issues and their ranking for NPP WWER 440/213, - IAEA - Safety Improvement of Mochovce NPP Project Review Mission, - Riskaudit - Evaluation of the Mochovce NPP Safety Improvements. Additional safety measures have been implemented before commissioning. The consortium EUCOM (FRAMATOME - SIEMENS), SKODA Praha, ENERGOPROJEKT Praha, Russian organizations and VUJE Trnava Nuclear Power Plants research institute were selected for design and implementation of the safety measures. The papers summarized, safety requirements, safety measures implemented, results of commissioning and results of safety analysis report evaluation. (author)

  20. Nuclear Safety Research Reactor (NSRR) program in JAERI

    Energy Technology Data Exchange (ETDEWEB)

    Ishikawa, M; Hoshi, T; Ohnishi, N; Fujishiro, T; Inabe, T [Japan Atomic Energy Research Institute (Japan)

    1974-07-01

    An experimental research program, named Nuclear Safety Research Reactor (NSRR) Program, has been progressing in Japan Atomic Energy Research Institute (JAERI) using a modified TRIGA-ACPR. This paper is prepared to describe the outline of the NSRR program. The purpose of the NSRR program is to examine the behaviors of fuel rods under various accidental conditions of power reactors so as to establish realistic safety criteria and to develop analytical models for prediction of fuel failures. We expect to contribute finally to the improvement of reactor design and fuel fabrication techniques based on these experimental results. The NSRR experiments will be performed in the large central experimental tube, which is one of the most excellent features of this reactor, using specially designed capsules or loops which can accommodate up to 49 BWR type test fuels. Many types of test fuels in various conditions will be examined by the NSRR program, such as BWR, PWR and FBR type fuels from the beginning of life to the end of life with and without simulated reactor internal structures. The experiments will be continued for more than 10 years divided into three phases. The first phase of the program will be devoted to the experiments pertaining to reactivity initiated accidents (RIA). In these experiments we will make use of the excellent pulsing capability of ACPR, which is expected to generate 100 MW-sec prompt energy release with 1.3 msec of minimum reactor period by 4.7 dollar reactivity insertion and to yield more than 280 cal/g-UO{sub 2} heat deposit even in an approximately 10% enriched BWR type test fuel. (280 cal/g-UO{sub 2} is believed enough heat deposit to cause fuel failure.) In general, heat flow behaviors from fuel meat to clad and from clad to coolant are very complex phenomena, but they are the key point in analyzing transient response of fuels. In the sudden heat transient conditions brought by pulsing, however, it will be possible to examine each phenomenon

  1. Nuclear Safety Research Reactor (NSRR) program in JAERI

    International Nuclear Information System (INIS)

    Ishikawa, M.; Hoshi, T.; Ohnishi, N.; Fujishiro, T.; Inabe, T.

    1974-01-01

    An experimental research program, named Nuclear Safety Research Reactor (NSRR) Program, has been progressing in Japan Atomic Energy Research Institute (JAERI) using a modified TRIGA-ACPR. This paper is prepared to describe the outline of the NSRR program. The purpose of the NSRR program is to examine the behaviors of fuel rods under various accidental conditions of power reactors so as to establish realistic safety criteria and to develop analytical models for prediction of fuel failures. We expect to contribute finally to the improvement of reactor design and fuel fabrication techniques based on these experimental results. The NSRR experiments will be performed in the large central experimental tube, which is one of the most excellent features of this reactor, using specially designed capsules or loops which can accommodate up to 49 BWR type test fuels. Many types of test fuels in various conditions will be examined by the NSRR program, such as BWR, PWR and FBR type fuels from the beginning of life to the end of life with and without simulated reactor internal structures. The experiments will be continued for more than 10 years divided into three phases. The first phase of the program will be devoted to the experiments pertaining to reactivity initiated accidents (RIA). In these experiments we will make use of the excellent pulsing capability of ACPR, which is expected to generate 100 MW-sec prompt energy release with 1.3 msec of minimum reactor period by 4.7 dollar reactivity insertion and to yield more than 280 cal/g-UO 2 heat deposit even in an approximately 10% enriched BWR type test fuel. (280 cal/g-UO 2 is believed enough heat deposit to cause fuel failure.) In general, heat flow behaviors from fuel meat to clad and from clad to coolant are very complex phenomena, but they are the key point in analyzing transient response of fuels. In the sudden heat transient conditions brought by pulsing, however, it will be possible to examine each phenomenon separately

  2. Operational safety and reactor life improvements of Kyoto University Reactor

    International Nuclear Information System (INIS)

    Utsuro, M.; Fujita, Y.; Nishihara, H.

    1990-01-01

    Recent important experience in improving the operational safety and life of a reactor are described. The Kyoto University Reactor (KUR) is a 25-year-old 5 MW light water reactor provided with two thermal columns of graphite and heavy water as well as other kinds of experimental facilities. In the graphite thermal column, noticeable amounts of neutron irradiation effects had accumulated in the graphite blocks near the core. Before the possible release of the stored energy, all the graphite blocks in the column were successfully replaced with new blocks using the opportunity provided by the installation of a liquid deuterium cold neutron source in the column. At the same time, special seal mechanisms were provided for essential improvements to the problem of radioactive argon production in the column. In the heavy-water thermal column we have accomplished the successful repair of a slow leak of heavy water through a thin instrumentation tube failure. The repair work included the removal and reconstructions of the lead and graphite shielding layers and welding of the instrumentation tube under radiation fields. Several mechanical components in the reactor cooling system were also exchanged for new components with improved designs and materials. On-line data logging of almost all instrumentation signals is continuously performed with a high speed data analysis system to diagnose operational conditions of the reactor. Furthermore, through detailed investigations on critical components, operational safety during further extended reactor life will be supported by well scheduled maintenance programs

  3. Chronic beryllium disease prevention program; worker safety and health program. Final rule.

    Science.gov (United States)

    2006-02-09

    The Department of Energy (DOE) is today publishing a final rule to implement the statutory mandate of section 3173 of the Bob Stump National Defense Authorization Act (NDAA) for Fiscal Year 2003 to establish worker safety and health regulations to govern contractor activities at DOE sites. This program codifies and enhances the worker protection program in operation when the NDAA was enacted.

  4. Structural Aging Program to evaluate continued performance of safety-related concrete structures in nuclear power plants

    International Nuclear Information System (INIS)

    Naus, D.J.; Oland, C.B.; Ellingwood, B.R.

    1994-01-01

    This report discusses the Structural Aging (SAG) Program which is being conducted at the Oak Ridge National Laboratory (ORNL) for the United States Nuclear Regulatory commission (USNRC). The SAG Program is addressing the aging management of safety-related concrete structures in nuclear power plants for the purpose of providing improved technical bases for their continued service. The program is organized into three technical tasks: Materials Property Data Base, Structural Component Assessment/Repair Technologies, and Quantitative Methodology for continued Service Determinations. Objectives and a summary of recent accomplishments under each of these tasks are presented

  5. Evaluating the effectiveness of a logger safety training program.

    Science.gov (United States)

    Bell, Jennifer L; Grushecky, Shawn T

    2006-01-01

    Logger safety training programs are rarely, if ever, evaluated as to their effectiveness in reducing injuries. Workers' compensation claim rates were used to evaluate the effectiveness of a logger safety training program, the West Virginia Loggers' Safety Initiative (LSI). There was no claim rate decline detected in the majority (67%) of companies that participated in all 4 years of the LSI. Furthermore, their rate did not differ from the rest of the WV logging industry that did not participate in the LSI. Worker turnover was significantly related to claim rates; companies with higher turnover of employees had higher claim rates. Companies using feller bunchers to harvest trees at least part of the time had a significantly lower claim rate than companies not using them. Companies that had more inspections per year had lower claim rates. High injury rates persist even in companies that receive safety training; high employee turnover may affect the efficacy of training programs. The logging industry should be encouraged to facilitate the mechanization of logging tasks, to address barriers to employee retention, and to increase the number of in-the-field performance monitoring inspections. Impact on industry There are many states whose logger safety programs include only about 4-8 hours of safe work practices training. These states may look to West Virginia's expanded training program (the LSI) as a model for their own programs. However, the LSI training may not be reaching loggers due to the delay in administering training to new employees and high levels of employee turnover. Regardless of training status, loggers' claim rates decline significantly the longer they work for a company. It may be that high injury rates in the state of West Virginia would be best addressed by finding ways to encourage and facilitate companies to become more mechanized in their harvesting practices, and to increase employee tenure. Increasing the number of yearly performance inspections

  6. The USERDA transport R and D program for environment and safety

    International Nuclear Information System (INIS)

    Sisler, J.A.

    1976-01-01

    This paper describes the U.S. Energy Research and Development Administration's (ERDA) transportation environment and safety research and development program for energy fuels and wastes, including background, current activities, and future plans. It will serve as an overview and integrating factor for the several related technical papers to be presented at this meeting which will enlarge on the detail of specific projects. The transportation R and D program provides for the environmental and safety review of transport systems and procedures; standards development; and package, vehicle, and systems testing for nuclear materials transport. A primary output of the program is the collection, processing, and dissemination of transport environment and safety data, shipment statistics, and technical information. Special transport projects which do not easily fit elsewhere in ERDA are usually done as a part of this program. (author)

  7. Using game theory to improve safety within chemical industrial parks

    CERN Document Server

    Reniers, Genserik

    2013-01-01

    Though the game-theoretic approach has been vastly studied and utilized in relation to economics of industrial organizations, it has hardly been used to tackle safety management in multi-plant chemical industrial settings. Using Game Theory for Improving Safety within Chemical Industrial Parks presents an in-depth discussion of game-theoretic modelling which may be applied to improve cross-company prevention and -safety management in a chemical industrial park.   By systematically analyzing game-theoretic models and approaches in relation to managing safety in chemical industrial parks, Using Game Theory for Improving Safety within Chemical Industrial Parks explores the ways game theory can predict the outcome of complex strategic investment decision making processes involving several adjacent chemical plants. A number of game-theoretic decision models are discussed to provide strategic tools for decision-making situations.   Offering clear and straightforward explanations of methodologies, Using Game Theor...

  8. Assessment of elementary school safety restraint programs.

    Science.gov (United States)

    1985-06-01

    The purpose of this research was to identify elementary school (K-6) safety belt : education programs in use in the United States, to review their development, and : to make administrative and impact assessments of their use in selected States. : Six...

  9. How to improve safety of laparoscopic cholecystectomy

    Directory of Open Access Journals (Sweden)

    ZHANG Yong

    2013-06-01

    Full Text Available Laparoscopic cholecystectomy (LC has become the "gold standard" of treatment for benign gallbladder disease. This paper summarizes various surgical safety measures used in recent years, and suggests an emphasis on perioperative imaging examination, preoperative prevention of risk factors, training of surgical skills, and introduction of fast-track surgery concept, so as to avoid the incidence of complications and improve the safety of LC.

  10. Improving patient safety through quality assurance.

    Science.gov (United States)

    Raab, Stephen S

    2006-05-01

    Anatomic pathology laboratories use several quality assurance tools to detect errors and to improve patient safety. To review some of the anatomic pathology laboratory patient safety quality assurance practices. Different standards and measures in anatomic pathology quality assurance and patient safety were reviewed. Frequency of anatomic pathology laboratory error, variability in the use of specific quality assurance practices, and use of data for error reduction initiatives. Anatomic pathology error frequencies vary according to the detection method used. Based on secondary review, a College of American Pathologists Q-Probes study showed that the mean laboratory error frequency was 6.7%. A College of American Pathologists Q-Tracks study measuring frozen section discrepancy found that laboratories improved the longer they monitored and shared data. There is a lack of standardization across laboratories even for governmentally mandated quality assurance practices, such as cytologic-histologic correlation. The National Institutes of Health funded a consortium of laboratories to benchmark laboratory error frequencies, perform root cause analysis, and design error reduction initiatives, using quality assurance data. Based on the cytologic-histologic correlation process, these laboratories found an aggregate nongynecologic error frequency of 10.8%. Based on gynecologic error data, the laboratory at my institution used Toyota production system processes to lower gynecologic error frequencies and to improve Papanicolaou test metrics. Laboratory quality assurance practices have been used to track error rates, and laboratories are starting to use these data for error reduction initiatives.

  11. Highway Safety Improvement Program (HSIP) - Highway Safety Improvement Program

    Data.gov (United States)

    Department of Transportation — The HSIP ORT establishes a standardized reporting process that promotes consistency among state reports while maintaining flexibility to meet states reporting needs....

  12. Nuclear power safety

    International Nuclear Information System (INIS)

    1991-11-01

    This paper reports that since the Chernobyl nuclear plant accident in 1986, over 70 of the International Atomic Energy Agency's 112 member states have adopted two conventions to enhance international cooperation by providing timely notification of an accident and emergency assistance. The Agency and other international organizations also developed programs to improve nuclear power plant safety and minimize dangers from radioactive contamination. Despite meaningful improvements, some of the measures have limitations, and serious nuclear safety problems remain in the design and operation of the older, Soviet-designed nuclear power plants. The Agency's ability to select reactors under its operational safety review program is limited. Also, information on the extent and seriousness of safety-related incidents at reactors in foreign countries is not publicly available. No agreements exist among nuclear power countries to make compliance with an nuclear safety standards or principles mandatory. Currently, adherence to international safety standards or principles is voluntary and nonbinding. Some states support the concept of mandatory compliance, but others, including the United States, believe that mandatory compliance infringes on national sovereignty and that the responsibility for nuclear reactor safety remains with each nation

  13. 77 FR 3784 - Recreational Boating Safety Projects, Programs and Activities Funded Under Provisions of the...

    Science.gov (United States)

    2012-01-25

    ... program which provides full marketing, media, public information, and program strategy support to the... Wear, Vessel Safety Check Program (VSC), Boating Safety Education Courses, Propeller Strike Avoidance, Carbon Monoxide Poisoning Awareness and Education, and other recreational boating safety issues on an as...

  14. Application of quality assurance program to safety related aging equipment or components

    International Nuclear Information System (INIS)

    Papaiya, N.C.

    1990-01-01

    This paper addresses how quality assurance programs and their criteria are applied to safety related and aging equipment or components used in commercial nuclear plant applications. The QA Programs referred to are 10CFR50 Appendix B and EPRI NP-5652. The QA programs as applicable are applied to equipment/component aging qualification, preventive maintenance, surveillance testing and procurement engineering. The intent of this paper is not the technical issues, methods and research of aging. The paper addresses QA program's application to age-related equipment or components in safety related applications. Quality Assurance Program 10CFR50 Appendix B applies to all safety related aging components or equipment related to the qualification program and associated preventive maintenance and surveillance testing programs. Quality Assurance involvement with procurement engineering for age-related commercial grade items supports EPRI NP-5652 and assures that the dedicated OGI is equal to the item purchased as a basic component to 10CFR50 Appendix B requirements

  15. Integrating team resource management program into staff training improves staff's perception and patient safety in organ procurement and transplantation: the experience in a university-affiliated medical center in Taiwan.

    Science.gov (United States)

    Hsu, Ya-Chi; Jerng, Jih-Shuin; Chang, Ching-Wen; Chen, Li-Chin; Hsieh, Ming-Yuan; Huang, Szu-Fen; Liu, Yueh-Ping; Hung, Kuan-Yu

    2014-08-11

    The process involved in organ procurement and transplantation is very complex that requires multidisciplinary coordination and teamwork. To prevent error during the processes, teamwork education and training might play an important role. We wished to evaluate the efficacy of implementing a Team Resource Management (TRM) program on patient safety and the behaviors of the team members involving in the process. We implemented a TRM training program for the organ procurement and transplantation team members of the National Taiwan University Hospital (NTUH), a teaching medical center in Taiwan. This 15-month intervention included TRM education and training courses for the healthcare workers, focused group skill training for the procurement and transplantation team members, video demonstration and training, and case reviews with feedbacks. Teamwork culture was evaluated and all procurement and transplantation cases were reviewed to evaluate the application of TRM skills during the actual processes. During the intervention period, a total of 34 staff members participated the program, and 67 cases of transplantations were performed. Teamwork framework concept was the most prominent dimension that showed improvement from the participants for training. The team members showed a variety of teamwork behaviors during the process of procurement and transplantation during the intervention period. Of note, there were two potential donors with a positive HIV result, for which the procurement processed was timely and successfully terminated by the team. None of the recipients was transplanted with an infected organ. No error in communication or patient identification was noted during review of the case records. Implementation of a Team Resource Management program improves the teamwork culture as well as patient safety in organ procurement and transplantation.

  16. Clinton P. Anderson Meson Physics Facility and its operational safety program

    International Nuclear Information System (INIS)

    Putnam, T.M.

    1975-01-01

    The Clinton P. Anderson Meson Physics Facility (LAMPF) at the Los Alamos Scientific Laboratory consists of/ (1) a medium-energy, high-intensity linear proton accelerator; (2) experimental areas designed to support a multidisciplined program of research and practical applications; and (3) support facilities for accelerator operations and the experimental program. The high-intensity primary and secondary beams at LAMPF and the varied research program create many interesting and challenging problems for the Health Physics staff. A brief overview of LAMPF is presented, and the Operational Safety Program is discussed, with emphasis on the radiological safety and health physics aspects

  17. Alternative off-site power supply improves nuclear power plant safety

    International Nuclear Information System (INIS)

    Gjorgiev, Blaže; Volkanovski, Andrija; Kančev, Duško; Čepin, Marko

    2014-01-01

    Highlights: • Additional power supply for mitigation of the station blackout event in NPP is used. • A hydro power plant is considered as an off-site alternative power supply. • An upgrade of the probabilistic safety assessment from its traditional use is made. • The obtained results show improvement of nuclear power plant safety. - Abstract: A reliable power system is important for safe operation of the nuclear power plants. The station blackout event is of great importance for nuclear power plant safety. This event is caused by the loss of all alternating current power supply to the safety and non-safety buses of the nuclear power plant. In this study an independent electrical connection between a pumped-storage hydro power plant and a nuclear power plant is assumed as a standpoint for safety and reliability analysis. The pumped-storage hydro power plant is considered as an alternative power supply. The connection with conventional accumulation type of hydro power plant is analysed in addition. The objective of this paper is to investigate the improvement of nuclear power plant safety resulting from the consideration of the alternative power supplies. The safety of the nuclear power plant is analysed through the core damage frequency, a risk measure assess by the probabilistic safety assessment. The presented method upgrades the probabilistic safety assessment from its common traditional use in sense that it considers non-plant sited systems. The obtained results show significant decrease of the core damage frequency, indicating improvement of nuclear safety if hydro power plant is introduced as an alternative off-site power source

  18. Revised GCFR safety program plan

    International Nuclear Information System (INIS)

    Kelley, A.P.; Boyack, B.E.; Torri, A.

    1980-05-01

    This paper presents a summary of the recently revised gas-cooled fast breeder reactor (GCFR) safety program plan. The activities under this plan are organized to support six lines of protection (LOPs) for protection of the public from postulated GCFR accidents. Each LOP provides an independent, sequential, quantifiable risk barrier between the public and the radiological hazards associated with postulated GCFR accidents. To implement a quantitative risk-based approach in identifying the important technology requirements for each LOP, frequency and consequence-limiting goals are allocated to each. To ensure that all necessary tasks are covered to achieve these goals, the program plan is broken into a work breakdown structure (WBS). Finally, the means by which the plan is being implemented are discussed

  19. Improving health care quality and safety: the role of collective learning.

    Science.gov (United States)

    Singer, Sara J; Benzer, Justin K; Hamdan, Sami U

    2015-01-01

    Despite decades of effort to improve quality and safety in health care, this goal feels increasingly elusive. Successful examples of improvement are infrequently replicated. This scoping review synthesizes 76 empirical or conceptual studies (out of 1208 originally screened) addressing learning in quality or safety improvement, that were published in selected health care and management journals between January 2000 and December 2014 to deepen understanding of the role that collective learning plays in quality and safety improvement. We categorize learning activities using a theoretical model that shows how leadership and environmental factors support collective learning processes and practices, and in turn team and organizational improvement outcomes. By focusing on quality and safety improvement, our review elaborates the premise of learning theory that leadership, environment, and processes combine to create conditions that promote learning. Specifically, we found that learning for quality and safety improvement includes experimentation (including deliberate experimentation, improvisation, learning from failures, exploration, and exploitation), internal and external knowledge acquisition, performance monitoring and comparison, and training. Supportive learning environments are characterized by team characteristics like psychological safety, appreciation of differences, openness to new ideas social motivation, and team autonomy; team contextual factors including learning resources like time for reflection, access to knowledge, organizational capabilities; incentives; and organizational culture, strategy, and structure; and external environmental factors including institutional pressures, environmental dynamism and competitiveness and learning collaboratives. Lastly learning in the context of quality and safety improvement requires leadership that reinforces learning through actions and behaviors that affect people, such as coaching and trust building, and through

  20. Thermonuclear generation program: risks and safety

    International Nuclear Information System (INIS)

    Goes, Alexandre Gromann de Araujo

    1999-01-01

    This work deals with the fundamental concepts of risk and safety related to nuclear power generation. In the first chapter, a general evaluation of the various systems for energy generation and their environmental impacts is made. Some definitions for safety and risk are suggested, based on the already existing regulatory processes and also on the current tendencies of risk management. Aspects regarding the safety culture are commented. The International Nuclear Event Scale (INES), a coherent and clear mechanism of communication between nuclear specialists and the general public, is analyzed. The second chapter examines the thermonuclear generation program in Brazil and the role of the National Nuclear Energy Commission. The third chapter presents national and international scenarios in terms of safety and risks, available policies and the main obstacles for future development of nuclear energy and nuclear engineering, and strategies are proposed. In the last chapter, comments about possible trends and recommendations related to practical risk management procedures, taking into account rational criteria for resources distribution and risk reduction are made, envisaging a closer integration between nuclear specialists and the society as a whole, thus decreasing the conflicts in a democratic decision-making process

  1. Reactor safety issues resolved by the 2D/3D Program

    International Nuclear Information System (INIS)

    Damerell, P.S.; Simons, J.W.

    1993-07-01

    The 2D/3D Program studied multidimensional thermal-hydraulics in a PWR core and primary system during the end-of-blowdown and post-blowdown phases of a large-break LOCA (LBLOCA), and during selected small-break LOCA (SBLOCA) transients. The program included tests at the Cylindrical Core Test Facility (CCTF), the Slab Core Test Facility (SCTF), and the Upper Plenum Test Facility (UPTF), and computer analyses using TRAC. Tests at CCTF investigated core thermal-hydraulics and overall system behavior while tests at SCTF concentrated on multidimensional core thermal-hydraulics. The UPTF tests investigated two-phase flow behavior in the downcomer, upper plenum, tie plate region, and primary loops. TRAC analyses evaluated thermal-hydraulic behavior throughout the primary system in tests as well as in PWRs. This report summarizes the test and analysis results in each of the main areas where improved information was obtained in the 2D/3D Program. The discussion is organized in terms of the reactor safety issues investigated

  2. A conceptual approach to the estimation of societal willingness-to-pay for nuclear safety programs

    International Nuclear Information System (INIS)

    Pandey, M.D.; Nathwani, J.S.

    2003-01-01

    The design, refurbishment and future decommissioning of nuclear reactors are crucially concerned with reducing the risk of radiation exposure that can result in adverse health effects and potential loss of life. To address this concern, large financial investments have been made to ensure safety of operating nuclear power plants worldwide. The efficacy of the expenditures incurred to provide safety must be judged against the safety benefit to be gained from such investments. We have developed an approach that provides a defendable basis for making that judgement. If the costs of risk reduction are disproportionate to the safety benefits derived, then the expenditures are not optimal; in essence the societal resources are being diverted away from other critical areas such as health care, education and social services that also enhance the quality of life. Thus, the allocation of society's resources devoted to nuclear safety must be continually appraised in light of competing needs, because there is a limit on the resources that any society can devote to extend life. The purpose of the paper is to present a simple and methodical approach to assessing the benefits of nuclear safety programs and regulations. The paper presents the Life-Quality Index (LQI) as a tool for the assessment of risk reduction initiatives that would support the public interest and enhance both safety and the quality of life. The LQI is formulated as a utility function consistent with the principles of rational decision analysis. The LQI is applied to quantify the societal willingness-to-pay (SWTP) for safety measures enacted to reduce of the risk of potential exposures to ionising radiation. The proposed approach provides essential support to help improve the cost-benefit analysis of engineering safety programs and safety regulations.

  3. Prioritization of R and D programs on probabilistic reactor safety

    International Nuclear Information System (INIS)

    Husseiny, A.A.

    1982-01-01

    An interactive computer code based on the multiattribute utility theory has been developed with graphic capabilities to use in selection of probabilistic reactor safety RandD programs. Utility values and proper graphic representation are made through lottery games on the computer terminal. The code is applied to prioritize a set of RandD programs on LWR safety based on attributes including regulatory issues, institutional issues and operation problems. The methodology is described here in detail with its applications. Some of the input includes statistical distributions and subjective judgments on institutional issues. The flexibility of the approach provides a tool for decision makers whether on individual or group level to assess LWR safety priorities and continuously update their strategies

  4. Errors in laboratory medicine: practical lessons to improve patient safety.

    Science.gov (United States)

    Howanitz, Peter J

    2005-10-01

    Patient safety is influenced by the frequency and seriousness of errors that occur in the health care system. Error rates in laboratory practices are collected routinely for a variety of performance measures in all clinical pathology laboratories in the United States, but a list of critical performance measures has not yet been recommended. The most extensive databases describing error rates in pathology were developed and are maintained by the College of American Pathologists (CAP). These databases include the CAP's Q-Probes and Q-Tracks programs, which provide information on error rates from more than 130 interlaboratory studies. To define critical performance measures in laboratory medicine, describe error rates of these measures, and provide suggestions to decrease these errors, thereby ultimately improving patient safety. A review of experiences from Q-Probes and Q-Tracks studies supplemented with other studies cited in the literature. Q-Probes studies are carried out as time-limited studies lasting 1 to 4 months and have been conducted since 1989. In contrast, Q-Tracks investigations are ongoing studies performed on a yearly basis and have been conducted only since 1998. Participants from institutions throughout the world simultaneously conducted these studies according to specified scientific designs. The CAP has collected and summarized data for participants about these performance measures, including the significance of errors, the magnitude of error rates, tactics for error reduction, and willingness to implement each of these performance measures. A list of recommended performance measures, the frequency of errors when these performance measures were studied, and suggestions to improve patient safety by reducing these errors. Error rates for preanalytic and postanalytic performance measures were higher than for analytic measures. Eight performance measures were identified, including customer satisfaction, test turnaround times, patient identification

  5. Home safe home: Evaluation of a childhood home safety program.

    Science.gov (United States)

    Stewart, Tanya Charyk; Clark, Andrew; Gilliland, Jason; Miller, Michael R; Edwards, Jane; Haidar, Tania; Batey, Brandon; Vogt, Kelly N; Parry, Neil G; Fraser, Douglas D; Merritt, Neil

    2016-09-01

    The London Health Sciences Centre Home Safety Program (HSP) provides safety devices, education, a safety video, and home safety checklist to all first-time parents for the reduction of childhood home injuries. The objective of this study was to evaluate the HSP for the prevention of home injuries in children up to 2 years of age. A program evaluation was performed with follow-up survey, along with an interrupted time series analysis of emergency department (ED) visits for home injuries 5 years before (2007-2013) and 2 years after (2013-2015) implementation. Spatial analysis of ED visits was undertaken to assess differences in home injury rates by dissemination areas controlling differences in socioeconomic status (i.e., income, education, and lone-parent status) at the neighborhood level. A total of 3,458 first-time parents participated in the HSP (a 74% compliance rate). Of these, 20% (n = 696) of parents responded to our questionnaire, with 94% reporting the program to be useful (median, 6; interquartile range, 2 on a 7-point Likert scale) and 81% learning new strategies for preventing home injuries. The median age of the respondent's babies were 12 months (interquartile range, 1). The home safety check list was used by 87% of respondents to identify hazards in their home, with 95% taking action to minimize the risk. The time series analysis demonstrated a significant decline in ED visits for home injuries in toddlers younger than2 years of age after HSP implementation. The declines in ED visits for home injuries remained significant over and above each socioeconomic status covariate. Removing hazards, supervision, and installing safety devices are key facilitators in the reduction of home injuries. Parents found the HSP useful to identify hazards, learn new strategies, build confidence, and provide safety products. Initial finding suggests that the program is effective in reducing home injuries in children up to 2 years of age. Therapeutic/care management study

  6. Nordic Nuclear Safety Research. Presentation of the 1994 - 1997 program

    International Nuclear Information System (INIS)

    Bennerstedt, Torkel

    1998-01-01

    NKS (Nordic Nuclear Safety Research) has just concluded its fifth 4-year program (1994 - 1997). The following nine projects were performed: Strategy for reactor safety: Studies of preparatory work to minimize the risk of accidents; Prevention of severe reactor accidents: studies of recriticality, core melt progression and support systems to minimize releases; Safe disposal of radioactive waste: Waste characterization, Performance analyses and environmental impact statements for repositories; Marine radioecology: Improved assessment methods for effects of releases of radionuclides; Long ecological half-lives in semi-natural systems: Models for transfer of cesium from nature to man; Preparedness strategies and procedures: Mobile measurements, quality assurance and interventions; Emergency preparedness drills and exercises; Preplanning of early cleanup: Check-list for planners and decision makers for various environments and fallout situations; Overriding information issues: Risk communication, real-time exchange of information after an accident. Together with additional financial support from a number of ministries and companies in the nuclear power field, the total NKS budget for the period 1994 - 1997 was some USD 5 million, evenly distributed over the years. To this should be added contributions in kind by participating organizations, worth at least another USD 10 million, without which this program would not have been possible. The nine projects and some practical results (rather than scientific detail) are outlined in this paper. (EG)

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

    DEFF Research Database (Denmark)

    Kristensen, Solvejg; Mainz, Jan; Bartels, Paul

    2009-01-01

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

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

    Science.gov (United States)

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

    2018-04-16

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

  9. Fusion Safety Program annual report, fiscal year 1984

    International Nuclear Information System (INIS)

    Crocker, J.G.; Holland, D.F.

    1985-06-01

    This report summarizes the Fusion Safety Program major activities in fiscal year 1984. The Idaho National Engineering Laboratory (INEL) is the designated lead laboratory and EG and G Idaho, Inc., is the prime contractor for this program, which was initiated in 1979. A report section titled ''Activities at the INEL'' includes progress reports on the tritium implantation experiment, tritium blanket permeation, volatilization of reactor alloys, plasma disruptions, a comparative blanket safety assessment, transient code development, and a discussion of the INEL's participation in the Tokamak Fusion Core Experiment (TFCX) design study. The report section titled ''Outside Contracts'' includes progress reports on tritium conversion by the Oak Ridge National Laboratory (ORNL), lithium-lead reactions by the Hanford Engineering Development Laboratory (HEDL) and the University of Wisconsin, magnet safety by the Francis Bitter Magnet Laboratory of the Massachusetts Institute of Technology (MIT) and Argonne National Laboratory (ANL), risk assessment by MIT, tritium retention by the University of Virginia, and activation product release by GA Technologies. A list of publications produced during the year and brief descriptions of activities planned for FY-1985 are also included

  10. Construction safety program for the National Ignition Facility, Appendix B

    Energy Technology Data Exchange (ETDEWEB)

    Cerruti, S.J.

    1997-06-26

    This Appendix contains material from the LLNL Health and Safety Manual as listed below. For sections not included in this list, please refer to the Manual itself. The areas covered are: asbestos, lead, fire prevention, lockout, and tag program confined space traffic safety.

  11. Construction safety program for the National Ignition Facility, Appendix B

    International Nuclear Information System (INIS)

    Cerruti, S.J.

    1997-01-01

    This Appendix contains material from the LLNL Health and Safety Manual as listed below. For sections not included in this list, please refer to the Manual itself. The areas covered are: asbestos, lead, fire prevention, lockout, and tag program confined space traffic safety

  12. Promoting safety culture in radiation industry through radiation audit

    International Nuclear Information System (INIS)

    Noriah, M.A.

    2007-01-01

    This paper illustrates the Malaysian experience in implementing and promoting effective radiation safety program. Current management practice demands that an organization inculcate culture of safety in preventing radiation hazard. The aforementioned objectives of radiation protection can only be met when it is implemented and evaluated continuously. Commitment from the workforce to treat safety as a priority and the ability to turn a requirement into a practical language is also important to implement radiation safety policy efficiently. Maintaining and improving safety culture is a continuous process. There is a need to establish a program to measure, review and audit health and safety performance against predetermined standards. This program is known as radiation safety audit and is able to reveal where and when action is needed to make improvements to the systems of controls. A structured and proper radiation self-auditing system is seen as the sole requirement to meet the current and future needs in sustainability of radiation safety. As a result safety culture, which has been a vital element on safety in many industries can be improved and promote changes, leading to good safety performance and excellence. (author)

  13. HRET patient safety leadership fellowship: the role of "community" in patient safety.

    Science.gov (United States)

    Leonhardt, Kathryn Kraft

    2010-01-01

    Community engagement is widely endorsed but poorly defined as a strategy to improve patient safety. With strong evidence that engaging patients can positively influence health outcomes, it is presumed that community engagement could improve patient safety. Leaning on the models from other disciplines such as public health, the adequate knowledge and application of the principles of community engagement are critical for this approach to be effective. This article provides a description of the theories supporting patient partnership and community engagement, reviews critical elements of successful community-based programs, and identifies the potential for empowering communities to improve patient safety.

  14. Modelling of safety barriers including human and organisational factors to improve process safety

    DEFF Research Database (Denmark)

    Markert, Frank; Duijm, Nijs Jan; Thommesen, Jacob

    2013-01-01

    It is believed that traditional safety management needs to be improved on the aspect of preparedness for coping with expected and unexpected deviations, avoiding an overly optimistic reliance on safety systems. Remembering recent major accidents, such as the Deep Water Horizon, the Texas City....... A valuable approach is the inclusion of human and organisational factors into the simulation of the reliability of the technical system using event trees and fault trees and the concept of safety barriers. This has been demonstrated e.g. in the former European research project ARAMIS (Accidental Risk...

  15. Tank waste remediation system nuclear criticality safety program management review

    International Nuclear Information System (INIS)

    BRADY RAAP, M.C.

    1999-01-01

    This document provides the results of an internal management review of the Tank Waste Remediation System (TWRS) criticality safety program, performed in advance of the DOE/RL assessment for closure of the TWRS Nuclear Criticality Safety Issue, March 1994. Resolution of the safety issue was identified as Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-40-12, due September 1999

  16. Patient Education May Improve Perioperative Safety.

    NARCIS (Netherlands)

    de Haan, L.S.; Calsbeek, H; Wolff, André

    2016-01-01

    Importance: There is a growing interest in enabling ways for patients to participate in their own care to improve perioperative safety, but little is known about the effectiveness of interventions enhancing an active patient role. Objective: To evaluate the effect of patient participation on

  17. An improved instrument setpoint control program

    International Nuclear Information System (INIS)

    Cash, J.S. Jr.; George, R.T.; Kincaid, S.C.

    1991-01-01

    Instrument setpoints have a definite and often significant impact on plant safety, reliability, and availability. Although typically overshadowed by plant design, modification, and physical change activities, instrument setpoints can alter plant status and system operating characteristics just as significantly. Recognizing the need for a formal program that provides configuration control of instrument setpoints, provides a readily accessible and clearly documented basis for instrument setpoints, and integrates and coordinates operations, engineering, and maintenance activities that influence the basis for instrument setpoints, Philadelphia Electric Company (PECo) is developing an Improved Instrument Setpoint Control Program (IISCP) that incorporates current industry guidance and practices and state-of-the-art information systems technology. The IISCP was designed around PECo's then existing business processes for setpoint control, determination, and maintenance. A task force representing the various constituencies from both plants and the engineering and services organizations were formed to identify objectives and design features for the IISCP. Utilizing industry standards and guidance, regulatory documents, the experiences and good practices obtained from other utilities, and PECo's nuclear group strategies, objectives, and goals, specific objectives were identified to enhance the business processes

  18. Aviation safety/automation program overview

    Science.gov (United States)

    Morello, Samuel A.

    1990-01-01

    The goal is to provide a technology base leading to improved safety of the national airspace system through the development and integration of human-centered automation technologies for aircraft crews and air traffic controllers. Information on the problems, specific objectives, human-automation interaction, intelligent error-tolerant systems, and air traffic control/cockpit integration is given in viewgraph form.

  19. [Improving patient safety through voluntary peer review].

    Science.gov (United States)

    Kluge, S; Bause, H

    2015-01-01

    The intensive care unit (ICU) is one area of the hospital in which processes and communication are of primary importance. Errors in intensive care units can lead to serious adverse events with significant consequences for patients. Therefore quality and risk-management are important measures when treating critically ill patients. A pragmatic approach to support quality and safety in intensive care is peer review. This approach has gained significant acceptance over the past years. It consists of mutual visits by colleagues who conduct standardised peer reviews. These reviews focus on the systematic evaluation of the quality of an ICU's structure, its processes and outcome. Together with different associations, the State Chambers of Physicians and the German Medical Association have developed peer review as a standardized tool for quality improvement. The common goal of all stakeholders is the continuous and sustainable improvement in intensive care with peer reviews significantly increasing and improving communication between professions and disciplines. Peer reviews secure the sustainability of planned change processes and consequently lead the way to an improved culture of quality and safety.

  20. Nuclear reactor safety program in US department of energy and future perspectives

    International Nuclear Information System (INIS)

    Song, Y.T.

    1988-01-01

    The US Department of Energy (DOE) establishes policy, issues orders, and assures compliance with requirements. The contractors who design, construct, modify, operate, maintain and decommission DOE reactors, set forth the assessment of the safety of cognizant reactors and implement DOE orders. Teams of experts in the Department, through scheduled and unscheduled review programs, reassess the safety of reactors in every phases of their lives. As new technology develops, the safety programs are reevaluated and policies are modified to accommodate these new technologies. The diagnostic capabilities of the computer using multiple alarms to enhance detection of defects and control of a reactor have been greatly utilized in reactor operating systems. The Application of artificial intelligence technologies for diagnostic and even for the decision making process in the event of reactor accidents would be one of the future trends in reactor safety programs

  1. The safety indicators program in Taiwan, China : a six-year trend

    International Nuclear Information System (INIS)

    Hsu, Mingte

    1998-01-01

    This paper presents data on the current operating status and the safety indicators (SI) of the six nuclear power units in Taiwan. Analysis of the data collected in a six-year period has been made to obtain trends for each safety indicator. An overview of the trends of the plant operational data during the same period are also provided and discussed. On the whole, the trends of safety indicators are improving during the observed period 1991-1996. The plant operational data have depicted coherent improvement with the safety indicator trends. This result supports the premise that improvements in safety performance and in operational reliability are correspondingly inter-dependent. Both the safety indicators quarterly report and the annual report are available to the public. The public can also approach this information from the AEC's World Wide Web site (http://www.aec.gov.tw). (author)

  2. National Space Agencies vs. Commercial Space: Towards Improved Space Safety

    Science.gov (United States)

    Pelton, J.

    2013-09-01

    Traditional space policies as developed at the national level includes many elements but they are most typically driven by economic and political objectives. Legislatively administered programs apportion limited public funds to achieve "gains" that can involve employment, stimulus to the economy, national defense or other advancements. Yet political advantage is seldom far from the picture.Within the context of traditional space policies, safety issues cannot truly be described as "afterthoughts", but they are usually, at best, a secondary or even tertiary consideration. "Space safety" is often simply assumed to be "in there" somewhere. The current key question is can "safety and risk minimization", within new commercial space programs actually be elevated in importance and effectively be "designed in" at the outset. This has long been the case with commercial aviation and there is at least reasonable hope that this could also be the case for the commercial space industry in coming years. The cooperative role that the insurance industry has now played for centuries in the shipping industry and for decades in aviation can perhaps now play a constructive role in risk minimization in the commercial space domain as well. This paper begins by examining two historical case studies in the context of traditional national space policy development to see how major space policy decisions involving "manned space programs" have given undue primacy to "political considerations" over "safety" and other factors. The specific case histories examined here include first the decision to undertake the Space Shuttle Program (i.e. 1970-1972) and the second is the International Space Station. In both cases the key and overarching decisions were driven by political, schedule and cost considerations, and safety seems absence as a prime consideration. In publicly funded space programs—whether in the United States, Europe, Russia, Japan, China, India or elsewhere—it seems realistic to

  3. Quantifying the effectiveness of ITS in improving safety of VRUs

    NARCIS (Netherlands)

    Silla, A.; Rämä, P.; Leden, L.; Noort, M. van; Kruijff, J. de; Bell, D.; Morris, A.; Hancox, G.; Scholliers, J.

    2017-01-01

    This paper presents the results of a safety impact assessment, providing quantitative estimates of the safety impacts of ten intelligent transport systems (ITS) which were designed to improve safety, mobility and comfort of vulnerable road users (VRUs). The evaluation method originally developed to

  4. PNRA: Practically Improving Safety Culture within the Regulatory Body

    International Nuclear Information System (INIS)

    Bhatti, S.A.N.; Habib, M.A.

    2016-01-01

    were carried out in order to prepare the organization for the cultural assessment activity. After completion of safety culture self assessment at PNRA, the communication strategy was defined to share outcome of this assessment in the organization with the focus on developing dialogue and shared understanding. The safety culture improvement activities were designed to maintain and enhance strong areas of safety culture at PNRA and to address those areas that need attention in order to enhance safety consciousness. This paper presents PNRA’s experience of using IAEA emerging methodology for safety culture self assessment, challenges faced during the process and lessons learnt for further improvement in order to implement it more effectively in future. The paper also highlights strategy utilised for conveying outcomes of SCSA in the organization at different levels along with safety culture improvement activities. (author)

  5. Major structural response methods used in the seismic safety margins research program

    International Nuclear Information System (INIS)

    Chou, C.K.; Lo, T.; Vagliente, V.

    1979-01-01

    In order to evaluate the conservatisms in present nuclear power plant seismic safety requirements, a probabilistic based systems model is being developed. This model will also be used to develop improved requirements. In Phase I of the Seismic Safety Margins Research Program (SSMRP), this methodology will be developed for a specific nuclear power plant and used to perform probabilistic sensitivity studies to gain engineering insights into seismic safety requirements. Random variables in the structural response analysis area, or parameters which cause uncertainty in the response, are discussed and classified into three categories; i.e., material properties, structural dynamic characteristics and related modeling techniques, and analytical methods. The sensitivity studies are grouped into two categories; deterministic and probabilistic. In a system analysis, transfer functions in simple form are needed since there are too many responses which have to be calculated in a Monte Carlo simulation to use the usual straightforward calculation approach. Therefore, the development of these simple transfer functions is one of the important tasks in SSMRP. Simplified as well as classical transfer functions are discussed

  6. Improving operational safety management through probabilistic safety assessment on personal computers

    International Nuclear Information System (INIS)

    1988-10-01

    The Technical Committee Meeting considered the current effort in the implementation and use of PSA information for day-to-day operational safety management on Personal Computers. Due to the very recent development of the necessary hardware and software for Personal Computers, the application of PSA information for day-to-day operational safety management on PCs is essentially still in a pioneering stage. There is at present only one such system for end users existing, the PRISIM (Plant Risk Status Information Management) program for which a limited practical application experience is available. Others are still in the development stage. The main aim of the Technical Committee Meeting was to discuss the present status of PSA based systems for operational safety management support on small computers, to consider practical aspects when implementing these systems into a nuclear installation and to address problems related to the further work in the area. A separate abstract was prepared for the summary of the Technical Committee Meeting and for the 8 papers presented by the participants. Refs, figs and tabs

  7. An overview of the US Department of Energy Plant Lifetime Improvement Program

    International Nuclear Information System (INIS)

    Moonka, A.K.; Harrison, D.L.

    1995-01-01

    This paper provides a brief summary of the U.S. Department of Energy's (USDOE's) cooperative effort with the nuclear industry to develop technology to manage the effects of material degradation in systems, structures and components (SSCs) that impact plant safety or can significantly improve plant performance/economics and to establish and demonstrate the license renewal process. Also included are efforts to reduce decontamination/decommission costs, and reduce the uncertainty in long-term service-life decision making. During 1995, the Plant Lifetime Improvement (PLIM) Program was renamed the Commercial Operating Light Water Reactor (COLWR) Program activities are focused on sustaining the LWR option for domestic electricity generation by supporting operation of existing LWRs as long as they are safe, efficient, and economical. The status of the key projects is discussed in this paper

  8. Nuclear safety improvement activities related to WWER-440 units in Bulgaria

    International Nuclear Information System (INIS)

    Gantchev, T.

    1998-01-01

    The systematic evaluation of the deficiencies of the original design of the WWER reactors brought to the development of a Short Term Programme for Safety Upgrading and Modernisation of Kozloduy WWER-440 units. The implementation of this Programme was completed in 1997. The strive for continuos improvement of Kozloduy Nuclear Power Plant (NPP) safety level, the new requirements of the Bulgarian Nuclear Safety Authority and the public concern initiated the development of new Complex Programme for Safety Improvement (PRG'97), now in a process of implementation. (author)

  9. Fusion Safety Program annual report: Fiscal year 1986

    International Nuclear Information System (INIS)

    Holland, D.F.; Merrill, B.J.; Herring, J.S.; Piet, S.J.; Longhurst, G.R.

    1987-06-01

    This report summarizes the Fusion Safety Program's (FSP) major activities in fiscal year 1986. The Idaho National Engineering Laboratory (INEL) is the designated lead laboratory, and EG and G Idaho, Inc., is the prime contractor for FSP, which was initiated in 1979. Activities are conducted at the INEL and in participating facilities, including the Hanford Engineering Development Laboratory (HEDL), the Massachusetts Institute of Technology (MIT), and the University of Wisconsin. The technical areas covered in this report include tritium safety, activation product release, reactions involving lithium breeding materials, safety of fusion magnet systems, plasma disruption, risk assessment methodology, and computer code development for reactor transients. Contributions to the Technical Planning Activity (TPA) and the ''white paper'' study by the Environmental, Safety,and Economics Committee (ESECOM) are summarized. The report also includes a summary of the safety and environmental analysis and documentation performed by the INEL for the Compact Ignition Tokamak (CIT) design project

  10. Driving forces behind the Chinese public's demand for improved environmental safety.

    Science.gov (United States)

    Wen, Ting; Wang, Jigan; Ma, Zongwei; Bi, Jun

    2017-12-15

    Over the past decades, the public demand for improved environmental safety keeps increasing in China. This study aims to assess the driving forces behind the increasing public demand for improved environmental safety using a provincial and multi-year (1995, 2000, 2005, 2010, and 2014) panel data and the Stochastic Impacts by Regression on Population, Affluence, and Technology (STIRPAT) model. The potential driving forces investigated included population size, income levels, degrees of urbanization, and educational levels. Results show that population size and educational level are positively (Pdemand for improved environmental safety. No significant impact on demand was found due to the degree of urbanization. For the impact due to income level, an inverted U-shaped curve effect with the turning point of ~140,000 CNY GDP per capita is indicated. Since per capita GDP of 2015 in China was approximately 50,000 CNY and far from the turning point, the public demand for improved environmental safety will continue rising in the near future. To meet the increasing public demand for improved environmental safety, proactive and risk prevention based environmental management systems coupled with effective environmental risk communication should be established. Copyright © 2017 Elsevier B.V. All rights reserved.

  11. Nuclear health and safety

    International Nuclear Information System (INIS)

    1991-08-01

    This paper is a review of environmental and safety programs at facilities in the Naval Reactors Program which shows no basis for allegations that unsafe conditions exist there or that the environment is being harmed by activities conducted there. The prototype reactor design provides safety measures that are consistent with commercial nuclear power plants. Minor incidents affecting safety and the environment have occurred, however, and dents affecting safety and the environment have occurred, however, and as with other nuclear facilities, past activities have caused environmental problems that require ongoing monitoring and vigilance. While the program has historically been exempt from most oversight, some federal and state environmental oversight agencies have recently been permitted access to Naval Reactors facilities for oversight purposes. The program voluntarily cooperates with the Nuclear Regulatory Commission regarding reactor modifications, safety improvements, and component reliability. In addition, the program and its contractors have established an extensive internal oversight program that is geared toward reporting the slightest deviations from requirements or procedures. Given the program's classification policies and requirements, it does not appear that the program routinely overclassifies information to prevent its release to the public or to avoid embarrassment. However, GAO did not some instances in which documents were improperly classified

  12. Safety coaches in radiology: decreasing human error and minimizing patient harm

    Energy Technology Data Exchange (ETDEWEB)

    Dickerson, Julie M.; Adams, Janet M. [Cincinnati Children' s Hospital Medical Center, Department of Radiology, MLC 5031, Cincinnati, OH (United States); Koch, Bernadette L.; Donnelly, Lane F. [Cincinnati Children' s Hospital Medical Center, Department of Radiology, MLC 5031, Cincinnati, OH (United States); Cincinnati Children' s Hospital Medical Center, Department of Pediatrics, Cincinnati, OH (United States); Goodfriend, Martha A. [Cincinnati Children' s Hospital Medical Center, Department of Quality Improvement, Cincinnati, OH (United States)

    2010-09-15

    Successful programs to improve patient safety require a component aimed at improving safety culture and environment, resulting in a reduced number of human errors that could lead to patient harm. Safety coaching provides peer accountability. It involves observing for safety behaviors and use of error prevention techniques and provides immediate feedback. For more than a decade, behavior-based safety coaching has been a successful strategy for reducing error within the context of occupational safety in industry. We describe the use of safety coaches in radiology. Safety coaches are an important component of our comprehensive patient safety program. (orig.)

  13. Safety coaches in radiology: decreasing human error and minimizing patient harm

    International Nuclear Information System (INIS)

    Dickerson, Julie M.; Adams, Janet M.; Koch, Bernadette L.; Donnelly, Lane F.; Goodfriend, Martha A.

    2010-01-01

    Successful programs to improve patient safety require a component aimed at improving safety culture and environment, resulting in a reduced number of human errors that could lead to patient harm. Safety coaching provides peer accountability. It involves observing for safety behaviors and use of error prevention techniques and provides immediate feedback. For more than a decade, behavior-based safety coaching has been a successful strategy for reducing error within the context of occupational safety in industry. We describe the use of safety coaches in radiology. Safety coaches are an important component of our comprehensive patient safety program. (orig.)

  14. Safety coaches in radiology: decreasing human error and minimizing patient harm.

    Science.gov (United States)

    Dickerson, Julie M; Koch, Bernadette L; Adams, Janet M; Goodfriend, Martha A; Donnelly, Lane F

    2010-09-01

    Successful programs to improve patient safety require a component aimed at improving safety culture and environment, resulting in a reduced number of human errors that could lead to patient harm. Safety coaching provides peer accountability. It involves observing for safety behaviors and use of error prevention techniques and provides immediate feedback. For more than a decade, behavior-based safety coaching has been a successful strategy for reducing error within the context of occupational safety in industry. We describe the use of safety coaches in radiology. Safety coaches are an important component of our comprehensive patient safety program.

  15. Training and qualification program for nuclear criticality safety technical staff. Revision 1

    International Nuclear Information System (INIS)

    Taylor, R.G.; Worley, C.A.

    1997-01-01

    A training and qualification program for nuclear criticality safety technical staff personnel has been developed and implemented. All personnel who are to perform nuclear criticality safety technical work are required to participate in the program. The program includes both general nuclear criticality safety and plant specific knowledge components. Advantage can be taken of previous experience for that knowledge which is portable such as performance of computer calculations. Candidates step through a structured process which exposes them to basic background information, general plant information, and plant specific information which they need to safely and competently perform their jobs. Extensive documentation is generated to demonstrate that candidates have met the standards established for qualification

  16. Safety analysis report upgrade program at the Plutonium Facility, Los Alamos National Laboratory

    International Nuclear Information System (INIS)

    Pan, P.Y.

    1993-01-01

    Plutonium research and development activities have resided at the Los Alamos National Laboratory (LANL) since 1943. The function of the Plutonium Facility (PF-4) has been to perform basic special nuclear materials research and development and to support national defense and energy programs. The original Final Safety Analysis Report (FSAR) for PF-4 was approved by DOE in 1978. This FSAR analyzed design-basis and bounding accidents. In 1986, DOE/AL published DOE/AL Order 5481.1B, ''Safety Analysis and Review System'', as a requirement for preparation and review of safety analyses. To meet the new DOE requirements, the Facilities Management Group of the Nuclear Material Technology Division submitted a draft FSAR to DOE for approval in April 1991. This draft FSAR analyzed the new configurations and used a limited-scope probabilistic risk analysis for accident analysis. During the DOE review of the draft FSAR, DOE Order 5480.23 ''Nuclear Safety Analysis Reports'', was promulgated and was later officially released in April 1992. The new order significantly expands the scope, preparation, and maintenance efforts beyond those required in DOE/AL Order 5481.1B by requiring: description of institutional and human-factor safety programs; clear definitions of all facility-specific safety commitments; more comprehensive and detailed hazard assessment; use of new safety analysis methods; and annual updates of FSARs. This paper describes the safety analysis report (SAR) upgrade program at the Plutonium Facility in LANL. The SAR upgrade program is established to meet the requirements in DOE Order 5480.23. Described in this paper are the SAR background, authorization basis for operations, hazard classification, and technical program elements

  17. ERC Safety and Hygiene Programs functional organization structure and mission statement

    International Nuclear Information System (INIS)

    Coleman, S.R.

    2000-01-01

    This document provides a description of the functions, structure, commitments, and goals of the Environmental Restoration Contractor Safety and Hygiene Program. The current structure of the ERC Safety and Hygiene organization is described herein

  18. European passive plant program preliminary safety analyses to support system design

    International Nuclear Information System (INIS)

    Saiu, Gianfranco; Barucca, Luciana; King, K.J.

    1999-01-01

    In 1994, a group of European Utilities, together with Westinghouse and its Industrial Partner GENESI (an Italian consortium including ANSALDO and FIAT), initiated a program designated EPP (European Passive Plant) to evaluate Westinghouse Passive Nuclear Plant Technology for application in Europe. In the Phase 1 of the European Passive Plant Program which was completed in 1996, a 1000 MWe passive plant reference design (EP1000) was established which conforms to the European Utility Requirements (EUR) and is expected to meet the European Safety Authorities requirements. Phase 2 of the program was initiated in 1997 with the objective of developing the Nuclear Island design details and performing supporting analyses to start development of Safety Case Report (SCR) for submittal to European Licensing Authorities. The first part of Phase 2, 'Design Definition' phase (Phase 2A) was completed at the end of 1998, the main efforts being design definition of key systems and structures, development of the Nuclear Island layout, and performing preliminary safety analyses to support design efforts. Incorporation of the EUR has been a key design requirement for the EP1000 form the beginning of the program. Detailed design solutions to meet the EUR have been defined and the safety approach has also been developed based on the EUR guidelines. The present paper describes the EP1000 approach to safety analysis and, in particular, to the Design Extension Conditions that, according to the EUR, represent the preferred method for giving consideration to the Complex Sequences and Severe Accidents at the design stage without including them in the design bases conditions. Preliminary results of some DEC analyses and an overview of the probabilistic safety assessment (PSA) are also presented. (author)

  19. Food Safety Program in Asian Countries.

    Science.gov (United States)

    Yamaguchi, Ryuji; Hwang, Lucy Sun

    2015-01-01

    By using the ILSI network in Asia, we are holding a session focused on food safety programs in several Asian areas. In view of the external environment, it is expected to impact the global food system in the near future, including the rapid increase in food demand and in public health services due to population growth, as well as the threats to biosecurity and food safety due to the rapid globalization of the food trade. Facilitating effective information sharing holds promise for the activation of the food industry. At this session, Prof. Hwang shares the current situation of Food Safety and Sanitation Regulations in Taiwan. Dr. Liu provides a talk on the role of risk assessment in food regulatory control focused on aluminum-containing food additives in China. After the JECFA evaluation of aluminum-containing food additives in 2011, each country has carried out risk assessment based on dietary intake surveys. Ms. Chan reports on the activities of a working group on Food Standards Harmonization in ASEAN. She also explains that the ILSI Southeast Asia Region has actively supported the various ASEAN Working Groups in utilizing science to harmonize food standards. Prof. Park provides current research activities in Korea focused on the effect of climate change on food safety. Climate change is generally seen as having a negative impact on food security, particularly in developing countries. We use these four presentations as a springboard to vigorous discussion on issues related to Food Safety in Asia.

  20. A crew resource management program tailored to trauma resuscitation improves team behavior and communication.

    Science.gov (United States)

    Hughes, K Michael; Benenson, Ronald S; Krichten, Amy E; Clancy, Keith D; Ryan, James Patrick; Hammond, Christopher

    2014-09-01

    Crew Resource Management (CRM) is a team-building communication process first implemented in the aviation industry to improve safety. It has been used in health care, particularly in surgical and intensive care settings, to improve team dynamics and reduce errors. We adapted a CRM process for implementation in the trauma resuscitation area. An interdisciplinary steering committee developed our CRM process to include a didactic classroom program based on a preimplementation survey of our trauma team members. Implementation with new cultural and process expectations followed. The Human Factors Attitude Survey and Communication and Teamwork Skills assessment tool were used to design, evaluate, and validate our CRM program. The initial trauma communication survey was completed by 160 team members (49% response). Twenty-five trauma resuscitations were observed and scored using Communication and Teamwork Skills. Areas of concern were identified and 324 staff completed our 3-hour CRM course during a 3-month period. After CRM training, 132 communication surveys and 38 Communication and Teamwork Skills observations were completed. In the post-CRM survey, respondents indicated improvement in accuracy of field to medical command information (p = 0.029); accuracy of emergency department medical command information to the resuscitation area (p = 0.002); and team leader identity, communication of plan, and role assignment (p = 0.001). After CRM training, staff were more likely to speak up when patient safety was a concern (p = 0.002). Crew Resource Management in the trauma resuscitation area enhances team dynamics, communication, and, ostensibly, patient safety. Philosophy and culture of CRM should be compulsory components of trauma programs and in resuscitation of injured patients. Copyright © 2014 American College of Surgeons. Published by Elsevier Inc. All rights reserved.

  1. 14 CFR 91.25 - Aviation Safety Reporting Program: Prohibition against use of reports for enforcement purposes.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 2 2010-01-01 2010-01-01 false Aviation Safety Reporting Program... GENERAL OPERATING AND FLIGHT RULES General § 91.25 Aviation Safety Reporting Program: Prohibition against... to the National Aeronautics and Space Administration under the Aviation Safety Reporting Program (or...

  2. Overview of a radiation safety program in a district style medical environment

    International Nuclear Information System (INIS)

    Wilson, G.

    2006-01-01

    This paper provides an overview of the eight components of a radiation safety program in a large health care facility spread out over several campuses in a large geographic area in Nova Scotia. The main focus is based on those areas that are regulated by the Canadian Nuclear Safety Commission and generally encompass nuclear medicine and radiation therapy operations. X-ray operations are regulated provincially, but the general operational principles of an effective radiation safety program can be applied in all these areas. The main components covered include the set up of an organizational structure that operates separately from individual departments, general items expected from reports to corporate management or regulators, and some examples of the front-line expectations for those in individual departments. The review is not all encompassing, but should give organizations some insight of the magnitude of a radiation safety program in a district style environment. (author)

  3. Improving patient safety in radiation oncology

    International Nuclear Information System (INIS)

    Hendee, William R.; Herman, Michael G.

    2011-01-01

    Beginning in the 1990s, and emphasized in 2000 with the release of an Institute of Medicine report, healthcare providers and institutions have dedicated time and resources to reducing errors that impact the safety and well-being of patients. But in January 2010 the first of a series of articles appeared in the New York Times that described errors in radiation oncology that grievously impacted patients. In response, the American Association of Physicists in Medicine and the American Society of Radiation Oncology sponsored a working meeting entitled ''Safety in Radiation Therapy: A Call to Action''. The meeting attracted 400 attendees, including medical physicists, radiation oncologists, medical dosimetrists, radiation therapists, hospital administrators, regulators, and representatives of equipment manufacturers. The meeting was cohosted by 14 organizations in the United States and Canada. The meeting yielded 20 recommendations that provide a pathway to reducing errors and improving patient safety in radiation therapy facilities everywhere.

  4. 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...

  5. An electronic intervention to improve safety for pain patients co-prescribed chronic opioids and benzodiazepines.

    Science.gov (United States)

    Zaman, Tauheed; Rife, Tessa L; Batki, Steven L; Pennington, David L

    2018-03-29

    Co-prescribing opioids and benzodiazepines increases overdose risk. A paucity of literature exists evaluating strategies to improve safety of co-prescribing. This study evaluated an electronic intervention to improve safety for patients co-prescribed chronic opioids for pain and benzodiazepines at 3 and 6 months. A prospective cohort study was conducted from December 2015 through May 2016 at San Francisco Veterans Affairs Health Care System. A clinical dashboard identified 145 eligible patients prescribed chronic opioids and benzodiazepines. Individualized taper and safety recommendations were communicated to prescribers via electronic medical record progress note and encrypted e-mail at baseline. Primary outcome was number of patients co-prescribed chronic opioids and benzodiazepines. Secondary outcomes included daily dose of opioids and benzodiazepines and number prescribed ≥100 mg morphine equivalent daily dose. Safety outcomes included number with opioid overdose education and naloxone distribution, annual urine drug screening, annual prescription drug monitoring program review, and signed opioid informed consent. Linear mixed models and generalized estimating equations were used to examine within-group change in outcomes between baseline and 3 and 6 months. Among the 145 patients, mean (standard deviation) age was 62 (11) years and 91.7% (133/145) were male. Number co-prescribed significantly decreased from 145/145 (100%) at baseline to 93/139 (67%) at 6-month follow-up (odds ratio [OR] = 0.53, 95% confidence interval [CI]: 0.34-0.81, P = .003). Mean opioid and benzodiazepine doses significantly decreased from 84.61 to 65.63 mg (95% CI: 8.32-27.86, P improve safety for patients co-prescribed chronic opioids for pain and benzodiazepines.

  6. The Role Of Quality Assurance Program For Safety Operation Of Nuclear Installations

    International Nuclear Information System (INIS)

    Harjanto, N.T.; Purwadi, K.P.; Boru, D.S.; Farida; Suharni

    2000-01-01

    Nuclear installations expose potential hazard of radiation, therefore in their construction, operation and maintenance, it is necessary to consider safety aspect, in which the safety requirements which has been determined must be met. One of the requirements that is absolutely needed is quality assurance, which covers arrangement of quality assurance program, organization and administration of the implementation of quality assurance, and supervision. Quality Assurance program is a guideline containing quality policies and basic determination on the realization of activities that effect the quality of equipment's and items used in the operation of nuclear installations in order that the operation of nuclear installation can run safety and in accordance with their design aims and operation limits. Quality Assurance Program includes document control, design control, supply control, control of equipment s and items, operation/process control, inspection and control of equipment test, and control of nonconformance and corrections. General system of nuclear installation operation is equipped with safety and supporting systems. These systems must apply the quality assurance program that cover control of activities in the systems. In the implementation of the quality assurance program, it is necessary to establish procedures, work guidelines/instructions, and quality recording that constitutes documents of quality system 2 nd , 3 th , and 4 th level after the quality assurance program. To ensure the effectivity and to prove whether the realization of the program has been pursuant to the determined requirements, an internal audit must be conducted accordingly

  7. Transportation Safety Excellence in Operations Through Improved Transportation Safety Document

    International Nuclear Information System (INIS)

    Dr. Michael A. Lehto; MAL

    2007-01-01

    A recent accomplishment of the Idaho National Laboratory (INL) Materials and Fuels Complex (MFC) Nuclear Safety analysis group was to obtain DOE-ID approval for the inter-facility transfer of greater-than-Hazard-Category-3 quantity radioactive/fissionable waste in Department of Transportation (DOT) Type A drums at MFC. This accomplishment supported excellence in operations through safety analysis by better integrating nuclear safety requirements with waste requirements in the Transportation Safety Document (TSD); reducing container and transport costs; and making facility operations more efficient. The MFC TSD governs and controls the inter-facility transfer of greater-than-Hazard-Category-3 radioactive and/or fissionable materials in non-DOT approved containers. Previously, the TSD did not include the capability to transfer payloads of greater-than-Hazard-Category-3 radioactive and/or fissionable materials using DOT Type A drums. Previous practice was to package the waste materials to less-than-Hazard-Category-3 quantities when loading DOT Type A drums for transfer out of facilities to reduce facility waste accumulations. This practice allowed operations to proceed, but resulted in drums being loaded to less than the Waste Isolation Pilot Plant (WIPP) waste acceptance criteria (WAC) waste limits, which was not cost effective or operations friendly. An improved and revised safety analysis was used to gain DOE-ID approval for adding this container configuration to the MFC TSD safety basis. In the process of obtaining approval of the revised safety basis, safety analysis practices were used effectively to directly support excellence in operations. Several factors contributed to the success of MFC's effort to obtain approval for the use of DOT Type A drums, including two practices that could help in future safety basis changes at other facilities. (1) The process of incorporating the DOT Type A drums into the TSD at MFC helped to better integrate nuclear safety

  8. Research program on nuclear technology and nuclear safety

    International Nuclear Information System (INIS)

    Dreier, J.

    2010-04-01

    This paper elaborated for the Swiss Federal Office of Energy (SFOE) presents the synthesis report for 2009 made by the SFOE's program leader on the research program concerning nuclear technology and nuclear safety. Work carried out, knowledge gained and results obtained in the various areas are reported on. These include projects carried out in the Laboratory for Reactor Physics and System Behaviour LRS, the LTH Thermohydraulics Laboratory, the Laboratory for Nuclear Materials LNM, the Laboratory for Final Storage Safety LES and the Laboratory for Energy Systems Analysis LEA of the Paul Scherrer Institute PSI. Work done in 2009 and results obtained are reported on, including research on transients in Swiss reactors, risk and human reliability. Work on the 'Proteus' research reactor is reported on, as is work done on component safety. International co-operation in the area of serious accidents and the disposal of nuclear wastes is reported on. Future concepts for reactors and plant life management are discussed. The energy business in general is also discussed. Finally, national and international co-operation is noted and work to be done in 2010 is reviewed

  9. Observed Food Safety Practices in the Summer Food Service Program

    Science.gov (United States)

    Patten, Emily Vaterlaus; Alcorn, Michelle; Watkins, Tracee; Cole, Kerri; Paez, Paola

    2017-01-01

    Purpose/Objectives: The purpose of this exploratory, observational study was three-fold: 1) Determine current food safety practices at Summer Food Service Program (SFSP) sites; 2) Identify types of food served at the sites and collect associated temperatures; and 3) Establish recommendations for food safety training in the SFSP.…

  10. Improving diabetic foot care in a nurse-managed safety-net clinic.

    Science.gov (United States)

    Peterson, Joann M; Virden, Mary D

    2013-05-01

    This article is a description of the development and implementation of a Comprehensive Diabetic Foot Care Program and assessment tool in an academically affiliated nurse-managed, multidisciplinary, safety-net clinic. The assessment tool parallels parameters identified in the Task Force Foot Care Interest Group of the American Diabetes Association's report published in 2008, "Comprehensive Foot Examination and Risk Assessment." Review of literature, Silver City Health Center's (SCHC) 2009 Annual Report, retrospective chart review. Since the full implementation of SCHC's Comprehensive Diabetic Foot Care Program, there have been no hospitalizations of clinic patients for foot-related complications. The development of the Comprehensive Diabetic Foot Assessment tool and the implementation of the Comprehensive Diabetic Foot Care Program have resulted in positive outcomes for the patients in a nurse-managed safety-net clinic. This article demonstrates that quality healthcare services can successfully be developed and implemented in a safety-net clinic setting. ©2012 The Author(s) Journal compilation ©2012 American Association of Nurse Practitioners.

  11. Joint FAM/Line Management Assessment Report on LLNL Machine Guarding Safety Program

    Energy Technology Data Exchange (ETDEWEB)

    Armstrong, J. J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2016-07-19

    The LLNL Safety Program for Machine Guarding is implemented to comply with requirements in the ES&H Manual Document 11.2, "Hazards-General and Miscellaneous," Section 13 Machine Guarding (Rev 18, issued Dec. 15, 2015). The primary goal of this LLNL Safety Program is to ensure that LLNL operations involving machine guarding are managed so that workers, equipment and government property are adequately protected. This means that all such operations are planned and approved using the Integrated Safety Management System to provide the most cost effective and safest means available to support the LLNL mission.

  12. Optimized work control process to improve safety and reliability in a risk-based and deregulated environment

    International Nuclear Information System (INIS)

    Anderson, Jon G.; Jeffries, Jeffrey D. E.; Mairs, Todd P.; Rahn, Frank J.

    1999-01-01

    This paper provides an overview of strategic models to assist power generating plants to improve their work control processes. These models include mechanisms to continually keep the process up to date. Included in the work control process are elements for system cost/performance analysis, life-cycle maintenance planning, on-line scheduling and look-ahead techniques, and schedule implementation to conduct work on the asset. The paper also discusses how risk management associated with work control issues that effect the safety and reliability, as well as O and M costs, is integrated into this strategy. The work control process is a pervasive and critical element in the successful implementation of operations and work management programs. While providing a method to implement maintenance activities in a cost-effective manner, the work control process improves plant safety and system reliability

  13. More safety by improving the safety culture

    International Nuclear Information System (INIS)

    Laaksonen, J.

    1993-01-01

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

  14. Proposal for the improvement of IRD safety culture based on risk analysis

    International Nuclear Information System (INIS)

    Aguiar, L.A.; Ferreira, P.R.R.; Silveira, C.S.

    2017-01-01

    The Safety Culture (SC) is a concept about the relationship of individuals and organizations towards the safety in a specific activity. Any organization that carries out activities with risks has a SC, even at minimum levels. People perceive different types of radiation risks in very different ways, therefore, to identify and to analysis of the possible radiation risks resulting from normal operation or accident conditions is an important issue in order to improve the SC in organization. The main is to present guidelines for the improvement of the safety culture in the Institute of Radiation Protection and Dosimetry - IRD through on risk-based approach. The methodology proposed here is: A) select a division of the IRD for case study; B) assess the level of the 10 culture safety basic elements of the IRD division selected; C) conduct a survey of the hazards and risks associated with the various activities developed by the division; D) reassess the level of the 10 basic elements of CS; And E) analyze the results and correlate the impact of risk knowledge on safety culture improvement. The expected result is improvement the safety and of safety culture by understanding of radiation risks and hazards relating to work and to the working environment; and thus enforce a collective commitment to safety by teams and individuals and raise the safety culture to higher levels. (author)

  15. Proposal for the improvement of IRD safety culture based on risk analysis

    Energy Technology Data Exchange (ETDEWEB)

    Aguiar, L.A.; Ferreira, P.R.R. [Instituto de Radioproteção e Dosimetria (DIRAD/IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Silveira, C.S., E-mail: laguiar@ird.gov.br [Comissão Nacional de Energia Nuclear (DRS/CGMI/CNEN), Rio de Janeiro, RJ (Brazil)

    2017-07-01

    The Safety Culture (SC) is a concept about the relationship of individuals and organizations towards the safety in a specific activity. Any organization that carries out activities with risks has a SC, even at minimum levels. People perceive different types of radiation risks in very different ways, therefore, to identify and to analysis of the possible radiation risks resulting from normal operation or accident conditions is an important issue in order to improve the SC in organization. The main is to present guidelines for the improvement of the safety culture in the Institute of Radiation Protection and Dosimetry - IRD through on risk-based approach. The methodology proposed here is: A) select a division of the IRD for case study; B) assess the level of the 10 culture safety basic elements of the IRD division selected; C) conduct a survey of the hazards and risks associated with the various activities developed by the division; D) reassess the level of the 10 basic elements of CS; And E) analyze the results and correlate the impact of risk knowledge on safety culture improvement. The expected result is improvement the safety and of safety culture by understanding of radiation risks and hazards relating to work and to the working environment; and thus enforce a collective commitment to safety by teams and individuals and raise the safety culture to higher levels. (author)

  16. Using hazard maps to identify and eliminate workplace hazards: a union-led health and safety training program.

    Science.gov (United States)

    Anderson, Joe; Collins, Michele; Devlin, John; Renner, Paul

    2012-01-01

    The Institute for Sustainable Work and Environment and the Utility Workers Union of America worked with a professional evaluator to design, implement, and evaluate the results of a union-led system of safety-based hazard identification program that trained workers to use hazard maps to identify workplace hazards and target them for elimination. The evaluation documented program implementation and impact using data collected from both qualitative interviews and an on-line survey from worker trainers, plant managers, and health and safety staff. Managers and workers reported that not only were many dangerous hazards eliminated as a result of hazard mapping, some of which were long-standing, difficult-to-resolve issues, but the evaluation also documented improved communication between union members and management that both workers and managers agreed resulted in better, more sustainable hazard elimination.

  17. Research Devices Maintenance Programs and Safety Network Infrastructures in Nuclear Malaysia

    International Nuclear Information System (INIS)

    Zainudin Jaafar; Muhammad Zahidee Taat; Ishak Mansor

    2015-01-01

    Instrumentation and Automation Center (PIA) is responsible in carrying out maintenance work for building safety infrastructure and area for nuclear scientific and research work. Care cycle and nuclear scientific tools starting from the preparation of specifications until devices disposal- to get the maximum output from devices therefore PIA has introduced Effective and Comprehensive Maintenance Plan under Management/ Trust/ Development/ Science Fund budgets and also user, Asset Management, caring and handling of the devices. This paper also discussed more on case study related to using and handling so that it can be guidance and standard when its involving mishandling, improper maintenance, inadequacy of supervision and others including improvement suggestion programs. (author)

  18. Advanced power reactors with improved safety characteristics

    International Nuclear Information System (INIS)

    Birkhofer, A.

    1994-01-01

    The primary objective of nuclear safety is the protection of individuals, society and environment against radiological hazards from accidental releases of radioactive materials contained in nuclear reactors. Hereto, these materials are enclosed by several successive barriers and the barriers protected against mishaps and accidents by a multi-level system of safety precautions. The evolution of reactor technology continuously improves this concept and its implementation. At a world-wide scale, several advanced reactor concepts are currently being considered, some of them already at a design stage. Essential safety objectives include both further strengthening the prevention of accidents and improving the containment of fission products should an accident occur. The proposed solutions differ considerably with regard to technical principles, plant size and time scales considered for industrial application. Two typical approaches can be distinguished: The first approach basically aims at an evolution of power reactors currently in use, taking into account the findings from safety research and from operation of current plants. This approach makes maximum use of proven technology and operating experience but may nevertheless include new safety features. The corresponding designs are often termed 'large evolutionary'. The second approach consists in more fundamental changes compared to present designs, often with strong emphasis on specific passive features protecting the fuel and fuel cladding barriers. Owing to the nature and capability of those passive features such 'innovative designs' are mostly smaller in power output. The paper describes the basic objectives of such developments and illustrates important technical concepts focusing on next generation plants, i.e. designs to be available for industrial application until the end of this decade. 1 tab. (author)

  19. Tailoring an educational program on the AHRQ Patient Safety Indicators to meet stakeholder needs: lessons learned in the VA.

    Science.gov (United States)

    Shin, Marlena H; Rivard, Peter E; Shwartz, Michael; Borzecki, Ann; Yaksic, Enzo; Stolzmann, Kelly; Zubkoff, Lisa; Rosen, Amy K

    2018-02-14

    Given that patient safety measures are increasingly used for public reporting and pay-for performance, it is important for stakeholders to understand how to use these measures for improvement. The Agency for Healthcare Research and Quality (AHRQ) Patient Safety Indicators (PSIs) are one particularly visible set of measures that are now used primarily for public reporting and pay-for-performance among both private sector and Veterans Health Administration (VA) hospitals. This trend generates a strong need for stakeholders to understand how to interpret and use the PSIs for quality improvement (QI). The goal of this study was to develop an educational program and tailor it to stakeholders' needs. In this paper, we share what we learned from this program development process. Our study population included key VA stakeholders involved in reviewing performance reports and prioritizing and initiating quality/safety initiatives. A pre-program formative evaluation through telephone interviews and web-based surveys assessed stakeholders' educational needs/interests. Findings from the formative evaluation led to development and implementation of a cyberseminar-based program, which we tailored to stakeholders' needs/interests. A post-program survey evaluated program participants' perceptions about the PSI educational program. Interview data confirmed that the concepts we had developed for the interviews could be used for the survey. Survey results informed us on what program delivery mode and content topics were of high interest. Six cyberseminars were developed-three of which focused on two content areas that were noted of greatest interest: learning how to use PSIs for monitoring trends and understanding how to interpret PSIs. We also used snapshots of VA PSI reports so that participants could directly apply learnings. Although initial interest in the program was high, actual attendance was low. However, post-program survey results indicated that perceptions about the

  20. 45 CFR 1355.35 - Program improvement plans.

    Science.gov (United States)

    2010-10-01

    ... 45 Public Welfare 4 2010-10-01 2010-10-01 false Program improvement plans. 1355.35 Section 1355.35... plans. (a) Mandatory program improvement plan. (1) States found not to be operating in substantial conformity shall develop a program improvement plan. The program improvement plan must: (i) Be developed...

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

    Science.gov (United States)

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

    2015-01-01

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

  2. Characterization and improvement of the nuclear safety culture through self-assessment

    International Nuclear Information System (INIS)

    Levin, H.A.; McGehee, R.B.; Cottle, W.T.

    1996-01-01

    Organizational culture has a powerful influence on overall corporate performance. The ability to sustain superior results in ensuring the public's health and safety is predicated on an organization's deeply embedded values and behavioral norms and how these affect the ability to change and seek continuous improvement. The nuclear industry is developing increased recognition of the relationship of culture to nuclear safety performance as a critical element of corporate strategy. This paper describes a self-assessment methodology designed to characterize and improve the nuclear safety culture, including processes for addressing employee concerns. This methodology has been successfully applied on more than 30 occasions in the last several years, resulting in measurable improvements in safety performance and quality and employee motivation, productivity, and morale. Benefits and lessons learned are also presented

  3. Program plan for evaluation of the Ferrocyanide Waste Tank safety issue at the Hanford Site

    International Nuclear Information System (INIS)

    Borsheim, G.L.; Meacham, J.E.; Cash, R.J.; Dukelow, G.T.

    1994-03-01

    This document describes the background, priorities, strategy and logic, and task descriptions for the Ferrocyanide Waste Tank Safety Program. The Ferrocyanide Safety Program was established in 1990 to provide resolution of a major safety issue identified for 24 high-level radioactive waste tanks at the Hanford Site

  4. Software programming languages for use in developing safety systems of nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jang Soo

    1997-07-01

    This report provides guidance to a verifier on reviewing of programs for safety systems written in the high level languages, such as Ada, C, and C++. The focus of the report is on programming, not design, requirements engineering, or testing. We have defined the attributes, for example, reliability, robustness, traceability, and maintainability, which largely define a general quality of software related to safety. Although an extensive revision to the standard of Ada occurred in 1995, current compiler implementations are insufficiently mature to be considered for safety systems. The discussion on C program emphasized the problem in memory allocation and deallocation, pointers, control flow, and software interface. (author). 26 refs.

  5. Resident work hour restrictions do not improve patient safety in surgery: a critical appraisal based on 7 years of experience in Switzerland

    Directory of Open Access Journals (Sweden)

    Businger Adrian P

    2012-07-01

    Full Text Available Abstract In 2005 the Swiss government implemented new work-hour limitations for all residency programs in Switzerland, including a 50-hour weekly limit. The reduction in the working hours of doctors in training implicate an increase in their rest time and suggest an amelioration of doctors' clinical performance and consequently in patients' outcomes and safety - which was not detectable in a preliminary study at a large referral center in Switzerland. It remains elusive why work-hour restrictions did not improve patient safety. We are well advised to thoroughly examine and eliminate the known adverse effects of reduced work-hours to improve our patients' safety.

  6. 30 CFR 77.1708 - Safety program; instruction of persons employed at the mine.

    Science.gov (United States)

    2010-07-01

    ... at the mine. 77.1708 Section 77.1708 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR COAL MINE SAFETY AND HEALTH MANDATORY SAFETY STANDARDS, SURFACE COAL MINES AND SURFACE WORK AREAS OF UNDERGROUND COAL MINES Miscellaneous § 77.1708 Safety program; instruction of persons...

  7. Orion Heat Shield Manufacturing Producibility Improvements for the EM-1 Flight Test Program

    Science.gov (United States)

    Koenig, William J.; Stewart, Michael; Harris, Richard F.

    2018-01-01

    This paper describes how the ORION program is incorporating improvements in the heat shield design and manufacturing processes reducing programmatic risk and ensuring crew safety in support of NASA's Exploration missions. The approach for the EFT-1 heat shield utilized a low risk Apollo heritage design and manufacturing process using an Avcoat TPS ablator with a honeycomb substrate to provide a one piece heat shield to meet the mission re-entry heating environments. The EM-1 mission will have additional flight systems installed to fly to the moon and return to Earth. Heat shield design and producibility improvements have been incorporated in the EM-1 vehicle to meet deep space mission requirements. The design continues to use the Avcoat material, but in a block configuration to enable improvements in consistant and repeatable application processes using tile bonding experience developed on the Space Shuttle Transportation System Program.

  8. A peer-to-peer traffic safety campaign program.

    Science.gov (United States)

    2014-06-01

    The purpose of this project was to implement a peer-to-peer drivers safety program designed for high school students. : This project builds upon an effective peer-to-peer outreach effort in Texas entitled Teens in the Driver Seat (TDS), the : nati...

  9. Construction safety program for the National Ignition Facility

    Energy Technology Data Exchange (ETDEWEB)

    Cerruti, S.J.

    1997-06-26

    The Construction Safety Program (CSP) for NIF sets forth the responsibilities, guidelines, rules, policies and regulations for all workers involved in the construction, special equipment installation, acceptance testing, and initial activation and operation of NIF at LLNL during the construction period of NIF.

  10. Construction safety program for the National Ignition Facility

    International Nuclear Information System (INIS)

    Cerruti, S.J.

    1997-01-01

    The Construction Safety Program (CSP) for NIF sets forth the responsibilities, guidelines, rules, policies and regulations for all workers involved in the construction, special equipment installation, acceptance testing, and initial activation and operation of NIF at LLNL during the construction period of NIF

  11. Improving health care quality and safety: the role of collective learning

    Directory of Open Access Journals (Sweden)

    Singer SJ

    2015-11-01

    Full Text Available Sara J Singer,1–4 Justin K Benzer,4–6 Sami U Hamdan4,6 1Department of Health Policy and Management, Harvard T.H. Chan School of Public Health, Boston, MA, USA; 2Department of Medicine, Harvard Medical School, Boston, MA, USA; 3Mongan Institute for Health Policy, Massachusetts General Hospital, Boston, MA, USA; 4Center for Healthcare Organization and Implementation Research, VA Boston Healthcare System, Boston, MA, USA; 5VISN 17 Center of Excellence for Research on Returning War Veterans, Waco, TX, USA; 6Department of Health Policy and Management, Boston University School of Public Health, Boston, MA, USA Abstract: Despite decades of effort to improve quality and safety in health care, this goal feels increasingly elusive. Successful examples of improvement are infrequently replicated. This scoping review synthesizes 76 empirical or conceptual studies (out of 1208 originally screened addressing learning in quality or safety improvement, that were published in selected health care and management journals between January 2000 and December 2014 to deepen understanding of the role that collective learning plays in quality and safety improvement. We categorize learning activities using a theoretical model that shows how leadership and environmental factors support collective learning processes and practices, and in turn team and organizational improvement outcomes. By focusing on quality and safety improvement, our review elaborates the premise of learning theory that leadership, environment, and processes combine to create conditions that promote learning. Specifically, we found that learning for quality and safety improvement includes experimentation (including deliberate experimentation, improvisation, learning from failures, exploration, and exploitation, internal and external knowledge acquisition, performance monitoring and comparison, and training. Supportive learning environments are characterized by team characteristics like psychological

  12. An Introduction of Behavior-Based Safety Program in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Lee, Yong Hee; Lim, Hyeon Kyo

    2011-01-01

    There are many methods and approaches for a human error assessment that is valuable for investigating the causes of undesirable events and counter-plans to prevent their recurrence in the nuclear power plants (NPPs). There is behavior-based safety refers to the process of using a proactive approach to safety and health management. It either focuses on risk of behaviors that can lead to an injury, or on safe behaviors that can contribute to injury prevention. Early applications of behavior based safety included the construction and manufacturing industries, but today behavior based safety is applied to a wide variety of industries and service lines. This behavior based safety program can offer a set of significant human error countermeasures to be considered for human error in NPPs as well as other fields of industry. The current methods for the human error prevention in NPPs are several techniques such as Self-Check, Peer Check, Concurrent Verification, 3-way Communication, etc. However, it is not enough to grasp the whole human error problems in operations because the things are needed in fields are a behavior technique not a simple knowledge. Therefore, we applied a behavior based safety program on the current methods

  13. Patient Safety Based Knowledge Management SECI to Improve Nusrsing Students Competency

    Directory of Open Access Journals (Sweden)

    Joanggi Wiriatarina Harianto

    2015-10-01

    Full Text Available Introduction: Patient safety is an important component of health services quality,and  basic principles of patient care. Nursing students also have a great potential to make an action that could endanger the patient, because hospital is one of student practice area. The purpose of this study was to improve the nursing students competency in patient safety by using knowledge management SECI approached. Method: The study used exploratory survey, and quasy experiment. The samples were some of nursing students of STIKes Muhammadiyah Samarinda who were on internship programme that selected using simple random sampling technique, in total of 54 students. This research’s variables were the knowledge management SECI based-patient safety and nursing student’s competency. The data were collected by using questionnaires and observation. The data were analyze by using Partial Least Square (PLS. Result: The result showed that there were significant influence the implementation of a model patient safety based knowledge management seci on increased competence nursing students. Discussion: Improved student competency in patient safety using SECI knowledge management was carried out in four phases, that is Socialization, Externalization, Combination, and Internalization. The result was a new knowledge related to patient safety that able to improve the student’s competency.. Keywords: Patient safety, Knowledge management, SECI, competency

  14. Quarterly report on the Ferrocyanide Safety Program for the period ending, March 31, 1995

    International Nuclear Information System (INIS)

    Cash, R.J.; Meacham, J.E.; Dukelow, G.T.

    1995-04-01

    This quarterly report provides a status of the activities underway on the Ferrocyanide Safety Issue at the Hanford Site, including actions in response to Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 90-7 (FR 1990). In March 1991, a DNFSB implementation plan (Cash 1991) responding to the six parts of Recommendation 90-7 was prepared and sent to the DNFSB. A Ferrocyanide Safety Program Plan addressing the total Ferrocyanide Safety Program, including the six parts of DNFSB Recommendation 90-7, was released in October 1994 (DOE 1994b). Activities in the program plan are underway or have been completed, and the status of each is described in Sections 2.0 and 3.0 of this report

  15. Mark I containment, short term program. Safety evaluation report

    International Nuclear Information System (INIS)

    1977-12-01

    Presented is a Safety Evaluation Report (SER) prepared by the Office of Nuclear Reactor Regulation addressing the Short Term Program (STP) reassessment of the containment systems of operating Boiler Water Reactor (BWR) facilities with the Mark I containment system design. The information presented in this SER establishes the basis for the NRC staff's conclusion that licensed Mark I BWR facilities can continue to operate safely, without undue risk to the health and safety of the public, during an interim period of approximately two years while a methodical, comprehensive Long Term Program (LTP) is conducted. This SER also provides one of the basic foundations for the NRC staff review of the Mark I containment systems for facilities not yet licensed for operation

  16. Evaluation of the food safety training for food handlers in restaurant operations

    OpenAIRE

    Park, Sung-Hee; Kwak, Tong-Kyung; Chang, Hye-Ja

    2010-01-01

    This study examined the extent of improvement of food safety knowledge and practices of employee through food safety training. Employee knowledge and practice for food safety were evaluated before and after the food safety training program. The training program and questionnaires for evaluating employee knowledge and practices concerning food safety, and a checklist for determining food safety performance of restaurants were developed. Data were analyzed using the SPSS program. Twelve restaur...

  17. Institutional glovebox safety committee (IGSC) annual report FY2010

    Energy Technology Data Exchange (ETDEWEB)

    Cournoyer, Michael E [Los Alamos National Laboratory; Roybal, Richard F [Los Alamos National Laboratory; Lee, Roy J [Los Alamos National Laboratory

    2011-01-04

    The Institutional Glovebox Safety Committee (IGSC) was chartered to minimize and/or prevent glovebox operational events. Highlights of the IGSC's third year are discussed. The focus of this working committee is to address glovebox operational and safety issues and to share Lessons Learned, best practices, training improvements, and glovebox glove breach and failure data. Highlights of the IGSC's third year are discussed. The results presented in this annual report are pivotal to the ultimate focus of the glovebox safety program, which is to minimize work-related injuries and illnesses. This effort contributes to the LANL Continuous Improvement Program by providing information that can be used to improve glovebox operational safety.

  18. Improving patient safety: patient-focused, high-reliability team training.

    Science.gov (United States)

    McKeon, Leslie M; Cunningham, Patricia D; Oswaks, Jill S Detty

    2009-01-01

    Healthcare systems are recognizing "human factor" flaws that result in adverse outcomes. Nurses work around system failures, although increasing healthcare complexity makes this harder to do without risk of error. Aviation and military organizations achieve ultrasafe outcomes through high-reliability practice. We describe how reliability principles were used to teach nurses to improve patient safety at the front line of care. Outcomes include safety-oriented, teamwork communication competency; reflections on safety culture and clinical leadership are discussed.

  19. Patient Safety and Healthcare Quality

    Directory of Open Access Journals (Sweden)

    Aikaterini Toska

    2012-01-01

    Full Text Available Introduction: Due to a variety of circumstances and world-wide research findings, patient safety andquality care during hospitalization have emerged as major issues. Patient safety deficits may burdenhealth systems as well as allocated resources. The international community has examined severalproposals covering general and systemic aspects in order to improve patient safety; several long-termprograms and strategies have also been implemented promoting the participation of health-relatedagents, and also government agencies and non-governmental organizations.Aim: Those factors that have negative correlations with patient safety and quality healthcare weredetermined; WHO and EU programs as well as the Greek health policy were also reviewed.Method: Local and international literature was reviewed, including EU and WHO official publications,by using the appropriate keywords.Conclusions: International cooperation on patient safety is necessary in order to improvehospitalization and healthcare quality standards. Such incentives depend heavily on establishing worldwideviable and effective health programs and planning. These improvements also require further stepson safe work procedures, environment safety, hazard management, infection control, safe use ofequipment and medication, and sufficient healthcare staff.

  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. Analyzing and strengthening the vaccine safety program in Manitoba.

    Science.gov (United States)

    Montalban, J M; Ogbuneke, C; Hilderman, T

    2014-12-04

    The emergence of a novel influenza A virus in 2009 and the rapid introduction of new pandemic vaccines prompted an analysis of the current state of the adverse events following immunization (AEFI) surveillance response in several provinces. To highlight aspects of the situational analysis of the Manitoba Health, Healthy Living and Seniors (MHHLS's) AEFI surveillance system and to demonstrate how common business techniques could be usefully applied to a provincial vaccine safety monitoring program. Situational analysis of the AEFI surveillance system in Manitoba was developed through a strengths-weaknesses-opportunities-threats (SWOT) analysis and informed by the National Immunization Strategy vaccine safety priorities. Strategy formulation was developed by applying the threats-opportunities-weaknesses-strengths (TOWS) matrix. Thirteen strategies were formulated that use strengths to either take advantage of opportunities or avoid threats, that exploit opportunities to overcome weaknesses, or that rectify weaknesses to circumvent threats. These strategies entailed the development of various tools and resources, most of which are either actively underway or completed. The SWOT analysis and the TOWS matrix enabled MHHLS to enhance the capacity of its vaccine safety program.

  2. Ostomy Home Skills Program

    Medline Plus

    Full Text Available ... About Quality Programs ACS Leadership in Quality ACS Leadership in Quality Setting the Quality Standard Optimal Resources for Surgical Quality and Safety Inspiring Quality Initiative Resources Continuous Quality Improvement ACS Clinical Scholars in Residence AHRQ Safety Program ...

  3. The Nordic program for nuclear safety 1990-1993

    International Nuclear Information System (INIS)

    1991-02-01

    The status of ongoing projects under The Nordic Program for Nuclear Safety (NKS) 1990-1993, and the economy of the programme is presented. A review of projects, projects managers and coordinators, and a list of members of NKS and associated members is included. (CLS)

  4. Implementing 'Continuous Improvement' in the U.S. Nuclear Regulatory Commission's Decommissioning Program

    International Nuclear Information System (INIS)

    Orlando, D. A.; Buckley, J. T.; Johnson, R. L.; Gillen, D. M.

    2006-01-01

    The United States Nuclear Regulatory Commission's (US NRC's) comprehensive decommissioning program encompasses the decommissioning of all US NRC licensed facilities, ranging from the termination of routine licenses for sealed sources, to the closure of complex materials sites and nuclear power reactor facilities. Of the approximately 200 materials licenses that are terminated each year, most are routine and require little, if any, remediation to meet the US NRC unrestricted release criteria. However, some present technical and policy challenges that require large expenditures of resources, including a few complex materials sites that have requested license termination under the restricted-use provisions of 10 CFR 20.1403. Fiscal constraints to reduce budgeted resources in the decommissioning program, as well as concerns over the time to complete the decommissioning process have led to actions to improve the program and use resources more efficiently. In addition, the US NRC's Strategic Plan requires efforts to identify and implement improvements to US NRC programs in order to improve efficiency, effectiveness, timeliness, and openness, of the US NRC's activities, while maintaining the necessary focus on safety. Decommissioning regulations, and more recently the analysis of several issues associated with implementing those regulations, also have been significant catalysts for improvements in the decommissioning program. Actions in response to these catalysts have resulted in a program focused on the management of complex sites in a comprehensive, consistent, and risk-informed manner, as opposed to the past practice of focusing on sites deemed to be problematic. This paper describes the current status of the decommissioning of US NRC-licensed nuclear facilities, including an overview of recent decommissioning project completion efforts. It provides a detailed summary of past, current, and future improvements in the US NRC decommissioning program including the

  5. The Power of Collaboration for Improving Safety in Complex Systems

    International Nuclear Information System (INIS)

    Hart, C. A.

    2016-01-01

    Many potentially hazardous industries involve systems that consist of a complex array of subsystems that must work together effectively in order for the entire system to perform. Often the subsystems are coupled, such that changes in any one subsystem can affect other subsystems. “System Think” refers to an awareness of the impacts throughout a system of changes in any subsystem. The U.S. commercial aviation industry, in its continuing endeavor to improve safety, uses a collaborative approach to accomplish System Think— bringing all of the key parts of the industry together to work in a collaborative manner to identify and address potential safety concerns. The collaborative approach resulted in an 83% reduction in the fatal accident rate in only 10 years. It also demonstrated that, contrary to conventional wisdom that safety improvements usually hurt productivity, safety improvements that result from a collaborative approach can simultaneously improve productivity. Last but not least, it minimised one of the continuing challenges of making changes in complex systems, which is unintended consequences. The purpose of this presentation is to describe the collaborative approach and to discuss its transferability to other potentially hazardous industries that are seeking to manage their risks more efficiently and effectively. (author)

  6. Introducing the Comprehensive Unit-based Safety Program for mechanically ventilated patients in Saudi Arabian Intensive Care Units

    Directory of Open Access Journals (Sweden)

    Raymond M Khan

    2017-01-01

    Full Text Available Over the past decade, there have been major improvements to the care of mechanically ventilated patients (MVPs. Earlier initiatives used the concept of ventilator care bundles (sets of interventions, with a primary focus on reducing ventilator-associated pneumonia. However, recent evidence has led to a more comprehensive approach: The ABCDE bundle (Awakening and Breathing trial Coordination, Delirium management and Early mobilization. The approach of the Comprehensive Unit-based Safety Program (CUSP was developed by patient safety researchers at the Johns Hopkins Hospital and is supported by the Agency for Healthcare Research and Quality to improve local safety cultures and to learn from defects by utilizing a validated structured framework. In August 2015, 17 Intensive Care Units (ICUs (a total of 271 beds in eight hospitals in the Kingdom of Saudi Arabia joined the CUSP for MVPs (CUSP 4 MVP that was conducted in 235 ICUs in 169 US hospitals and led by the Johns Hopkins Armstrong Institute for Patient Safety and Quality. The CUSP 4 MVP project will set the stage for cooperation between multiple hospitals and thus strives to create a countrywide plan for the management of all MVPs in Saudi Arabia.

  7. Effect of Smaller Left Ventricular Capture Threshold Safety Margins to Improve Device Longevity in Recipients of Cardiac Resynchronization-Defibrillation Therapy.

    Science.gov (United States)

    Steinhaus, Daniel A; Waks, Jonathan W; Collins, Robert; Kleckner, Karen; Kramer, Daniel B; Zimetbaum, Peter J

    2015-07-01

    Device longevity in cardiac resynchronization therapy (CRT) is affected by the pacing capture threshold (PCT) and programmed pacing amplitude of the left ventricular (LV) pacing lead. The aims of this study were to evaluate the stability of LV pacing thresholds in a nationwide sample of CRT defibrillator recipients and to determine potential longevity improvements associated with a decrease in the LV safety margin while maintaining effective delivery of CRT. CRT defibrillator patients in the Medtronic CareLink database were eligible for inclusion. LV PCT stability was evaluated using ≥2 measurements over a 14-day period. Separately, a random sample of 7,250 patients with programmed right atrial and right ventricular amplitudes ≤2.5 V, LV thresholds ≤ 2.5 V, and LV pacing ≥90% were evaluated to estimate theoretical battery longevity improvement using LV safety margins of 0.5 and 1.5 V. Threshold stability analysis in 43,256 patients demonstrated LV PCT stability of 1 V had the greatest increases in battery life (mean increase 0.86 years, 95% confidence interval 0.85 to 0.87). In conclusion, nearly all CRT defibrillator patients had LV PCT stability <1.0 V. Decreasing the LV safety margin from 1.5 to 0.5 V provided consistent delivery of CRT for most patients and significantly improved battery longevity. Copyright © 2015 Elsevier Inc. All rights reserved.

  8. Advancing perinatal patient safety through application of safety science principles using health IT.

    Science.gov (United States)

    Webb, Jennifer; Sorensen, Asta; Sommerness, Samantha; Lasater, Beth; Mistry, Kamila; Kahwati, Leila

    2017-12-19

    The use of health information technology (IT) has been shown to promote patient safety in Labor and Delivery (L&D) units. The use of health IT to apply safety science principles (e.g., standardization) to L&D unit processes may further advance perinatal safety. Semi-structured interviews were conducted with L&D units participating in the Agency for Healthcare Research and Quality's (AHRQ's) Safety Program for Perinatal Care (SPPC) to assess units' experience with program implementation. Analysis of interview transcripts was used to characterize the process and experience of using health IT for applying safety science principles to L&D unit processes. Forty-six L&D units from 10 states completed participation in SPPC program implementation; thirty-two (70%) reported the use of health IT as an enabling strategy for their local implementation. Health IT was used to improve standardization of processes, use of independent checks, and to facilitate learning from defects. L&D units standardized care processes through use of electronic health record (EHR)-based order sets and use of smart pumps and other technology to improve medication safety. Units also standardized EHR documentation, particularly related to electronic fetal monitoring (EFM) and shoulder dystocia. Cognitive aids and tools were integrated into EHR and care workflows to create independent checks such as checklists, risk assessments, and communication handoff tools. Units also used data from EHRs to monitor processes of care to learn from defects. Units experienced several challenges incorporating health IT, including obtaining organization approval, working with their busy IT departments, and retrieving standardized data from health IT systems. Use of health IT played an integral part in the planning and implementation of SPPC for participating L&D units. Use of health IT is an encouraging approach for incorporating safety science principles into care to improve perinatal safety and should be incorporated

  9. Patient safety improvement programmes for primary care. Review of a Delphi procedure and pilot studies by the LINNEAUS collaboration on patient safety in primary care

    Science.gov (United States)

    Verstappen, Wim; Gaal, Sander; Esmail, Aneez; Wensing, Michel

    2015-01-01

    ABSTRACT Background: To improve patient safety it is necessary to identify the causes of patient safety incidents, devise solutions and measure the (cost-) effectiveness of improvement efforts. Objective: This paper provides a broad overview with practical guidance on how to improve patient safety. Methods: We used modified online Delphi procedures to reach consensus on methods to improve patient safety and to identify important features of patient safety management in primary care. Two pilot studies were carried out to assess the value of prospective risk analysis (PRA), as a means of identifying the causes of a patient safety incident. Results: A range of different methods can be used to improve patient safety but they have to be contextually specific. Practice organization, culture, diagnostic errors and medication safety were found to be important domains for further improvement. Improvement strategies for patient safety could benefit from insights gained from research on implementation of evidence-based practice. Patient involvement and prospective risk analysis are two promising and innovative strategies for improving patient safety in primary care. Conclusion: A range of methods is available to improve patient safety, but there is no ‘magic bullet.’ Besides better use of the available methods, it is important to use new and potentially more effective strategies, such as prospective risk analysis. PMID:26339837

  10. Improvement programme of safety performance indicators (SPIs) in Korea

    International Nuclear Information System (INIS)

    Lee, S.Y.

    2001-01-01

    KINS has developed and used Safety Performance Indicators (SPIs), which are count based and composed of 10 indicators in 8 areas, to monitor the trend of performance of NPPs in Korea since 1997. However, the limited usage of SPIs and the increasing worldwide interest on SPIs became the motivation of the SPI improvement programme in Korea. Korea is planning to establish plant performance evaluation programme through analysis of SPI and result of inspection. The SPI improvement programme is a part of the plant performance evaluation programme and includes study on performance evaluation areas, indicator categories, selection and development of indicators, redefinition of indicators and introduction of graphical display system. The selected performance evaluation areas are general performance, reactor safety and radiation safety. Each area will have categories as sub-areas and a total of six categories are selected. One or two indicators for each category are determined or will be developed to make a set of Safety Performance Indicators. Also, a graphic display system will be introduced to extend the usage of SPIs. (author)

  11. Nuclear reactor safety program in U.S. Department of Energy and future perspectives

    International Nuclear Information System (INIS)

    Song, Y.T.

    1987-01-01

    The U.S. Department of Energy (DOE) establishes policy, issues orders, and assures compliance with requirements. The contractors who design, construct, modify, operate, maintain and decommission DOE reactors, set forth the assessment of the safety of cognizant reactors and impliment DOE orders. Teams of experts in the Depatment, through scheduled and unscheduled review programs, reassess the safety of reactors in every phases of their lives. As new technology develops, the safety programs are reevaluated and policies are modified to accommodate these new technologies. The diagnostic capabilities of the computer using multiple alarms to enhance detection of defects and control of a reactor have been greatly utilized in reactor operating systems. The application of artificial intelligence (AI) technologies for diagnostic and even for the decision making process in the event of reactor accidents would be one of the future trends in reactor safety programs. (author)

  12. Containment performance improvement program

    International Nuclear Information System (INIS)

    Beckner, W.; Mitchell, J.; Soffer, L.; Chow, E.; Lane, J.; Ridgely, J.

    1990-01-01

    The Containment Performance Improvement (CPI) program has been one of the main elements in the US Nuclear Regulatory Commission's (NRC's) integrated approach to closure of severe accident issues for US nuclear power plants. During the course of the program, results from various probabilistic risk assessment (PRA) studies and from severe accident research programs for the five US containment types have been examined to identify significant containment challenges and to evaluate potential improvements. The five containment types considered are: the boiling water reactor (BMR) Mark I containment, the BWR Mark II containment, the BWR Mark III containment, the pressurized water reactor (PWR) ice condenser containment, and the PWR dry containments (including both subatmospheric and large subtypes). The focus of the CPI program has been containment performance and accident mitigation, however, insights are also being obtained in the areas of accident prevention and accident management

  13. Identifying the Critical Factors Affecting Safety Program Performance for Construction Projects within Pakistan Construction Industry

    Directory of Open Access Journals (Sweden)

    Zubair Ahmed Memon

    2013-04-01

    Full Text Available Many studies have shown that the construction industry one of the most hazardous industries with its high rates of fatalities and injuries and high financial losses incurred through work related accident. To reduce or overcome the safety issues on construction sites, different safety programs are introduced by construction firms. A questionnaire survey study was conducted to highlight the influence of the Construction Safety Factors on safety program implementation. The input from the questionnaire survey was analyzed by using AIM (Average Index Method and rank correlation test was conducted between different groups of respondents to measure the association between different groups of respondent. The finding of this study highlighted that management support is the critical factor for implementing the safety program on projects. From statistical test, it is concluded that all respondent groups were strongly in the favor of management support factor as CSF (Critical Success Factor. The findings of this study were validated on selected case studies. Results of the case studies will help to know the effect of the factors on implementing safety programs during the execution stage.

  14. Challenges in promoting radiation safety culture

    International Nuclear Information System (INIS)

    Mod Ali, Noriah

    2008-01-01

    Safety has quickly become an industry performance measure, and the emphasis on its reliability has always been part of a strategic commitment. This paper presents an approach taken by Malaysian Nuclear Agency (Nuclear Malaysia) and authority to develop and implement safety culture for industries that uses radioactive material and radiation sources. Maintaining and improving safety culture is a continuous process. There is a need to establish a program to measure, review and audit health and safety performance against predetermined standards. Proper safety audit will help to identify the non-compliance of safety culture as well as the deviation of management, individual and policy level commitment; review of radiation protection program and activities should be preceded. (author)

  15. [An approach to care indicators benchmarking. Learning to improve patient safety].

    Science.gov (United States)

    de Andrés Gimeno, B; Salazar de la Guerra, R M; Ferrer Arnedo, C; Revuelta Zamorano, M; Ayuso Murillo, D; González Soria, J

    2014-01-01

    Improvements in clinical safety can be achieved by promoting a safety culture, professional training, and learning through benchmarking. The aim of this study was to identify areas for improvement after analysing the safety indicators in two public Hospitals in North-West Madrid Region. Descriptive study performed during 2011 in Hospital Universitario Puerta de Hierro Majadahonda (HUPHM) and Hospital de Guadarrama (HG). The variables under study were 40 indicators on nursing care related to patient safety. Nineteen of them were defined in the SENECA project as care quality standards in order to improve patient safety in the hospitals. The data collected were clinical history, Madrid Health Service assessment reports, care procedures, and direct observation Within the 40 indicators: 22 of them were structured (procedures), HUPHM had 86%, and HG 95% 14 process indicators (training and protocols compliance) with similar results in both hospitals, apart from the care continuity reports and training in hand hygiene. The 4 results indicators (pressure ulcer, falls and pain) showed different results. The analysis of the indicators allowed the following actions to be taken: to identify improvements to be made in each hospital, to develop joint safety recommendations in nursing care protocols in prevention and treatment of chronic wound, to establish systematic pain assessments, and to prepare continuity care reports on all patients transferred from HUPHM to HG. Copyright © 2013 SECA. Published by Elsevier Espana. All rights reserved.

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

    Energy Technology Data Exchange (ETDEWEB)

    1980-10-01

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

  17. Radiation safety and protection in US dental hygiene programs

    International Nuclear Information System (INIS)

    Farman, A.G.; Hunter, N.; Grammer, S.

    1986-01-01

    A survey of radiation safety and protection measures used by programs teaching dental hygiene indicated some areas for concern. No barriers or radiation shieldings were used between operator and patient in four programs. Radiation monitoring devices were not worn by faculty operators in 16% of the programs. Fewer than half of the programs used thyroid shields for patients on a routine basis. Insufficient filtration for the kilovolt peak employed was used by 14% of the programs, and for 19% more the filtration was unknown or unspecified. Three programs used closed cones. Rectangular collimation was not used at all by 63% of the programs, and only 20% used E speed film routinely. Quality assurance for equipment maintenance and for film processing were in place at only 54% and 49% of the programs, respectively

  18. Improved safety at CERN

    CERN Multimedia

    2006-01-01

    As announced in Weekly Bulletin No. 43/2006, a new approach to the implementation of Safety at CERN has been decided, which required taking some managerial decisions. The guidelines of the new approach are described in the document 'New approach to Safety implementation at CERN', which also summarizes the main managerial decisions I have taken to strengthen compliance with the CERN Safety policy and Rules. To this end I have also reviewed the mandates of the Safety Commission and the Safety Policy Committee (SAPOCO). Some details of the document 'Safety Policy at CERN' (also known as SAPOCO42) have been modified accordingly; its essential principles, unchanged, remain the basis for the safety policy of the Organisation. I would also like to inform you that I have appointed Dr M. Bona as the new Head of the Safety Commission until 31.12.2008, and that I will proceed soon to the appointment of the members of the new Safety Policy Committee. All members of the personnel are deemed to have taken note of the d...

  19. UMTRA project office federal employee occupational safety and health program plan

    International Nuclear Information System (INIS)

    1994-06-01

    This document establishes the Federal Employee Occupational Safety and Health (FEOSH) Program for the US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project Office. This program will ensure compliance with applicable requirements of DOE Order 3790.1B and DOE Albuquerque Operations Office (AL) Order 3790.lA. FEOSH Program responsibilities delegated by the DOE-AL to the UMTRA Project Office by AL Order 3790.1A also are assigned. The UMTRA Project Office has developed the UMTRA Project Environmental, Safety, and Health (ES ampersand H) Plan (DOE, 1992), which establishes the basic programmatic ES ampersand H requirements for all participants on the UMTRA Project. The ES ampersand H plan is designed primarily to cover remedial action activities at UMTRA sites and defines the ES ampersand H responsibilities of both the UMTRA Project Office and its contractors. The UMTRA FEOSH Program described herein is a subset of the overall UMTRA ES ampersand H program and covers only federal employees working on the UMTRA Project

  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

    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