John M. Eisenberg Patient Safety Awards. System innovation: Veterans Health Administration National Center for Patient Safety.

Science.gov (United States)

Heget, Jeffrey R; Bagian, James P; Lee, Caryl Z; Gosbee, John W

2002-12-01

In 1998 the Veterans Health Administration (VHA) created the National Center for Patient Safety (NCPS) to lead the effort to reduce adverse events and close calls systemwide. NCPS's aim is to foster a culture of safety in the Department of Veterans Affairs (VA) by developing and providing patient safety programs and delivering standardized tools, methods, and initiatives to the 163 VA facilities. To create a system-oriented approach to patient safety, NCPS looked for models in fields such as aviation, nuclear power, human factors, and safety engineering. Core concepts included a non-punitive approach to patient safety activities that emphasizes systems-based learning, the active seeking out of close calls, which are viewed as opportunities for learning and investigation, and the use of interdisciplinary teams to investigate close calls and adverse events through a root cause analysis (RCA) process. Participation by VA facilities and networks was voluntary. NCPS has always aimed to develop a program that would be applicable both within the VA and beyond. NCPS's full patient safety program was tested and implemented throughout the VA system from November 1999 to August 2000. Program components included an RCA system for use by caregivers at the front line, a system for the aggregate review of RCA results, information systems software, alerts and advisories, and cognitive acids. Following program implementation, NCPS saw a 900-fold increase in reporting of close calls of high-priority events, reflecting the level of commitment to the program by VHA leaders and staff.

Stennis Space Center observes 2009 Safety and Health Day

Science.gov (United States)

2009-01-01

Sue Smith, a medical clinic employee at NASA's John C. Stennis Space Center, takes the temperature of colleague Karen Badon during 2009 Safety and Health Day activities Oct. 22. Safety Day activities included speakers, informational sessions and a number of displays on safety and health issues. Astronaut Dominic Gorie also visited the south Mississippi rocket engine testing facility during the day to address employees and present several Silver Snoopy awards for outstanding contributions to flight safety and mission success. The activities were part of an ongoing safety and health emphasis at Stennis.

International Nuclear Safety Center (INSC) database

International Nuclear Information System (INIS)

Sofu, T.; Ley, H.; Turski, R.B.

1997-01-01

As an integral part of DOE's International Nuclear Safety Center (INSC) at Argonne National Laboratory, the INSC Database has been established to provide an interactively accessible information resource for the world's nuclear facilities and to promote free and open exchange of nuclear safety information among nations. The INSC Database is a comprehensive resource database aimed at a scope and level of detail suitable for safety analysis and risk evaluation for the world's nuclear power plants and facilities. It also provides an electronic forum for international collaborative safety research for the Department of Energy and its international partners. The database is intended to provide plant design information, material properties, computational tools, and results of safety analysis. Initial emphasis in data gathering is given to Soviet-designed reactors in Russia, the former Soviet Union, and Eastern Europe. The implementation is performed under the Oracle database management system, and the World Wide Web is used to serve as the access path for remote users. An interface between the Oracle database and the Web server is established through a custom designed Web-Oracle gateway which is used mainly to perform queries on the stored data in the database tables

Business of Nuclear Safety Analysis Office, Nuclear Technology Test Center

International Nuclear Information System (INIS)

Hayakawa, Masahiko

1981-01-01

The Nuclear Technology Test Center established the Nuclear Safety Analysis Office to execute newly the works concerning nuclear safety analysis in addition to the works related to the proving tests of nuclear machinery and equipments. The regulations for the Nuclear Safety Analysis Office concerning its organization, business and others were specially decided, and it started the business formally in August, 1980. It is a most important subject to secure the safety of nuclear facilities in nuclear fuel cycle as the premise of developing atomic energy. In Japan, the strict regulation of safety is executed by the government at each stage of the installation, construction, operation and maintenance of nuclear facilities, based on the responsibility for the security of installers themselves. The Nuclear Safety Analysis Office was established as the special organ to help the safety examination related to the installation of nuclear power stations and others by the government. It improves and puts in order the safety analysis codes required for the cross checking in the safety examination, and carries out safety analysis calculation. It is operated by the cooperation of the Science and Technology Agency and the Agency of Natural Resources and Energy. The purpose of establishment, the operation and the business of the Nuclear Safety Analysis Office, the plan of improving and putting in order of analysis codes, and the state of the similar organs in foreign countries are described. (Kako, I.)

Key Problems of Fire Safety Enforcement in Traffic and Communication Centers (TCC)

Science.gov (United States)

Medyanik, M.; Zosimova, O.

2017-10-01

A Traffic and Communication Center (TCC) means facilities designed and used to distribute and redirect flows of humans and motor vehicles while they get serviced and operate. This paper sets forth the basic problems of fire safety enforcement on the TCC, and the causes that slow down human and vehicle traffic speeds. It proposes ways to solve the problems of fire safety enforcement on the TCC, in the Russian Federation and elsewhere. Engineering solutions are proposed for TCC design, with key outlooks of TCC future development as an alternative way to organize access in transportation.

National Resource Center for Health and Safety in Child Care and Early Education

Science.gov (United States)

... National Resource Center for Health and Safety in Child Care and Early Education (NRC) at the University of Colorado College of ... National Resource Center for Health and Safety in Child Care and Early Education Email: info@NRCKids.org Please read our disclaimer ...

Knowledge management: Role of the the Radiation Safety Information Computational Center (RSICC)

Science.gov (United States)

Valentine, Timothy

2017-09-01

The Radiation Safety Information Computational Center (RSICC) at Oak Ridge National Laboratory (ORNL) is an information analysis center that collects, archives, evaluates, synthesizes and distributes information, data and codes that are used in various nuclear technology applications. RSICC retains more than 2,000 software packages that have been provided by code developers from various federal and international agencies. RSICC's customers (scientists, engineers, and students from around the world) obtain access to such computing codes (source and/or executable versions) and processed nuclear data files to promote on-going research, to ensure nuclear and radiological safety, and to advance nuclear technology. The role of such information analysis centers is critical for supporting and sustaining nuclear education and training programs both domestically and internationally, as the majority of RSICC's customers are students attending U.S. universities. Additionally, RSICC operates a secure CLOUD computing system to provide access to sensitive export-controlled modeling and simulation (M&S) tools that support both domestic and international activities. This presentation will provide a general review of RSICC's activities, services, and systems that support knowledge management and education and training in the nuclear field.

Criticality Safety Information Resource Center Web portal: www.csirc.net

International Nuclear Information System (INIS)

Harmon, C.D. II; Jones, T.

2000-01-01

The Nuclear Criticality Safety Group (ESH-6) at Los Alamos National Laboratory (LANL) is in the process of collecting and archiving historical and technical information related to nuclear criticality safety from LANL and other facilities. In an ongoing effort, this information is being made available via the Criticality Safety Information Resource Center (CSIRC) web site, which is hosted and maintained by ESH-6 staff. Recently, the CSIRC Web site was recreated as a Web portal that provides the criticality safety community with much more than just archived data

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

Kazakhstan center of nuclear technology safety. Approach of work, possibilities and plans

International Nuclear Information System (INIS)

Tazhibaeva, I.L; Romanenko, O.G.; Cherepnin, Yu. S.; Planchon, H.P; Imel, G; Newton, D.

2000-01-01

NTSC was created in November, 1997 as an association of experts in all the areas of nuclear and radiation safety and radioactive materials handling The main goal of creation is investigation of safety aspects of nuclear power in the Republic of Kazakhstan, taking into account the interests of environment and human health protection in the regions of nuclear industry units allocation. The Center was created with support and special cooperation with the US, has grown and developed cooperative ties with several other countries.In the report are enumerate the main directions of NTSC activity, general directions of cooperation, current and completed activity, planing activity

Purpose, Principles, and Challenges of the NASA Engineering and Safety Center

Science.gov (United States)

Gilbert, Michael G.

2016-01-01

NASA formed the NASA Engineering and Safety Center in 2003 following the Space Shuttle Columbia accident. It is an Agency level, program-independent engineering resource supporting NASA's missions, programs, and projects. It functions to identify, resolve, and communicate engineering issues, risks, and, particularly, alternative technical opinions, to NASA senior management. The goal is to help ensure fully informed, risk-based programmatic and operational decision-making processes. To date, the NASA Engineering and Safety Center (NESC) has conducted or is actively working over 600 technical studies and projects, spread across all NASA Mission Directorates, and for various other U.S. Government and non-governmental agencies and organizations. Since inception, NESC human spaceflight related activities, in particular, have transitioned from Shuttle Return-to-Flight and completion of the International Space Station (ISS) to ISS operations and Orion Multi-purpose Crew Vehicle (MPCV), Space Launch System (SLS), and Commercial Crew Program (CCP) vehicle design, integration, test, and certification. This transition has changed the character of NESC studies. For these development programs, the NESC must operate in a broader, system-level design and certification context as compared to the reactive, time-critical, hardware specific nature of flight operations support.

Safety and Environment- Masterplan 2020 of DLR's Rocket Test Center Lampoldhausen

Science.gov (United States)

Haberzettl, Andreas; Dommers, Michael

2013-09-01

safety of the test center.The site of Lampoldshausen with its test and supply facilities is subject to the restrictions of the German law BundesImissionsSchutzGesetz (derived from the European SEVESO-II directive) and its relevant ordinances, especially the Hazardous Incident Ordinance. Because of the complex framework effort which guarantees safety and security, Lampoldshausen has invested in people and processes in order to respect the restrictions of all relevant laws and ordinances as well as to guarantee the protection of people and the environment.Therefor a very special Master plan has been developed, with the goal to rearrange the complete testing area in order to be able to divide the area in certain sectors (testing range, technology and bureau) so that future testing enterprises will not affect almost free testing activities inside the site as it is in the present status.The paper provides comprehensive information related to the planned innovations including detailed background facts related to the foreseen safety and security standard applications.

Development of reliability centered maintenance methods and tools

International Nuclear Information System (INIS)

Jacquot, J.P.; Dubreuil-Chambardel, A.; Lannoy, A.; Monnier, B.

1992-12-01

This paper recalls the development of the RCM (Reliability Centered Maintenance) approach in the nuclear industry and describes the trial study implemented by EDF in the context of the OMF (RCM) Project. The approach developed is currently being applied to about thirty systems (Industrial Project). On a parallel, R and D efforts are being maintained to improve the selectivity of the analysis methods. These methods use Probabilistic Safety Study models, thereby guaranteeing better selectivity in the identification of safety critical elements and enhancing consistency between Maintenance and Safety studies. They also offer more detailed analysis of operation feedback, invoking for example Bayes' methods combining expert judgement and feedback data. Finally, they propose a functional and material representation of the plant. This dual representation describes both the functions assured by maintenance provisions and the material elements required for their implementation. In the final chapter, the targets of the future OMF workstation are summarized and the latter's insertion in the EDF information system is briefly described. (authors). 5 figs., 2 tabs., 7 refs

The Role of the Radiation Safety Information Computational Center (RSICC) in Knowledge Management

International Nuclear Information System (INIS)

Valentine, T.

2016-01-01

Full text: The Radiation Safety Information Computational Center (RSICC) is an information analysis center that collects, archives, evaluates, synthesizes and distributes information, data and codes that are used in various nuclear technology applications. RSICC retains more than 2,000 packages that have been provided by contributors from various agencies. RSICC’s customers obtain access to such computing codes (source and/or executable versions) and processed nuclear data files to promote on-going research, to help ensure nuclear and radiological safety, and to advance nuclear technology. The role of such information analysis centers is critical for supporting and sustaining nuclear education and training programmes both domestically and internationally, as the majority of RSICC’s customers are students attending U.S. universities. RSICC also supports and promotes workshops and seminars in nuclear science and technology to further the use and/or development of computational tools and data. Additionally, RSICC operates a secure CLOUD computing system to provide access to sensitive export-controlled modeling and simulation (M&S) tools that support both domestic and international activities. This presentation will provide a general review of RSICC’s activities, services, and systems that support knowledge management and education and training in the nuclear field. (author

Semi-annual report of Nuclear Technology and Development Center (CDTN) - July to December 1988

International Nuclear Information System (INIS)

1989-01-01

The main activities developed by the several divisions of Nuclear Technology Development Center (CDTN) are described, including areas of reactor tecnologies, fuel cycle, materials and component, nuclear safety and tecnical substructure. (C.G.C.) [pt

Development and Validation of a Short-Form Safety Net Medical Home Scale.

Science.gov (United States)

Nocon, Robert S; Gunter, Kathryn E; Gao, Yue; Lee, Sang Mee; Chin, Marshall H

2017-12-01

To develop a short-form Safety Net Medical Home Scale (SNMHS) for assessing patient-centered medical home (PCMH) capability in safety net clinics. National surveys of federally qualified health centers (FQHCs). Interviews with FQHC directors. We constructed three short-form SNMHS versions and examined correlations with full SNMHS and related primary care assessments. We tested usability with FQHC directors and reviewed scale development with an advisory group. Federally qualified health center surveys were administered in 2009 and 2013, by mail and online. Usability testing was conducted through telephone interviews with FQHC directors in 2013. Six-, 12-, and 18-question short-form SNMHS versions had Pearson correlations with full scale of 0.84, 0.92, and 0.96, respectively. All versions showed a level of convergent validity with other primary care assessment scales comparable to the full SNMHS. User testers found short forms to be low-burden, though missing some PCMH concepts. Advisory group members expressed caution over missing concepts and appropriate use of short-form self-assessments. Short-form versions of SNMHS showed strong correlations with full scale and may be useful for brief assessment of safety net PCMH capability. Each short-form SNMHS version may be appropriate for different research, quality improvement, and assessment purposes. © Health Research and Educational Trust.

NASA Engineering and Safety Center (NESC) Enhanced Melamine (ML) Foam Acoustic Test (NEMFAT)

Science.gov (United States)

McNelis, Anne M.; Hughes, William O.; McNelis, Mark E.

2014-01-01

The NASA Engineering and Safety Center (NESC) funded a proposal to achieve initial basic acoustic characterization of ML (melamine) foam, which could serve as a starting point for a future, more comprehensive acoustic test program for ML foam. A project plan was developed and implemented to obtain acoustic test data for both normal and enhanced ML foam. This project became known as the NESC Enhanced Melamine Foam Acoustic Test (NEMFAT). This document contains the outcome of the NEMFAT project.

Poison control centers in developing countries and Asia's need for toxicology education

International Nuclear Information System (INIS)

Makalinao, Irma R.; Awang, Rahmat

2005-01-01

Poison control centers (PCCs) in developing countries have been set up in response to the challenge of decreasing mortality and morbidity from poisoning. The services range from poison information to actual clinical treatment mostly of acute cases. Lately, PCCs have expanded from their traditional role to one that actively engages in community health studies, toxicovigilance along with treatment of chronic poisoning. Recognizing that types of poisoning and specific needs may vary from country to country, toxicology education that addresses these unique regional issues has become more necessary. Toxicology education, both formal and informal, exists in various stages of development in Asia. Clearly, there are gaps that need to be addressed especially in areas where there are no poison centers or where strengthening is necessary. Collaboration between PCCs in developing countries can help augment available resources including human, analytical and technical expertise. The critical mass of trained toxicologists will fill in the demand for clinical and regulatory specialists and educators as well. This paper highlights the experiences and resources available to the Philippine and Malaysian poison centers and the strengths generated by networking and collaboration. The role of Asia Pacific Association of Medical Toxicology (APAMT) as the Science NGO representative to the Intergovernmental Forum on Chemical Safety (IFCS) forum standing committee in promoting chemical safety at the regional level will be discussed. The 'Clearinghouse on the Sound Management of Chemicals', a platform for engaging multi-stakeholder and interdisciplinary partnerships, will be described as a possible model for capacity building to advance chemical safety through education and training not only in developing countries in Asia but globally as well

The occupational safety of health professionals working at community and family health centers.

Science.gov (United States)

Ozturk, Havva; Babacan, Elif

2014-10-01

Healthcare professionals encounter many medical risks while providing healthcare services to individuals and the community. Thus, occupational safety studies are very important in health care organizations. They involve studies performed to establish legal, technical, and medical measures that must be taken to prevent employees from sustaining physical or mental damage because of work hazards. This study was conducted to determine if the occupational safety of health personnel at community and family health centers (CHC and FHC) has been achieved. The population of this cross-sectional study comprised 507 nurses, 199 physicians, and 237 other medical personnel working at a total of 18 family health centers (FHC) and community health centers (CHC) in Trabzon, Turkey. The sample consisted of a total of 418 nurses, 156 physicians, and 123 other medical personnel. Sampling method was not used, and the researchers tried to reach the whole population. Data were gathered with the Occupational Safety Scale (OSS) and a questionnaire regarding demographic characteristics and occupational safety. According to the evaluations of all the medical personnel, the mean ± SD of total score of the OSS was 3.57 ± 0.98; of the OSS's subscales, the mean ± SD of the health screening and registry systems was 2.76 ± 1.44, of occupational diseases and problems was 3.04 ± 1.3 and critical fields control was 3.12 ± 1.62. In addition, occupational safety was found more insufficient by nurses (F = 14.18; P occupational safety to be insufficient as related to protective and supportive activities.

The development of two-phase flow instrumentation at PNC O-arai Engineering Center

International Nuclear Information System (INIS)

Obata, T.; Kobori, T.; Hayamizu, Y.

1975-10-01

This paper reviews development works on the two-phase flow instrumentation carried out at PNC Oarai Engineering Center for FUGEN safety test. The paper describes heater surface temperature measurement, four types of void meters and two steam quality meters. (auth.)

Real-time environmental monitoring at the Japan Nuclear Cycle Development Institute O-arai Engineering Center. Using the internet to promote safety and environmental transparency

International Nuclear Information System (INIS)

Motomatsu, Sheila; Nakashima Inoue, Naoko

2000-12-01

The report documents the results of an effort at the Japan Nuclear Cycle Development Institute O-arai Engineering Center (JNC/OEC) to provide via the Internet, in real-time, environmental monitoring data to promote safety and environmental transparency. Provided in Japanese as well as in English, the Internet site provides assurance that OEC nuclear operations are being conducted in a manner that is safe to both people in the surrounding area and the environment. This work conducted by Environmental Monitoring Team of the OEC Safety Administration Section fulfilled the assignment to release data real-time via the Internet tasked by the Information Disclosure Section of the JNC Headquarters Public Relations Division. The work conducted by the visiting exchange scientist fulfilled the experimental portion of Action Sheet 34 of the Agreement between JNC and DOE for Cooperation in Research and Development Concerning Nuclear Material Control and Accounting Measures for Safeguards and Nonproliferation. In Japan, the project for Action Sheet 34 Personnel Exchange on Remote Monitoring and Transparency' entailed both a study and an experiment on how remote monitoring technologies can be used to promote nonproliferation, environmental and safety transparency. Environmental airborne radionuclide monitoring falls under the definition of remote monitoring technology more broadly defined as 'remotely accessed unattended monitoring system technology'. (author)

Guidelines for PWR safety research and development at NUCLEBRAS - Brazil

International Nuclear Information System (INIS)

Pinheiro, R.B.

1980-06-01

NUCLEBRAS research into different areas of pressurized light-water reactor technology, is one of the aims of its Research and Development Center, Centro de Desenvolvimento da Tecnologia Nuclear (CDTN), in Belo Horizonte. The main effort of the center is now directed to give technical support to the industrial activities of the Nuclear Program, and to carry out R and D work in strainght connection with these activities. As a consequence few work on safety research is actualy being performed, although the number of activities in this field increases steadily, not as a function but strong related to the development of our industrial program. Basic training and qualification of personnel at CDTN for different research and development activities of NUCLEBRAS has high priority. This is covered either by agreements with national institutions (e.g. universities) or using the various possibilities offered by special agreements and cooperation programs with research centers and other institutions, not only but mainly in Germany, F.R. (Author) [pt

FBR Plant Engineering Center annual report 2012

International Nuclear Information System (INIS)

2013-12-01

This annual report shows the last year's R and D activities of currently-reorganized FBR Plant Engineering Center, which was established on April 1, 2009. FBR Safety Technology Center was founded on April 1, 2013 by the consolidation of both the activities of 'former FBR Plant Engineering Center' and a portion of 'FBR Safety Evaluation Unit, Advanced Nuclear System Research and Development Directorate', especially concentrating on safety evaluations and analyses for severe accidents. As for FBR safety technology, it is necessary to continuously make an effort for compliance with new safety regulations in preparation for 'Monju' to restart, for safety enhancement evaluation and for safety technology upgrading. In this context, the new organization was founded in order to reinforce the safety evaluation capability, which will surely and steadily promote FBR safety-technology related activities. As a result, FBR Plant Engineering Center was abolished. This report summarizes the R and D activities at the former FBR Plant Engineering Center, aiming at contributing to the commercialization by using operation experiences and technology development results derived from the actual reactor 'Monju'. The activities are divided into five areas of operation-and-maintenance engineering, sodium engineering, reactor-core-and-fuel engineering, plant engineering, and safety engineering. This annual report is intended for a report of the activities of individual researcher in the center rather than that of the progress of the center as a whole. This will clarify the individual themes, progresses and problems of each researcher, which will, hopefully, facilitate communication with the outside researchers. (author)

Development of a health and safety manual for emergency response operations

International Nuclear Information System (INIS)

Riland, C.A.; Junio, S.S.

2000-01-01

The Federal Radiological Monitoring and Assessment Center (FRMAC) Health and Safety Manual, which has been under development by a multi-agency group, is nearing completion and publication. The manual applies to offsite monitoring during a radiological accident or incident. Though written for multi-agency offsite monitoring activities (FRMAC), the manual is generic in nature and should be readily adaptable for other emergency response operations. Health and safety issues for emergency response situations often differ from those of normal operations. Examples of these differences and methodologies to address these issues are discussed. Challenges in manual development, including lack of regulatory and guidance documentation, are also discussed. One overriding principle in the Health and Safety Manual development is the overall reduction of risk, not just dose. The manual is broken into several chapters, which include Overview of Responsibities, Health Physics, Industrial Hygiene and Safey, Medical, and Environmental Compliance and Records. Included is a series of appendices, which presents additional information on forms and plans for default scenarios

Development of safety related technology and infrastructure for safety assessment

International Nuclear Information System (INIS)

Venkat Raj, V.

1997-01-01

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

The Criticality Safety Information Resource Center (CSIRC) at Los Alamos National Laboratory

International Nuclear Information System (INIS)

Henderson, B.D.; Meade, R.A.; Pruvost, N.L.

1999-01-01

The Criticality Safety Information Resource Center (CSIRC) at Los Alamos National Laboratory (LANL) is a program jointly funded by the U.S. Department of Energy (DOE) and the U.S. Nuclear Regulatory Commission (NRC) in conjunction with the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 97-2. The goal of CSIRC is to preserve primary criticality safety documentation from U.S. critical experimental sites and to make this information available for the benefit of the technical community. Progress in archiving criticality safety primary documents at the LANL archives as well as efforts to make this information available to researchers are discussed. The CSIRC project has a natural linkage to the International Criticality Safety Benchmark Evaluation Project (ICSBEP). This paper raises the possibility that the CSIRC project will evolve in a fashion similar to the ICSBEP. Exploring the implications of linking the CSIRC to the international criticality safety community is the motivation for this paper

Patient-Centered Robot-Aided Passive Neurorehabilitation Exercise Based on Safety-Motion Decision-Making Mechanism

Directory of Open Access Journals (Sweden)

Lizheng Pan

2017-01-01

Full Text Available Safety is one of the crucial issues for robot-aided neurorehabilitation exercise. When it comes to the passive rehabilitation training for stroke patients, the existing control strategies are usually just based on position control to carry out the training, and the patient is out of the controller. However, to some extent, the patient should be taken as a “cooperator” of the training activity, and the movement speed and range of the training movement should be dynamically regulated according to the internal or external state of the subject, just as what the therapist does in clinical therapy. This research presents a novel motion control strategy for patient-centered robot-aided passive neurorehabilitation exercise from the point of the safety. The safety-motion decision-making mechanism is developed to online observe and assess the physical state of training impaired-limb and motion performances and regulate the training parameters (motion speed and training rage, ensuring the safety of the supplied rehabilitation exercise. Meanwhile, position-based impedance control is employed to realize the trajectory tracking motion with interactive compliance. Functional experiments and clinical experiments are investigated with a healthy adult and four recruited stroke patients, respectively. The two types of experimental results demonstrate that the suggested control strategy not only serves with safety-motion training but also presents rehabilitation efficacy.

Report on administrative work at radiation safety center in fiscal year 2003

International Nuclear Information System (INIS)

Uda, Tatsuhiko; Asakura, Yamato; Sakuma, Yoichi; Kawano, Takao; Yamanishi, Hirokuni; Sugiyama, Takahiko; Nishimura, Kiyohiko; Miyake, Hitoshi

2005-06-01

National Institute for Fusion Science constructed the Large Helical Device (LHD) which is the largest magnetic confinement plasma experimental device using super conductive magnet coils system. It took eight years to construct and the first plasma shot was carried out on March 1998. Since then high temperature plasma and improved plasma confinement experiments have been achieved. This is the report on administrative work at the radiation safety center considering radiation protection for workers at the LHD and the Compact Helical Device (CHS), and radiation measurement and monitoring in the site. Major scope is as follows. (1) Radiation (X ray) dose measurement and monitoring in the radiation controlled area and in the site using particularly developed monitoring system named as Radiation Monitoring System Applicable to Fusion Experiments (RMSAFE). (2) Establishment of education and registration system for radiation workers and accessing control system for the LHD controlled area. As same as the published annual reports from fiscal year 1999 to 2002, this report will be helpful for the future radiation safety management in the research institute. (author)

Development of a National Center for Hydrogen Technology

Energy Technology Data Exchange (ETDEWEB)

Jay C. Almlie; Bruce Wood; Rich Schlupp

2007-03-01

In November 2005, the Energy & Environmental Research Center (EERC), ePowerSynergies, Inc. (ePSI), and Resurfice Corporation teamed to develop, produce, and demonstrate the world's first and only fuel cell-powered ice resurfacer. The goals of this project were: {sm_bullet} To educate the public on the readiness, practicality, and safety of fuel cells powered by hydrogen fuel and {sm_bullet} To establish a commercialization pathway in an early-adopter, niche market. The vehicle was developed and produced in a short 3-month span. The vehicle made its world debut at U.S. Senator Byron Dorgan's (D-ND) 2005 Hydrogen Energy Action Summit. Subsequently, the vehicle toured North America appearing at numerous public events and conferences, receiving much attention from international media outlets.

Model-Driven Development of Safety Architectures

Science.gov (United States)

Denney, Ewen; Pai, Ganesh; Whiteside, Iain

2017-01-01

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

Information report on the nuclear safety and radiation protection of the Aube center for short-lived low- and intermediate-level wastes storage - 2011. Annual report in the framework of article 21 of the Act on nuclear transparency and safety

International Nuclear Information System (INIS)

2012-06-01

The National Radioactive Waste Management Agency (Andra), was established by the December 1991 Waste Act as a public body in charge of the long-term management of all radioactive waste, under the supervision of the Ministry of Ecology, Energy, Sustainable Development and the Sea (formerly the Ministry of Industry and the Ministry of Environment), and the Ministry of Research. The Andra operates two storage centers in the Aube region (France): the center for short-lived low- and intermediate-level wastes, and the center for very-low-level radioactive wastes. This document is the 2011 activity report of the center for short-lived low- and intermediate-level wastes. It presents a review of the activities of the center: presentation of the installations, safety and radiation protection, events or incidents, environmental monitoring, wastes management, public information, recommendations of the Health and safety Committee (CHSCT)

The San Diego Center for Patient Safety: Creating a Research, Education, and Community Consortium

National Research Council Canada - National Science Library

Pratt, Nancy; Vo, Kelly; Ganiats, Theodore G; Weinger, Matthew B

2005-01-01

In response to the Agency for Healthcare Research and Quality's Developmental Centers of Education and Research in Patient Safety grant program, a group of clinicians and academicians proposed the San...

Technology and Tool Development to Support Safety and Mission Assurance

Science.gov (United States)

Denney, Ewen; Pai, Ganesh

2017-01-01

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

76 FR 40733 - National Institute for Occupational Safety and Health, (NIOSH), World Trade Center Health Program...

Science.gov (United States)

2011-07-11

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention National Institute for Occupational Safety and Health, (NIOSH), World Trade Center Health Program Science/Technical Advisory Committee (WTCHP-STAC) Correction: This notice was published in the Federal Register on June 23...

Work safety and sustainable development in enterprise

Institute of Scientific and Technical Information of China (English)

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

2005-01-01

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

Developing a strong safety culture - a safety management challenge

International Nuclear Information System (INIS)

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

1995-01-01

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

Anomaly Analysis: NASA's Engineering and Safety Center Checks Recurring Shuttle Glitches

Science.gov (United States)

Morring, Frank, Jr.

2004-01-01

The NASA Engineering and Safety Center (NESC), set up in the wake of the Columbia accident to backstop engineers in the space shuttle program, is reviewing hundreds of recurring anomalies that the program had determined don't affect flight safety to see if in fact they might. The NESC is expanding its support to other programs across the agency, as well. The effort, which will later extend to the International Space Station (ISS), is a principal part of the attempt to overcome the normalization of deviance--a situation in which organizations proceeded as if nothing was wrong in the face of evidence that something was wrong--cited by sociologist Diane Vaughn as contributing to both space shuttle disasters.

Road safety in developing countries.

NARCIS (Netherlands)

Schreuder, D.A.

1991-01-01

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

Engineer Research and Development Center's Materials Testing Center (MTC)

Data.gov (United States)

Federal Laboratory Consortium — The Engineer Research and Development Center's Materials Testing Center (MTC) is committed to quality testing and inspection services that are delivered on time and...

Summary of the function and the safety design of the Tokai Reprocessing Utility Center

International Nuclear Information System (INIS)

Yanai, Chisato; Yamazaki, Toshihiko; Tomita, Tsuneo; Horii, Shinichi; Uryu, Mituru; Ishiguro, Nobuharu; Kobayashi, Kentarou

1998-01-01

The Tokai Reprocessing Utility Center is a new facility to replace the utilities to the Tokai Reprocessing Plant such as the emergency power supply, compressed air, etc. which are scattered about the site and have became superannuated. The Facility building has a base-isolation system that is a strongly resistant to earthquake. After completion, the center will supply utilities to the Main Plant, the Central Building, the Auxiliary Active Facility, etc. of the Tokai Reprocessing Plant. This document outlines the function and the safety design of the Tokai Reprocessing Utility Center. (author)

Setting clear expectations for safety basis development

International Nuclear Information System (INIS)

MORENO, M.R.

2003-01-01

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

76 FR 60503 - Guidance for Industry on Target Animal Safety and Effectiveness Protocol Development and...

Science.gov (United States)

2011-09-29

... Safety and Effectiveness Protocol Development and Submission.'' The purpose of this document is to provide sponsors guidance in preparation of study protocols for review by the Center for Veterinary Medicine, Office of New Animal Drug Evaluation. The recommendations included in this guidance are intended...

Sustainable Development of Food Safety

DEFF Research Database (Denmark)

Fabech, B.; Georgsson, F.; Gry, Jørn

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

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.

Current research and development at the Nuclear Research Center Karlsruhe

International Nuclear Information System (INIS)

Kuesters, H.

1982-01-01

The Nuclear Research Center Karlsruhe (KfK) is funded to 90% by the Federal Republic of Germany and to 10% by the State of Baden-Wuerttemberg. Since its foundation in 1956 the main objective of the Center is research and development (R and D) in the aera of the nuclear technology and about 2/3 of the research capacity is now devoted to this field. Since 1960 a major activity of KfK is R and D work for the design of fast breeder reactors, including material research, physics, and safety investigations; a prototype of 300 MWe is under construction now in the lower Rhine Valley. For enrichment of 235 U fissile material KfK developed the separation nozzle process; its technical application is realized within an international contract between the Federal Republic of Germany and Brazil. Within the frame of the European Programme on fusion technology KfK develops and tests superconducting magnets for toroidal fusion systems; a smaller activity deals with research on inertial confinement fusion. A broad research programme is carried through for safety investigations of nuclear installations, especially for PWRs; this activity is supplemented by research and development in the field of nuclear materials' safeguards. Development of fast reactors has to initiate research for the reprocessing of spent fuel and waste disposal. In the pilot plant WAK spent fuel from LKWs is reprocessed; research especially tries e.g. to improve the PUREX-process by electrochemical means, vitrification of high active waste is another main activity. First studies are being performed now to clarify the necessary development for reprocessing fast reactor fuel. About 1/3 of the research capacity of KfK deals with fundamental research in nuclear physics, solid state physics, biology and studies on the impact of technology on environment. Promising new technologies as e.g. the replacement of gasoline by hydrogen cells as vehicle propulsion are investigated. (orig.)

Safety guides development process in Spain

International Nuclear Information System (INIS)

Butragueno, J.L.; Perello, M.

1979-01-01

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

The development of safety requirements

International Nuclear Information System (INIS)

Jorel, M.

2009-01-01

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

Development of safety analysis technology for integral reactor

Energy Technology Data Exchange (ETDEWEB)

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

1999-03-01

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

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

Development of a Reliability Program approach to assuring operational nuclear 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 used in other high technology industries is being formulated for potential application in the nuclear power industry. Research findings are discussed. The reliability methods employed under NASA and military direction, commercial airline and related FAA programs were surveyed with several reliability concepts (e.g., quantitative reliability goals, reliability centered maintenance) appearing to be directly transferable. Other tasks in the RP development effort involved the benchmarking and evaluation of the existing nuclear regulations and practices relevant to safety/reliability integration. A review of current risk-dominant issues was also conducted using results from existing probabilistic risk assessment studies. The ongoing RP development tasks have concentrated on defining a RP for the operating phase of a nuclear plant's lifecycle. The RP approach incorporates safety systems risk/reliability analysis and performance monitoring activities with dedicated tasks that integrate these activities with operating, 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 RP

Manpower development and international cooperation in Nuclear Technology and Education Center, JAERI

International Nuclear Information System (INIS)

Shiba, Koreyuki; Tojo, Takao; Takada, Kazuo; Nomura, Masayuki

1996-01-01

Nuclear Technology and Education Center was founded in 1958 and now has two branches, Tokyo Education Center at Bunkyo-ku, Tokyo and Tokai Education Center at Tokai, Ibaraki-ken. The objective was to educate and train nuclear engineers and scientists for implementing the nation's program of atomic energy research, development and utilization. A variety of training courses have been prepared and carried out to meet the requirements of the nuclear community. In recent years, activities of getting the public acceptance have become important for nuclear energy deployment in Japan. Many short courses have been implemented at JAERI sites and cities for providing the public including high school teachers with basic knowledge on nuclear energy. International training programs of the center were started with the cooperation of the Japan International Cooperation Agency (JICA) in 1985 and of the International Atomic Energy Agency (IAEA) in 1987. International seminars were implemented for improving nuclear safety by inviting participants from the former Soviet Union, central/east European countries and the neighboring countries of Japan under the direction of the Science and Technology Agency (STA) in 1992. STA and JAERI are starting new programs of helping Asian and Pacific countries to develop nuclear manpower. (author)

International Nuclear Safety Center database on thermophysical properties of reactor materials

International Nuclear Information System (INIS)

Fink, J.K.; Sofu, T.; Ley, H.

1997-01-01

The International Nuclear Safety Center (INSC) database has been established at Argonne National Laboratory to provide easily accessible data and information necessary to perform nuclear safety analyses and to promote international collaboration through the exchange of nuclear safety information. The INSC database, located on the World Wide Web at http://www.insc.anl.gov, contains critically assessed recommendations for reactor material properties for normal operating conditions, transients, and severe accidents. The initial focus of the database is on thermodynamic and transport properties of materials for water reactors. Materials that are being included in the database are fuel, absorbers, cladding, structural materials, coolant, and liquid mixtures of combinations of UO 2 , ZrO 2 , Zr, stainless steel, absorber materials, and concrete. For each property, the database includes: (1) a summary of recommended equations with uncertainties; (2) a detailed data assessment giving the basis for the recommendations, comparisons with experimental data and previous recommendations, and uncertainties; (3) graphs showing recommendations, uncertainties, and comparisons with data and other equations; and (4) property values tabulated as a function of temperature

Development and Validation of Quality Criteria for Providing Patient- and Family-centered Injury Care.

Science.gov (United States)

Boyd, Jamie M; Burton, Rachael; Butler, Barb L; Dyer, Dianne; Evans, David C; Felteau, Melissa; Gruen, Russell L; Jaffe, Kenneth M; Kortbeek, John; Lang, Eddy; Lougheed, Val; Moore, Lynne; Narciso, Michelle; Oxland, Peter; Rivara, Frederick P; Roberts, Derek; Sarakbi, Diana; Vine, Karen; Stelfox, Henry T

2017-08-01

The aim of this study was to develop and evaluate the content validity of quality criteria for providing patient- and family-centered injury care. Quality criteria have been developed for clinical injury care, but not patient- and family-centered injury care. Using a modified Research AND Development Corporation (RAND)/University of California, Los Angeles (UCLA) Appropriateness Methodology, a panel of 16 patients, family members, injury and quality of care experts serially rated and revised criteria for patient- and family-centered injury care identified from patient and family focus groups. The criteria were then sent to 384 verified trauma centers in the United States, Canada, Australia, and New Zealand for evaluation. A total of 46 criteria were rated and revised by the panel over 4 rounds of review producing 14 criteria related to clinical care (n = 4; transitions of care, pain management, patient safety, provider competence), communication (n = 3; information for patients/families; communication of discharge plans to patients/families, communication between hospital and community providers), holistic care (n = 4; patient hygiene, kindness and respect, family access to patient, social and spiritual support) and end-of-life care (n = 3; decision making, end-of-life care, family follow-up). Medical directors, managers, or coordinators representing 254 trauma centers (66% response rate) rated 12 criteria to be important (95% of responses) for patient- and family-centered injury care. Fewer centers rated family access to the patient (80%) and family follow-up after patient death (65%) to be important criteria. Fourteen-candidate quality criteria for patient- and family-centered injury care were developed and shown to have content validity. These may be used to guide quality improvement practices.

Automated system for the management of the radiological safety in a radiopharmaceutical and labelled compounds production center

International Nuclear Information System (INIS)

Amador B, Z.H.; Alvarez Builla de Sologuren, E.

2006-01-01

The establishment in the Center of Isotopes of Cuba of a managerial quality system in matter of radiological safety Y the accumulated operational experience, its constitute the foundations for the development of a system of management of the radiological safety organically structured, with the application of evaluative techniques of it management Y it integration in an automated system. The Visual Basic 5 platform for the programming of the 'SASR' system is used. The functions of each one of the 11 modules that integrate it are described. With this it can be carried out the registration of the data of the training Y the personnel's authorization, the checkup of the radioactive inventory of the installation, the annual upgrade of the registrations of the individual doses of those workers, the analysis of the state of the available equipment for magnitude to control, the radiological situation of the work positions, the public exposure by the gassy discharges, the experiences of the radiological events, the annual consolidation of the costs of the safety Y the evaluation of indicators Y of tendencies. A computer tool that facilitates the effective management of the radiological safety in a radioactive installation is obtained. (Author)

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.

SAFETY BASIS DESIGN DEVELOPMENT CHALLENGES IMECE2007-42747

Energy Technology Data Exchange (ETDEWEB)

RYAN GW

2007-09-24

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

SAFETY BASIS DESIGN DEVELOPMENT CHALLENGES IMECE2007-42747

International Nuclear Information System (INIS)

RYAN GW

2007-01-01

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

Safety culture development at Daya Bay NPP

International Nuclear Information System (INIS)

Zhang Shanming

2001-01-01

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

The International Science and Technology Center (ISTC) and ISTC projects related to nuclear safety. Information review

International Nuclear Information System (INIS)

Tocheny, Lev V.

2003-01-01

The ISTC is an intergovernmental organization created ten years ago by Russia, USA, EU and Japan in Moscow. The Center supports numerous science and technology projects in different areas, from biotechnologies and environmental problems to all aspects of nuclear studies, including those focused on the development of effective innovative concepts and technologies in the nuclear field, in general, and for improvement of nuclear safety, in particular. The presentation addresses some technical results of the ISTC projects as well as methods and approaches employed by the ISTC to foster close international collaboration and manage projects towards fruitful results. (author)

Safety culture development in nuclear electric plc

International Nuclear Information System (INIS)

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

1995-01-01

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

Development of nuclear safety issues program

Energy Technology Data Exchange (ETDEWEB)

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

2006-12-15

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

Development of nuclear safety issues program

International Nuclear Information System (INIS)

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

2006-12-01

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

Developing safety culture in nuclear power engineering

International Nuclear Information System (INIS)

Tevlin, S.A.

2000-01-01

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

Small Business Development Center

Data.gov (United States)

Small Business Administration — Small Business Development Centers (SBDCs) provide assistance to small businesses and aspiring entrepreneurs throughout the United States and its territories. SBDCs...

Impact of biomarker development on drug safety assessment

International Nuclear Information System (INIS)

Marrer, Estelle; Dieterle, Frank

2010-01-01

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

Safety culture assessment developed by JANTI

International Nuclear Information System (INIS)

Hamada, Jun

2009-01-01

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

Carbon Monoxide Information Center

Medline Plus

Full Text Available ... OnSafety Blog Safety Education Centers Neighborhood Safety Network Community Outreach Resource Center Toy Recall Statistics CO Poster ... Sitemap RSS E-mail Inside CPSC Accessibility Privacy Policy Budget, Performances & Finance Open Government Freedom of Information ( ...

Neonatal Safety of Elective Family-Centered Caesarean Sections: A Cohort Study

Directory of Open Access Journals (Sweden)

Ilona C. Narayen

2018-02-01

Full Text Available BackgroundAlthough little data are available concerning safety for newborns, family-centered caesarean sections (FCS are increasingly implemented. With FCS mothers can see the delivery of their baby, followed by direct skin-to-skin contact. We evaluated the safety for newborns born with FCS in the Leiden University Medical Center (LUMC, where FCS was implemented in June 2014 for singleton pregnancies with a gestational age (GA ≥38 weeks and without increased risks for respiratory morbidity.MethodsThe incidence of respiratory pathology, unplanned admission, and hypothermia in infants born after FCS in LUMC were retrospectively reviewed and compared with a historical cohort of standard elective cesarean sections (CS.ResultsFrom June 2014 to November 2015, 92 FCS were performed and compared to 71 standard CS in 2013. Incidence of respiratory morbidity, hypothermia, temperatures at arrival at the department, GA, and birth weight were comparable (ns. Unplanned admission occurred more often after FCS when compared to standard CS (21 vs 7%; p = 0.03, probably due to peripheral oxygen saturation (SpO2 monitoring. There was no increase in respiratory pathology (8 vs 6%, ns. One-third of the babies were separated from their mother during or after FCS.ConclusionUnplanned neonatal admissions after elective CS increased after implementing FCS, without an increase in respiratory morbidity or hypothermia. SpO2 monitoring might have a contribution. Separation from the mother occurred often.

Development of Safety Culture Indicators for HANARO

International Nuclear Information System (INIS)

Wu, Jong-Sup; Lee, Kye-Hong

2007-01-01

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

Building Up an On-Line Plant Information System for the Emergency Response Center of the Hungarian Nuclear Safety Directorate

International Nuclear Information System (INIS)

Vegh, Janos; Major, Csaba; Horvath, Csaba; Hozer, Zoltan; Adorjan, Ferenc; Lux, Ivan; Horvath, Kristof

2002-01-01

The main design features, services, and human-machine interface characteristics are described of the CERTA VITA on-line plant information system developed and installed by KFKI AEKI at the Nuclear Safety Directorate (NSD) of the Hungarian Atomic Energy Authority (HAEA) in cooperation with experts from the NSD. The Center for Emergency Response, Training, and Analysis (CERTA) located at the headquarters of NSD, Budapest, Hungary, was established in 1997. The center supports the NSD installation, radiological monitoring, and advisory team in case of nuclear emergencies, with appropriate hardware and software for communication, diagnosis, prognosis, and prediction. The vital information transfer and analysis (VITA) system represents an important part of the CERTA, as it provides for the continuous remote inspection of the four VVER-440/V213 units of the Hungarian Paks nuclear power plant (NPP). The on-line information system maintains a continuous data link with the NPP through a managed leased line that connects CERTA to a gateway computer located at the Paks NPP. The present scope of the system is a result of a 4-yr development project: In addition to the basic safety parameter display functions, the VITA system now includes an on-line break parameter estimation module, an extensive training package based on simulated transients, and on-line data transfer capabilities to feed accident diagnosis/analysis codes

Safety policy for nuclear power development

International Nuclear Information System (INIS)

Uchida, Hideo

1987-01-01

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

Report on administrative work at radiation safety center in fiscal year 2000

Energy Technology Data Exchange (ETDEWEB)

Uda, Tatsuhiko; Sakuma, Yoichi; Kawano, Takao; Yamanishi, Hirokuni; Shinotsuka, Kazunori; Asakura, Yamato; Miyake, Hitoshi

2002-05-01

National Institute for Fusion Science constructed Large Helical Device (LHD) which is the largest magnetic confinement plasma experimental device using super conductive magnet coils. It took eight years to construct and the first plasma shot had been carried out on March 1998. Since then plasma confinement experiments have been improved. This is the report of administrative work at the radiation safety center considering radiation protection for workers at the LHD and related devices, and radiation monitoring in the site. Major scope is as follows. (1) Radiation measurement and dose monitoring in the radiation controlled area and in the site using particularly developed monitoring system named as Radiation Monitoring System Applicable to Fusion Experiments (RMSAFE). (2) Establishment of education and registration system for radiation workers and access control system for the LHD controlled area. I hope that as like the published report of fiscal year 1999, the present report will be helpful for management of future radiation protection in the research institute. (author)

Telework centers as local development

OpenAIRE

Lorentzen, Anne

2013-01-01

This paper discusses the establishment of distant work centers as an element in local development strategies in rural areas with a particular view on two new telework centers in Region North DenmarkDistant work is a phenomenon on the rise, due to the development of the internet on the one hand and new flexible work functions on the other hand. Not only the exchange of documents, but also meetings can be organized virtually by still better video conference equipment and programs. An implicatio...

Producing health, producing safety. Developing a collective safety culture in radiotherapy

International Nuclear Information System (INIS)

Nascimento, Adelaide

2009-01-01

This research thesis aims at a better understanding of safety management in radiotherapy and at proposing improvements for patient safety through the development of a collective safety culture. A first part presents the current context in France and abroad, addresses the transposition of other safety methods to the medical domain, and discusses the peculiarities of radiotherapy in terms of risks and the existing quality-assurance approaches. The second part presents the theoretical framework by commenting the intellectual evolution with respect to system safety and the emergence of the concept of safety culture, and by presenting the labour collective aspects and their relationship with system safety. The author then comments the variety of safety cultures among the different professions present in radiotherapy, highlights the importance of the collective dimension in correcting discrepancies at the end of the treatment process, and highlights how physicians take their colleagues work into account. Recommendations are made to improve patient safety in radiotherapy

A knowledge-centered paradigm for operations and design

International Nuclear Information System (INIS)

Perin, C.

2005-01-01

A paradigm premised on the reactor design basis and on its systems, structures, and components also governs nuclear power plant operations. This machine-centered paradigm emphasizes a functional and discipline-based division of responsibilities, which can create hierarchical 'silos' and 'stovepipes' inhibiting the development and lateral exchange of knowledge about safety-critical system interactions. A knowledge-centered paradigm instead encourages the timely development, analysis, and exchange of information about system conditions and their likely consequences. This new paradigm puts operational focus on the importance of operating experience, informative root cause analyses, effective corrective actions, and cross-discipline exchange and cooperation. Although the knowledge-centered paradigm is already central to three main strategies of risk reduction, it is less likely to be recognized as such in terms of priorities, resources, and training: configuration control, control room operations, and root cause analysis. To maintain the capacity for safe shutdown and to preserve public trust, the knowledge-centered paradigm places as high a priority on interactions of safety-critical knowledge as it does on interactions of safety-critical systems, structures, and components. (author)

Using participatory action research for injury prevention in child development centers, Suratthani province

Directory of Open Access Journals (Sweden)

Naturthai Suwantip

2018-01-01

Full Text Available This study investigated the effects of using participatory action research (PAR in the prevention of injury to children in 14 child development centers (CDCs under local administrative organizations in one district in Suratthani province, Thailand. In total, 98 stakeholder representatives participated in the study, consisting of 7 managers or representatives of the CDCs, 14 caregivers, 7 local health officials and 70 children's parents. They participated in all stages of the study—problem identification, setting the objectives and goals of the study, planning the study, development of research tools, data collection, risk analysis, risk management, monitoring, evaluation, and revision. The physical environments that were in non-compliance with safety standards were identified after a walk-through survey with the participants using an approved checklist. The number of injuries to children was collected before and after the risk management. The participants' knowledge and awareness of child injury prevention were collected using questionnaires. Optimal solutions for injury prevention were obtained through several focus group discussions between the participants within each CDC and among the CDCs. Active participation of the stakeholders resulted in significantly more knowledge and awareness relating to child injury prevention. The environments of CDCs in compliance with safety standards were significantly increased. The number of injuries to the children decreased. The participatory action model in this research was developed through collaboration between the 14 CDCs. The executives of local administrative organizations and local health officials can take the model used in this study and apply it to injury prevention in other CDCs which have a similar environment across the province. Keywords: child development center, injury prevention, participatory action research

Development of NUMO safety case for geological disposal

International Nuclear Information System (INIS)

Suzuki, Satoru; Deguchi, Akira

2016-01-01

NUMO has developed a generic safety ease based on the latest knowledge to show the feasibility and safety of geological disposal in Japan. The NUMO safety case has been developed to provide a basic structure for subsequent safety cases that would be applied to any selected site, emphasising practical approaches and methodology, which will be applicable for the conditions/constraints during an actual siting process. This paper will provide a brief overview of the NUMO safety case. (author)

National Center for Food Safety and Technology

Science.gov (United States)

2013-12-05

on the Determination of Copper, Iron, Manganese and Zinc in Beef and Goat Liver American Chemical Society (ACS) – September, 2013 22. Meng Xu...addresses key food safety issues facing the country and supports the development of safe food with health-promoting properties from farm to fork. This...Reddy, Renate Reimschuessel. 2013. Proficiency Test on the Determination of Copper, Iron, Manganese and Zinc in Beef and Goat Liver American

The development of international safety standards on geological disposal

International Nuclear Information System (INIS)

McCartin, T.

2005-01-01

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

Nuclear safety endeavour in Korea

International Nuclear Information System (INIS)

Sang-hoon lee

1987-01-01

Korea's nuclear power plant program is growing. As it grows, nuclear safety becomes an important issue. This article traces the development of Korean nuclear power program, the structure of the nuclear industries, the Nuclear Safety Center and its roles in the regulation and licensing of nuclear power plant, and also identifies some of the activities carried out to enhance the safety of nuclear power plants. (author)

Development of the Digital Reactor Safety System

International Nuclear Information System (INIS)

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

2008-04-01

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

Physical aspects of quality assurance in nuclear medicine and radiotherapy, regulatory approach of the National Nuclear Safety Center

International Nuclear Information System (INIS)

Gonzalez C, D.; Fuente P, A. de la; Quevedo G, J.R.; Lopez F, Y.; Varela C, C.

2006-01-01

The physical aspects of the quality guarantee in Nuclear Medicine and Radiotherapy its are of cardinal importance to guarantee the quality of the diagnoses and treatments that are carried out to the patients in this type of services. The OIEA, the OMS and other scientific and professional organizations have contributed significantly to the elaboration of recommendations, Protocols, etc. applicable in the quality control programs and safety of the Nuclear Medicine and Radiotherapy departments. In spite of the great effort developed in this sense the Installation of the programs of quality control and safety of the Nuclear Medicine and Radiotherapy departments can fail if the same ones are not based in three decisive elements that are: the existence of national regulations, the existence of the infrastructure required for it and the existence of enough qualified personnel to develop this programs. The present work shows the regulatory focus that on this topic, it has followed the National Center of Nuclear Safety of Cuba (CNSN). The same left of strengthen all the existent Synergies in the different organizations of the country and it went in two fundamental directions: installation of the regulatory requirements that govern this activity and the Authorization of a Cuban Entity, specialized in carrying out audits to the quality control and safety programs of the Nuclear Medicine and Radiotherapy departments. After 4 work years in this direction, the results confirm the validity of the experience developed by the CNSN, at the moment all the services of Nuclear Medicine and Radiotherapy of Cuba possess quality control and safety programs, these programs are annually Auditing by an Authorized entity by the CNSN and the Inspectors of the Regulatory Authority, control, during the inspections, the one execution of the established requirements in the national regulations. The work developed so far can serve, modestly, of reference to others countries of Latin America that

Safety case development with SBVR-based controlled language

NARCIS (Netherlands)

Luo, Y.; van den Brand, M.G.J.; Kiburse, A.; Desfray, P.; Philipe, J.; Hammoudi, S.; Pires, L.F.

2015-01-01

Safety case development is highly recommended by some safety standards to justify the safety of a system. The Goal Structuring Notation (GSN) is a popular approach to construct a safety case. However, the content of the safety case elements, such as safety claims, is in natural language. Therefore,

Foundational development of an advanced nuclear reactor integrated safety code

International Nuclear Information System (INIS)

Clarno, Kevin; Lorber, Alfred Abraham; Pryor, Richard J.; Spotz, William F.; Schmidt, Rodney Cannon; Belcourt, Kenneth; Hooper, Russell Warren; Humphries, Larry LaRon

2010-01-01

This report describes the activities and results of a Sandia LDRD project whose objective was to develop and demonstrate foundational aspects of a next-generation nuclear reactor safety code that leverages advanced computational technology. The project scope was directed towards the systems-level modeling and simulation of an advanced, sodium cooled fast reactor, but the approach developed has a more general applicability. The major accomplishments of the LDRD are centered around the following two activities. (1) The development and testing of LIME, a Lightweight Integrating Multi-physics Environment for coupling codes that is designed to enable both 'legacy' and 'new' physics codes to be combined and strongly coupled using advanced nonlinear solution methods. (2) The development and initial demonstration of BRISC, a prototype next-generation nuclear reactor integrated safety code. BRISC leverages LIME to tightly couple the physics models in several different codes (written in a variety of languages) into one integrated package for simulating accident scenarios in a liquid sodium cooled 'burner' nuclear reactor. Other activities and accomplishments of the LDRD include (a) further development, application and demonstration of the 'non-linear elimination' strategy to enable physics codes that do not provide residuals to be incorporated into LIME, (b) significant extensions of the RIO CFD code capabilities, (c) complex 3D solid modeling and meshing of major fast reactor components and regions, and (d) an approach for multi-physics coupling across non-conformal mesh interfaces.

Foundational development of an advanced nuclear reactor integrated safety code.

Energy Technology Data Exchange (ETDEWEB)

Clarno, Kevin (Oak Ridge National Laboratory, Oak Ridge, TN); Lorber, Alfred Abraham; Pryor, Richard J.; Spotz, William F.; Schmidt, Rodney Cannon; Belcourt, Kenneth (Ktech Corporation, Albuquerque, NM); Hooper, Russell Warren; Humphries, Larry LaRon

2010-02-01

This report describes the activities and results of a Sandia LDRD project whose objective was to develop and demonstrate foundational aspects of a next-generation nuclear reactor safety code that leverages advanced computational technology. The project scope was directed towards the systems-level modeling and simulation of an advanced, sodium cooled fast reactor, but the approach developed has a more general applicability. The major accomplishments of the LDRD are centered around the following two activities. (1) The development and testing of LIME, a Lightweight Integrating Multi-physics Environment for coupling codes that is designed to enable both 'legacy' and 'new' physics codes to be combined and strongly coupled using advanced nonlinear solution methods. (2) The development and initial demonstration of BRISC, a prototype next-generation nuclear reactor integrated safety code. BRISC leverages LIME to tightly couple the physics models in several different codes (written in a variety of languages) into one integrated package for simulating accident scenarios in a liquid sodium cooled 'burner' nuclear reactor. Other activities and accomplishments of the LDRD include (a) further development, application and demonstration of the 'non-linear elimination' strategy to enable physics codes that do not provide residuals to be incorporated into LIME, (b) significant extensions of the RIO CFD code capabilities, (c) complex 3D solid modeling and meshing of major fast reactor components and regions, and (d) an approach for multi-physics coupling across non-conformal mesh interfaces.

Status of nuclear safety research - 2000

International Nuclear Information System (INIS)

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

2000-11-01

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

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

Science.gov (United States)

Green, Lawrence L.

2015-01-01

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

Developing safety in the nuclear fuel cycle

International Nuclear Information System (INIS)

Brown, M.L.

1996-01-01

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

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.

Radiation Safety for Sustainable Development

International Nuclear Information System (INIS)

2015-10-01

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

Developing and maintaining national food safety control systems ...

African Journals Online (AJOL)

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

33 CFR 55.9 - Child development centers.

Science.gov (United States)

2010-07-01

.... (c) Training programs shall be conducted monthly to ensure that all child development center employees complete a minimum of 20 hours of training annually with respect to early childhood development... 33 Navigation and Navigable Waters 1 2010-07-01 2010-07-01 false Child development centers. 55.9...

Ensuring ecology safety, furthering the development of nuclear energy

International Nuclear Information System (INIS)

Shang Zhaorong; Chen Xiaoqiu; Tang Senming

2008-01-01

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

Development of digital safety system logic and control

International Nuclear Information System (INIS)

Nishikawa, H.; Sakamoto, H.

1995-01-01

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

Assessing progress in the development of safety culture

International Nuclear Information System (INIS)

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

2002-01-01

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

Central Safety Department, annual report 1987

International Nuclear Information System (INIS)

Kiefer, H.; Koenig, L.A.

1988-02-01

The Central Safety Department is responsible for handling all problems of radiation protection, safety and security of the institutes and departments of the Karlsruhe Nuclear Research Center, for waste water activity measurements and environmental monitoring of the whole area of the Center, and for research and development work mainly focusing on nuclear safety and radiation protection measures. The r+d work concentrates on the following aspects: physical and chemical behaviour of biologically particularly active radionuclides, behaviour of HT in the air/plan/soil system, biophysics of multicellular systems, improvement in radiation protection measurement and personnel dosimetry. This report gives details of the different duties, indicates the results of 1987 routine tasks and reports about results of investigations and developments of the working groups of the Department. (orig./HP) [de

Safety of infliximab in Crohn's disease: a large single-center experience.

Science.gov (United States)

Hamzaoglu, H; Cooper, J; Alsahli, M; Falchuk, K R; Peppercorn, M A; Farrell, R J

2010-12-01

The aim of this study was to evaluate the short- and long-term safety experience of infliximab treatment in patients with Crohn's disease (CD) in clinical practice. The medical records of 297 consecutive patients with CD treated with infliximab at the Beth Israel Deaconess Medical Center were reviewed for demographic features and adverse events. The 297 patients received a total of 1794 infusions. Patients received a median of four infusions and had a median follow-up of 14.3 months. Forty-four patients (15%) experienced a serious adverse event, requiring the infusion to be stopped in 33 patients (11%). Acute infusion reactions occurred in 18 patients (6%) including respiratory problems in 10 patients (3%) and an anaphylactoid reaction in 1 patient (0.3%). Serum sickness-like disease occurred in one patient (0.3%) and three patients (1%) developed drug-induced lupus. One patient developed a probable new demyelination disorder. Eight patients (2.7%), all of whom were on concurrent immunosuppressants, developed a serious infection, one resulting in fatal sepsis. Six patients (2%) developed malignancies including two lymphomas and two skin cancers. A total of four (1.3%) deaths were observed (median age 72.5 years); two due to gastrointestinal bleeding, one due to sepsis, and one due to malignancy. While short- and long-term infliximab therapy was generally well tolerated, serious adverse events occurred in 15% of patients including drug-induced lupus, fatal sepsis, and malignancy. Concomitant immunosuppressants were significantly associated with infections and deaths, particularly among elderly patients. Copyright © 2010 Crohn's & Colitis Foundation of America, Inc.

An interfaith workers' center approach to workplace rights: implications for workplace safety and health.

Science.gov (United States)

Cho, Chi C; Oliva, Jose; Sweitzer, Erica; Nevarez, Juan; Zanoni, Joseph; Sokas, Rosemary K

2007-03-01

Over the past decade, fatal occupational injury rates for immigrant workers have increased disproportionately, as have informal and precarious working arrangements. Workers' rights centers have emerged as a response. This descriptive report characterizes an innovative approach to encourage immigrant workers to access federal and state occupational safety and health programs through an interfaith workers' center. : Existing data obtained by volunteers at time of intake were redacted and imported into a SAS database for secondary analysis. Statistical methods used to evaluate associations between outcome of interest and various characteristics included the chi2 test of association, Fisher exact test of association, and multivariate logistic regression. A total of 934 individual records were reviewed, although for any given item, missing data was a limitation. Among 780 persons reporting their primary language, 75% spoke Spanish, 19% Polish, 4% English, and 1% Other. The following total numbers of formal complaints were filed with each of the following agencies: 110 referred to the state Department of Labor (DOL), 123 to the federal Equal Employment Opportunity Commission (EEOC), 65 concerning federal violations of wages and hours, and 47 complaints with the Occupational Safety and Health Administration (OSHA). Approximately 37% of the OSHA complaints resulted in a measurable outcome, exceeding the average for all complaints. Workers' most frequent concerns focus on pay and discrimination. Recasting occupational safety and health hazards as threats to income and as forms of discrimination may help identify hazards.

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

International Nuclear Information System (INIS)

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

2014-01-01

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

Safety climate and attitude as evaluation measures of organizational safety.

Science.gov (United States)

Isla Díaz, R; Díaz Cabrera, D

1997-09-01

The main aim of this research is to develop a set of evaluation measures for safety attitudes and safety climate. Specifically it is intended: (a) to test the instruments; (b) to identify the essential dimensions of the safety climate in the airport ground handling companies; (c) to assess the quality of the differences in the safety climate for each company and its relation to the accident rate; (d) to analyse the relationship between attitudes and safety climate; and (e) to evaluate the influences of situational and personal factors on both safety climate and attitude. The study sample consisted of 166 subjects from three airport companies. Specifically, this research was centered on ground handling departments. The factor analysis of the safety climate instrument resulted in six factors which explained 69.8% of the total variance. We found significant differences in safety attitudes and climate in relation to type of enterprise.

Increasing NASA SSC Range Safety by Developing the Framework to Monitor Airspace and Enforce Restrictions

Data.gov (United States)

National Aeronautics and Space Administration — The NASA John C. Stennis Space Center (SSC) Office of Safety and Mission Assurance (SMA) has a safety concern associated with unauthorized aircraft entering...

The Radiation Safety Information Computational Center (RSICC): A Resource for Nuclear Science Applications

Energy Technology Data Exchange (ETDEWEB)

Kirk, Bernadette Lugue [ORNL

2009-01-01

The Radiation Safety Information Computational Center (RSICC) has been in existence since 1963. RSICC collects, organizes, evaluates and disseminates technical information (software and nuclear data) involving the transport of neutral and charged particle radiation, and shielding and protection from the radiation associated with: nuclear weapons and materials, fission and fusion reactors, outer space, accelerators, medical facilities, and nuclear waste management. RSICC serves over 12,000 scientists and engineers from about 100 countries.

Development of Safety Culture Assessment Strategy for Korean NPP

International Nuclear Information System (INIS)

Park, Jung Hwan; Kim, Jong Hyun

2014-01-01

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

Development of Safety Culture Assessment Strategy for Korean NPP

Energy Technology Data Exchange (ETDEWEB)

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

2014-08-15

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

Central Safety Department. Annual report 1986

International Nuclear Information System (INIS)

Kiefer, H.; Koenig, L.A.

1987-03-01

The Safety Officer and the Security Officer are responsible for radiation protection and technical safety, both conventional and nuclear, for the physical protection as well as the safeguards of nuclear materials and radioactive substances within the Kernforschungszentrum Karlsruhe GmbH (KfK). To fulfill these functions they rely on the assistance of the Central Safety Department. The Central Safety Department is responsible for handling all problems of radiation protection, safety and security of the institutes and departments of the Karlsruhe Nuclear Research Center, for waste water activity measurements and environmental monitoring of the whole area of the Center, and for research and development work mainly focusing on nuclear safety and radiation protection measures. The r+d work concentrates on the following aspects: physical and chemical behavior of biologically particularly active radionuclides, behavior of HT in the air/plant/soil system, biophysics of multicellular systems, improvement in radiation protection measurement and personnel dosimetry. The report gives details of the different duties, indicates the results of 1986 routine tasks and reports about results of investigations and developments of the working groups of the Department. (orig.) [de

Collaborating with nurse leaders to develop patient safety practices.

Science.gov (United States)

Kanerva, Anne; Kivinen, Tuula; Lammintakanen, Johanna

2017-07-03

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

Development of safety analysis technology for LMR

International Nuclear Information System (INIS)

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

2000-05-01

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

Development of safety analysis technology for LMR

Energy Technology Data Exchange (ETDEWEB)

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

2000-05-01

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

Sustainable Biofuels Development Center

Energy Technology Data Exchange (ETDEWEB)

Reardon, Kenneth F. [Colorado State Univ., Fort Collins, CO (United States)

2015-03-01

The mission of the Sustainable Bioenergy Development Center (SBDC) is to enhance the capability of America’s bioenergy industry to produce transportation fuels and chemical feedstocks on a large scale, with significant energy yields, at competitive cost, through sustainable production techniques. Research within the SBDC is organized in five areas: (1) Development of Sustainable Crops and Agricultural Strategies, (2) Improvement of Biomass Processing Technologies, (3) Biofuel Characterization and Engine Adaptation, (4) Production of Byproducts for Sustainable Biorefining, and (5) Sustainability Assessment, including evaluation of the ecosystem/climate change implication of center research and evaluation of the policy implications of widespread production and utilization of bioenergy. The overall goal of this project is to develop new sustainable bioenergy-related technologies. To achieve that goal, three specific activities were supported with DOE funds: bioenergy-related research initiation projects, bioenergy research and education via support of undergraduate and graduate students, and Research Support Activities (equipment purchases, travel to attend bioenergy conferences, and seminars). Numerous research findings in diverse fields related to bioenergy were produced from these activities and are summarized in this report.

The Community Health Applied Research Network (CHARN) Data Warehouse: a Resource for Patient-Centered Outcomes Research and Quality Improvement in Underserved, Safety Net Populations.

Science.gov (United States)

Laws, Reesa; Gillespie, Suzanne; Puro, Jon; Van Rompaey, Stephan; Quach, Thu; Carroll, Joseph; Weir, Rosy Chang; Crawford, Phil; Grasso, Chris; Kaleba, Erin; McBurnie, Mary Ann

2014-01-01

The Community Health Applied Research Network, funded by the Health Resources and Services Administration, is a research network comprising 18 Community Health Centers organized into four Research Nodes (each including an academic partner) and a data coordinating center. The network represents more than 500,000 diverse safety net patients across 11 states. The primary objective of this paper is to describe the development and implementation process of the CHARN data warehouse. The methods involved regulatory and governance development and approval, development of content and structure of the warehouse and processes for extracting the data locally, performing validation, and finally submitting data to the data coordinating center. Version 1 of the warehouse has been developed. Tables have been added, the population and the years of electronic health records (EHR) have been expanded for Version 2. It is feasible to create a national, centralized data warehouse with multiple Community Health Center partners using different EHR systems. It is essential to allow sufficient time: (1) to develop collaborative, trusting relationships among new partners with varied technology, backgrounds, expertise, and interests; (2) to complete institutional, business, and regulatory review processes; (3) to identify and address technical challenges associated with diverse data environments, practices, and resources; and (4) to provide continuing data quality assessments to ensure data accuracy.

Report on administrative work at radiation safety center in fiscal year 2001

Energy Technology Data Exchange (ETDEWEB)

Uda, Tatsuhiko; Asakura, Yamato; Sakuma, Yoichi; Kawano, Takao; Yamanishi, Hirokuni; Sugiyama, Takahiko; Miyake, Hitoshi

2003-03-01

National Institute for Fusion Science constructed Large Helical Device (LHD) which is the largest magnetic confinement plasma experimental device using super conductive magnet coils. It took eight years to construct and the first plasma shot had been carried out on March 1998. In the experiments high plasma temperature and improved plasma confinement have been achieved. This is the report of administrative work at the radiation safety center considering radiation protection for workers at the LHD and related devices, and radiation monitoring in the site. Major scope is as follows. (1) Radiation measurement and dose monitoring in the radiation controlled area and in the site using particularly developed monitoring system named as Radiation Monitoring System Applicable to Fusion Experiments (RMSAFE). (2) Establishment of education and registration system for radiation workers and access control system for the LHD controlled area. I hope that as like the published reports of fiscal year 1999 and 2000, the present report will be helpful for management of future radiation protection in the research institute. (author)

Development of web-based safety review advisory system

International Nuclear Information System (INIS)

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

2002-01-01

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

Assessing progress in the development of safety culture

International Nuclear Information System (INIS)

Rotaru, Ioan; Ghita, Sorin

1999-01-01

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

Safety Case Development as an Information Modelling Problem

Science.gov (United States)

Lewis, Robert

This paper considers the benefits from applying information modelling as the basis for creating an electronically-based safety case. It highlights the current difficulties of developing and managing large document-based safety cases for complex systems such as those found in Air Traffic Control systems. After a review of current tools and related literature on this subject, the paper proceeds to examine the many relationships between entities that can exist within a large safety case. The paper considers the benefits to both safety case writers and readers from the future development of an ideal safety case tool that is able to exploit these information models. The paper also introduces the idea that the safety case has formal relationships between entities that directly support the safety case argument using a methodology such as GSN, and informal relationships that provide links to direct and backing evidence and to supporting information.

Annual report 1991 of the Central Safety Department

International Nuclear Information System (INIS)

Koelzer, W.

1992-04-01

The Central Safety Department is responsible for handling all problems of radiation protection, safety and security of the institutes and departments of the Karlsruhe Nuclear Research Center, for waste water activity measurements and environmental monitoring of the whole area of the Center, and for research and development work mainly focusing on nuclear safety and radiation protection measures. The research and development work concentrates on the following aspects: Physical and chemical behavior of trace elements in the environment, behavior of tritium in the air/plant/soil system, biophysics of multicellular systems, improvement in radiation protection measurement and personnel dosimetry. This report gives details of the different duties, indicates the results of 1989 routine tasks and reports about results of investigations and developments of the working groups of the Department. The reader is referred to the English translation of the Table of Contents and of Chapter 1 describing the duties and organization of the Central Safety Department. (orig.) [de

Annual report 1990 of the Central Safety Department

International Nuclear Information System (INIS)

Koelzer, W.; Urban, M.

1991-04-01

The Central Safety Department is responsible for handling all problems of radiation protection, safety and security of the institutes and departments of the Karlsruhe Nuclear Research Center, for waste water activity measurements and environmental monitoring of the whole area of the Center, and for research and development work mainly focusing on nuclear safety and radiation protection measures. The research and development work concentrates on the following aspects: Physical and chemical behavior of trace elements in the environment, behavior of tritium in the air/plant/soil system, biophysics of multicellular systems, improvement in radiation protection measurement and personnel dosimetry. This report gives details of the different duties, indicates the results of 1989 routine tasks and reports about results of investigations and developments of the working groups of the Department. The reader is referred to the English translation of the Table of Contents and of Chapter 1 describing the duties and organization of the Central Safety Department. (orig.) [de

Food Safety: At the Center of a One Health Approach for Combating Zoonoses

DEFF Research Database (Denmark)

Wielinga, Pieter; Schlundt, Jørgen

2013-01-01

in three major classes: parasites, bacteria, and viruses. While parasites often relate to very specific animal hosts and contribute significantly to the human disease burden, virus have often been related to major, well-published global outbreaks, e.g. SARS and avian- and swine-influenza. The bacterial...... international organizations and national agricultural-and health authorities in most countries, for instance as was the case with avian influenza. Other diseases relate to the industrialized food production chain and have been-in some settings-dealt with efficiently through farm-to-fork preventive action......Food Safety is at the center of One Health. Many, if not most, of all important zoonoses relate in some way to animals in the food production chain. Therefore, the food becomes an important vehicle for many, but not all, of these zoonotic pathogens. One of the major issues in food safety over...

[Clinical safety audits for primary care centers. A pilot study].

Science.gov (United States)

Ruiz Sánchez, Míriam; Borrell-Carrió, Francisco; Ortodó Parra, Cristina; Fernàndez I Danés, Neus; Fité Gallego, Anna

2013-01-01

To identify organizational processes, violations of rules, or professional performances that pose clinical levels of insecurity. Descriptive cross-sectional survey with customized externally-behavioral verification and comparison of sources, conducted from June 2008 to February 2010. Thirteen of the 53 primary care teams (PCT) of the Catalonian Health Institute (ICS Costa de Ponent, Barcelona). Employees of 13 PCT classified into: director, nurse director, customer care administrators, and general practitioners. Non-random selection, teaching (TC)/non-teaching, urban (UC)/rural and small/large (LC) health care centers (HCC). A total of 33 indicators were evaluated; 15 of procedures, 9 of attitude, 3 of training, and 6 of communication. Level of uncertainty: <50% positive answers for each indicator. no collaboration. A total of 55 professionals participated (84.6% UC, 46.2% LC and 76.9% TC). Rank distribution: 13 customer care administrators, 13 nurse directors, 13 HCC directors, and 16 general practitioners. Levels of insecurity emerged from the following areas: reception of new medical professionals, injections administration, nursing weekend home calls, urgent consultations to specialists, aggressive patients, critical incidents over the agenda of the doctors, communication barriers with patients about treatment plans, and with immigrants. Clinical safety is on the agenda of the health centers. Identified areas of uncertainty are easily approachable, and are considered in the future system of accreditation of the Catalonian Government. General practitioners are more critical than directors, and teaching health care centers, rural and small HCC had a better sense of security. Copyright © 2012 Elsevier España, S.L. All rights reserved.

Safety climate and workplace violence prevention in state-run residential addiction treatment centers.

Science.gov (United States)

Lipscomb, Jane A; London, M; Chen, Y M; Flannery, K; Watt, M; Geiger-Brown, J; Johnson, J V; McPhaul, K

2012-01-01

To examine the association between violence prevention safety climate measures and self reported violence toward staff in state-run residential addiction treatment centers. In mid-2006, 409 staff from an Eastern United States state agency that oversees a system of thirteen residential addiction treatment centers (ATCs) completed a self-administered survey as part of a comprehensive risk assessment. The survey was undertaken to identify and measure facility-level risk factors for violence, including staff perceptions of the quality of existing US Occupational Safety and Health Administration (OSHA) program elements, and ultimately to guide violence prevention programming. Key informant interviews and staff focus groups provided researchers with qualitative data with which to understand safety climate and violence prevention efforts within these work settings. The frequency with which staff reported experiencing violent behavior ranged from 37% for "clients raised their voices in a threatening way to you" to 1% for "clients pushed, hit, kicked, or struck you". Findings from the staff survey included the following significant predictors of violence: "client actively resisting program" (OR=2.34, 95% CI=1.35, 4.05), "working with clients for whom the history of violence is unknown" (OR=1.91, 95% CI=1.18, 3.09) and "management commitment to violence prevention" reported as "never/hardly ever" and "seldom or sometimes" (OR=4.30 and OR=2.31 respectively), while controlling for other covariates. We utilized a combination of qualitative and quantitative research methods to begin to describe the risk and potential for violence prevention in this setting. The prevalence of staff physical violence within the agency's treatment facilities was lower than would be predicted. Possible explanations include the voluntary nature of treatment programs; strong policies and consequences for resident behavior and ongoing quality improvement efforts. Quantitative data identified low

Sometimes Overlooked: Women's Small Business Development Center.

Science.gov (United States)

Lariviere, Elizabeth A.

2001-01-01

Describes the development and growth of the Western Reserve Small Business Development Center for Women (Ohio), which promotes the advancement of women-owned businesses in the Northeastern Ohio region by assisting women in starting and maintaining their own businesses. States that the center offers low-cost training programs and counseling by a…

Progress of nuclear safety research. 2001

Energy Technology Data Exchange (ETDEWEB)

Anoda, Yoshinari; Sasajima, Hideo; Nishiyama, Yutaka (eds.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment] [and others

2001-10-01

JAERI is conducting nuclear safety research primarily at the Nuclear Safety Research Center in close cooperation with the related departments in accordance with the Long Term Plan for Development and Utilization of Nuclear Energy or the Safety Research Annual Plan issued by the Japanese government. The safety research at JAERI concerns the engineering safety of nuclear power plants and nuclear fuel cycle facilities, and radioactive waste management as well as advanced technology for safety improvement or assessment. Also, JAERI has conducted international collaboration to share the information on common global issues of nuclear safety. This report summarizes the nuclear safety research activities of JAERI from April 1999 through March 2001. (author)

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.

Development of web-based safety review advisory system

International Nuclear Information System (INIS)

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

2002-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2002-03-01

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

Implementation of the INEEL safety analyst training standard

International Nuclear Information System (INIS)

Hochhalter, E. E.

2000-01-01

The Idaho Nuclear Technology and Engineering Center (INTEC) safety analysis units at the Idaho National Engineering and Environmental Laboratory (INEEL) are in the process of implementing the recently issued INEEL Safety Analyst Training Standard (STD-1107). Safety analyst training and qualifications are integral to the development and maintenance of core safety analysis capabilities. The INEEL Safety Analyst Training Standard (STD-1107) was developed directly from EFCOG Training Subgroup draft safety analyst training plan template, but has been adapted to the needs and requirements of the INEEL safety analysis community. The implementation of this Safety Analyst Training Standard is part of the Integrated Safety Management System (ISMS) Phase II Implementation currently underway at the INEEL. The objective of this paper is to discuss (1) the INEEL Safety Analyst Training Standard, (2) the development of the safety analyst individual training plans, (3) the implementation issues encountered during this initial phase of implementation, (4) the solutions developed, and (5) the implementation activities remaining to be completed

Development and Demise of a Women's Center.

Science.gov (United States)

Liss, Lora

The formation, development, and demise of a women's center in suburban New York are described. The women's center resulted from a conference designed to assess problems confronting women and to mobilize resources to meet those problems. However, after the formation of the center, a struggle for leadership and conflicts over the values and beliefs…

Burnout, Perceived Stress, and Job Satisfaction Among Trauma Nurses at a Level I Safety-Net Trauma Center.

Science.gov (United States)

Munnangi, Swapna; Dupiton, Lynore; Boutin, Anthony; Angus, L D George

Nurses are at the forefront of our health care delivery system and have been reported to exhibit a high level of burnout. Burnout and stress in trauma nurses at a safety-net hospital can negatively impact patient care. Safety-net hospitals are confronted with unique social, financial, as well as resource problems that can potentially make the work environment frustrating. The purpose of this study was to explore the levels of burnout, stress, and job satisfaction in nurses providing care to trauma patients at a Level I safety-net trauma center. A cross-sectional survey design was used to investigate principal factors including personal and professional demographics, burnout, perceived stress, and job satisfaction. Trauma nurses working at a Level I safety-net trauma center are stressed and exhibited moderate degree of burnout. The extent of emotional exhaustion experienced by the nurses varied with work location and was highest in surgical intensive care unit nurses. The level of job satisfaction in terms of opportunities for promotion differed significantly by race and the health status of the nurses. Satisfaction with coworkers was lowest in those nurses between the ages of 60-69 years. Female nurses were more satisfied with their coworkers than male nurses. In addition, the study revealed that significant relationships exist among perceived stress, burnout, and job satisfaction. Work environment significantly impacts burnout, job satisfaction, and perceived stress experienced by trauma nurses in a safety-net hospital. Nursing administration can make an effort to understand the levels of burnout and strategically improve work environment for trauma nurses in order to minimize stressors leading to attrition and enhance job satisfaction.

Development of Management, Child Development Centers Organization rule Local Government in Udon thani

OpenAIRE

Suriya Sukram; Chaiyot Ruangsuwan

2017-01-01

This research aims to study the composition and indications 1. The Child Development Centre under the local governments in UdonThani province 2. Study the current state and the desired operating child care centers under the jurisdiction of local governments in UdonThani province. 3. Develop the child development centers under the local governments in UdonThani province. The operation is divided. Phase one of the elements and indicators, the Child Development Center. By synthesi...

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

International Nuclear Information System (INIS)

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

2004-01-01

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

Program integration of predictive maintenance with reliability centered maintenance

International Nuclear Information System (INIS)

Strong, D.K. Jr; Wray, D.M.

1990-01-01

This paper addresses improving the safety and reliability of power plants in a cost-effective manner by integrating the recently developed reliability centered maintenance techniques with the traditional predictive maintenance techniques of nuclear power plants. The topics of the paper include a description of reliability centered maintenance (RCM), enhancing RCM with predictive maintenance, predictive maintenance programs, condition monitoring techniques, performance test techniques, the mid-Atlantic Reliability Centered Maintenance Users Group, test guides and the benefits of shared guide development

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

International Nuclear Information System (INIS)

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

2013-01-01

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

Shields calculations for teletherapy equipment. Regulatory approach of the National Center of Nuclear Safety

International Nuclear Information System (INIS)

Fuente P, A. de la; Dumenigo G, C.; Quevedo G, J.R.; Lopez F, Y.

2006-01-01

The evaluation of applications of construction licenses for the new services of radiotherapy has occupied a significant space in the activity developed by the National Center of Nuclear Safety (CNSN) in the last 2 years. Presently work the experiences of the authors in the evaluation of the required shield for the local where cobalt therapy equipment and lineal accelerators of medical use are used its are exposed, the practical problems detected are approached during the application of the methodologies recommended in both cases and its are discussed which have been the suppositions of items accepted by the Regulatory Authority for the realization of these shield calculations. The accumulated experience allows to assure that the realistic application of the item data and the rational use of the engineering logic makes possible to design local for radiotherapy equipment that fulfill the established dose restrictions in the in use legislation in Cuba, without it implies an excessive expense of construction materials. (Author)

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

Science.gov (United States)

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

2015-04-22

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

Status of SPACE Safety Analysis Code Development

International Nuclear Information System (INIS)

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

2009-01-01

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

Developing safety culture-rocket science or common sense?

International Nuclear Information System (INIS)

Mahn, J.A.

1998-01-01

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

Developing safety culture-rocket science or common sense?

Energy Technology Data Exchange (ETDEWEB)

Mahn, J.A.

1998-08-01

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

Development of Comprehensive Nuclear Safety Regulation Plan for 2007-2011

International Nuclear Information System (INIS)

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

2006-01-01

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

Proceeding of the Fifth Scientific Presentation on Nuclear Safety Technology

International Nuclear Information System (INIS)

Suhaemi, Tj.; Sudarno; Sunaryo, G. R.; Supriatna, P.; Antariksawan, A. R.; Sumijanto; Febrianto; Histori; Aliq

2000-01-01

The proceedings includes the result of research and development activities on nuclear safety technology that have been done by research Center for Nuclear Safety Technology in 2000 and was presented on June 28, 2000. The proceedings is expected to give illustration of the research result on Nuclear Safety Technology

Developing IAM for Life Cycle Safety Assessment

NARCIS (Netherlands)

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

2013-01-01

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

Development of the structural materials information center

International Nuclear Information System (INIS)

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

1990-01-01

The U.S. Nuclear Regulatory Commission has initiated a Structural Aging Program at the Oak Ridge National Laboratory to identify potential structural safety issues related to continued service of nuclear power plants and to establish criteria for evaluating and resolving these issues. One of the tasks in this program focuses on the establishment of a Structural Materials Information Center where data and information on the time variation of concrete and other structural material properties under the influence of pertinent environmental stressors and aging factors are being collected and assembled into a database. This database will be used to assist in the prediction of potential long-term deterioration of critical structural components in nuclear power plants and to establish limits on hostile environmental exposure for these structures and materials. Two complementary database formats have been developed. The Structural Materials Handbook is an expandable, hard copy handbook that contains complete sets of data and information for selected portland cement concrete, metallic reinforcement, prestressing tendon, and structural steel materials. The Structural Materials Electronic Database is accessible by an IBM-compatible personal computer and provides an efficient means for searching the various database files to locate materials with similar properties. The database formats have been developed to accommodate data and information on the time-variation of concrete and other structural material properties. To date, the database includes information on concrete, reinforcement, prestressing, and structural steel materials

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

Science.gov (United States)

Mitchell, Rebecca; Friswell, Rena; Mooren, Lori

2012-07-01

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

Annual report 1988 of the Central Safety Department

International Nuclear Information System (INIS)

Koelzer, W.; Urban, M.

1989-04-01

The Central Safety Department is responsible for handling all problems of radiation protection, safety and security of the institutes and departments of the Karlsruhe Nuclear Research Center, for waste water activity measurements and environmental monitoring of the whole area of the Center, and for research and development work mainly focusing on nuclear safety and radiation protection measures. The r+d work concentrates on the following aspects: physical and chemical behavior of biologically particularly active radionuclides, behavior of tritium in the air/plant/soil system, biophysics of multicellular systems, improvement in radiation protection measurement and personnel dosimetry. This report gives details of the different duties, indicates the results of 1988 routine tasks and reports about results of investigations and developments of the working groups of the Department. The reader is referred to the English translation of the Table of Contents and of Chapter 1 describing the duties and organization of the Central Safety Department. (orig./HP) [de

Sandia National Laboratories: Microsystems Science & Technology Center

Science.gov (United States)

Environmental Management System Pollution Prevention History 60 impacts Diversity Locations Facts & Figures Programs Nuclear Weapons About Nuclear Weapons Safety & Security Weapons Science & Technology Robotics R&D 100 Awards Laboratory Directed Research & Development Technology Deployment Centers

The 10th Anniversary Of Daejeon Environmental Technology Development Center

International Nuclear Information System (INIS)

2010-12-01

This book describes the Daejeon Environment Technology Development Center with pictures for ten years. It also introduces the purpose of the foundation and background of center, structure of the center, main project and role of the center, center logo, current situation of cost of project, research business for 10 years, business supporting the environmental corporate, environment education, public relations activity and vision and prospect of the Daejeon Environmental Technology Development Center.

Global road safety online course development.

Science.gov (United States)

2017-06-01

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

Proceedings of the Fourth Scientific Presentation on Reactor Safety Technology

International Nuclear Information System (INIS)

1999-01-01

The proceedings includes the result of research and development activities on nuclear safety technology that have been done by research Center for Nuclear Safety Technology in 1998/1999 and was presented on May 5, 1999. The proceedings is expected to give illustration of the research result on Nuclear Safety Technology

Development of fusion safety standards

International Nuclear Information System (INIS)

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

1996-01-01

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

Center Planning and Development Student Engineer

Science.gov (United States)

Jenkins, Kenneth T.

2013-01-01

This fall I was the Student Trainee (Engineering) Pathways Intern (co-op) at the Kennedy Space Center (KSC) in the Center Planning Development (CPD) Directorate. CPD works with commercial companies who are interested using KSCs unique capabilities in spaceflight, spacecraft processing, ground systems and Research Development (RD) projects that fall in line with NASAs mission and goals. CPD is divided into four (4) groups: (1) AD-A, which works on the Master Planning for center, (2) AD-B (where I am), which works on project management and integration, (3) AD-C, which works on partnership development, and (4) AD-T, which works on the RD aspects of partnerships. CPDs main goal is to one day make KSC the worlds largest spaceport and maintain the center as a leader in space exploration. CPD is a very diverse group with employees having a wide knowledge of not only the Space Shuttle, but also that of the Apollo era. Our director of CPD, Scott Colloredo, is on the advisory board for Commercial Space Operations (CSO) and has a degree at ERAU. I worked on a number of different tasks for AD-B, as well as CPD, that includes, but not limited to: reviewing and reissuing engineering drawings from the Apollo and Shuttle eras, to supporting NASA rocket launches (MAVEN), and working on actual agreementsproposals that will be used in the partnership process with multiple partners. Most of the work I have done is sensitive information and cannot be disclosed.

Safety Evaluation Report for the Claiborne Enrichment Center, Homer, Louisiana (Docket No. 70-3070)

Energy Technology Data Exchange (ETDEWEB)

1994-01-01

This report documents the US Nuclear Regulatory Commission (NRC) staff review and safety evaluation of the Louisiana Energy Services, L.P. (LES, the applicant) application for a license to possess and use byproduct, source, and special nuclear material and to enrich natural uranium to a maximum of 5 percent U-235 by the gas centrifuge process. The plant, to be known as the Claiborne Enrichment Center (CEC), would be constructed near the town of Homer in Claiborne Parish, Louisiana. At full production in a given year, the plant will receive approximately 4,700 tonnes of feed UF{sub 6} and produce 870 tonnes of low-enriched UF{sub 6}, and 3,830 tonnes of depleted UF{sub 6} tails. Facility construction, operation, and decommissioning are expected to last 5, 30, and 7 years, respectively. The objective of the review is to evaluate the potential adverse impacts of operation of the facility on worker and public health and safety under both normal operating and accident conditions. The review also considers the management organization, administrative programs, and financial qualifications provided to assure safe design and operation of the facility. The NRC staff concludes that the applicant`s descriptions, specifications, and analyses provide an adequate basis for safety review of facility operations and that construction and operation of the facility does not pose an undue risk to public health and safety.

Safety Evaluation Report for the Claiborne Enrichment Center, Homer, Louisiana (Docket No. 70-3070)

International Nuclear Information System (INIS)

1994-01-01

This report documents the US Nuclear Regulatory Commission (NRC) staff review and safety evaluation of the Louisiana Energy Services, L.P. (LES, the applicant) application for a license to possess and use byproduct, source, and special nuclear material and to enrich natural uranium to a maximum of 5 percent U-235 by the gas centrifuge process. The plant, to be known as the Claiborne Enrichment Center (CEC), would be constructed near the town of Homer in Claiborne Parish, Louisiana. At full production in a given year, the plant will receive approximately 4,700 tonnes of feed UF 6 and produce 870 tonnes of low-enriched UF 6 , and 3,830 tonnes of depleted UF 6 tails. Facility construction, operation, and decommissioning are expected to last 5, 30, and 7 years, respectively. The objective of the review is to evaluate the potential adverse impacts of operation of the facility on worker and public health and safety under both normal operating and accident conditions. The review also considers the management organization, administrative programs, and financial qualifications provided to assure safe design and operation of the facility. The NRC staff concludes that the applicant's descriptions, specifications, and analyses provide an adequate basis for safety review of facility operations and that construction and operation of the facility does not pose an undue risk to public health and safety

A phenomenological investigation of science center exhibition developers' expertise development

Science.gov (United States)

Young, Denise L.

The purpose of this study was to examine the exhibition developer role in the context of United States (U.S.) science centers, and more specifically, to investigate the way science center exhibition developers build their professional expertise. This research investigated how successfully practicing exhibition developers described their current practices, how they learned to be exhibition developers, and what factors were the most important to the developers in building their professional expertise. Qualitative data was gathered from 10 currently practicing exhibition developers from three science centers: the Exploratorium, San Francisco, California; the Field Museum, Chicago, Illinois; and the Science Museum of Minnesota, St. Paul, Minnesota. In-depth, semistructured interviews were used to collect the data. The study embraced aspects of the phenomenological tradition and sought to derive a holistic understanding of the position and how expertise was built for it. The data were methodically coded and organized into themes prior to analysis. The data analysis found that the position consisted of numerous and varied activities, but the developers' primary roles were advocating for the visitor, storytelling, and mediating information and ideas. They conducted these activities in the context of a team and relied on an established exhibition planning process to guide their work. Developers described a process of learning exhibition development that was experiential in nature. Learning through daily practice was key, though they also consulted with mentors and relied on visitor studies to gauge the effectiveness of their work. They were adept at integrating prior knowledge gained from many aspects of their lives into their practice. The developers described several internal factors that contributed to their expertise development including the desire to help others, a natural curiosity about the world, a commitment to learning, and the ability to accept critique. They

Workshop on development and view on digital safety system of KNICS

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-05-15

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

Workshop on development and view on digital safety system of KNICS

International Nuclear Information System (INIS)

2006-05-01

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

Development of an FPGA-based controller for safety critical application

International Nuclear Information System (INIS)

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

2011-01-01

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

SCALE Graphical Developments for Improved Criticality Safety Analyses

International Nuclear Information System (INIS)

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

1999-01-01

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

The Austrian Research Centers activities in energy risks

International Nuclear Information System (INIS)

Sdouz, Gert

1998-01-01

Among the institutions involved in energy analyses in Austria the risk context is being treated by three different entities: the Energy Consumption Agency, internationally known as EVA, the Federal Environmental Protection Agency, or Urnweltbundesarnt assessing mainly the environmental risks involved and the Austrian Research Centers, working on safety and risk evaluation. The Austrian Research Center Seibersdorf draws form its proficiency in Reactor Safety and Fusion Research, two fields of experience it has been involved in since its foundation, for some 40 years now. Nuclear energy is not well accepted by the Austrian population. Therefore in our country only energy systems with advanced safety level might be accepted in the far future. This means that the development of methods to compare risks is an important task. The characteristics of energy systems featuring advanced safety levels are: A very low hazard potential and a focus on deterministic safety instead of probabilistic safety, meaning to rely on inherently safe physics concepts, confirmed by probabilistic safety evaluation results. This can be achieved by adequate design of fusion reactors, advanced fission reactors and all different renewable sources of energy

Safety management in research and development organisation

International Nuclear Information System (INIS)

Nivedha, T.

2016-01-01

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

Carbon Monoxide Information Center

Medline Plus

Full Text Available ... Education Safety Education Centers Carbon Monoxide Information Center Carbon Monoxide Information Center En Español The Invisible Killer Carbon monoxide, also known as CO, is called the " ...

History of aviation safety; the satisfying sighs of relief due to developments in Aviation safety

NARCIS (Netherlands)

Stoop, J.A.A.M.

2014-01-01

”Aviation safety is an Integral part of my career. Being part of TU Delft’s impressive record of research on Aviation safety, my career has been with a sense of purpose and a responsibility to equip students to deal with the status quo challenges on Aviation safety, developments, Investigations and

Development of Safety Review Guidance for Research and Training Reactors

International Nuclear Information System (INIS)

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

2007-01-01

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

Center for Leadership Development (CLD) Repository

Data.gov (United States)

Office of Personnel Management — The Center for Leadership Development Repository stores various data including policies, procedures, governance, guidance, security, and financial documents of the...

Development of safety analysis technology for integral reactor

International Nuclear Information System (INIS)

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

2002-04-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2015-05-15

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

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

International Nuclear Information System (INIS)

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

2015-01-01

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

Carbon Monoxide Information Center

Medline Plus

Full Text Available ... CONSUMER PRODUCT SAFETY COMMISSION Search CPSC Search Menu Home Recalls Recall List CPSC Recall API Recall Lawsuits ... and Bans Report an Unsafe Product Consumers Businesses Home Safety Education Safety Education Centers Carbon Monoxide Information ...

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

ENTREPRENEURSHIP ECONOMIC SAFETY AND DEVELOPMENT OF SECURITY SERVICES

Directory of Open Access Journals (Sweden)

G. V. Goudkov

2011-01-01

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

Compliance of child care centers in Pennsylvania with national health and safety performance standards for emergency and disaster preparedness.

Science.gov (United States)

Olympia, Robert P; Brady, Jodi; Kapoor, Shawn; Mahmood, Qasim; Way, Emily; Avner, Jeffrey R

2010-04-01

To determine the preparedness of child care centers in Pennsylvania to respond to emergencies and disasters based on compliance with National Health and Safety Performance Standards for Out-of-Home Child Care Programs. A questionnaire focusing on the presence of a written evacuation plan, the presence of a written plan for urgent medical care, the immediate availability of equipment and supplies, and the training of staff in first aid/cardiopulmonary resuscitation (CPR) as delineated in Caring for Our Children: National Health and Safety Performance Standards for Out-of-Home Child Care Programs, 2nd Edition, was mailed to 1000 randomly selected child care center administrators located in Pennsylvania. Of the 1000 questionnaires sent, 496 questionnaires were available for analysis (54% usable response rate). Approximately 99% (95% confidence interval [CI], 99%-100%) of child care centers surveyed were compliant with recommendations to have a comprehensive written emergency plan (WEP) for urgent medical care and evacuation, and 85% (95% CI, 82%-88%) practice their WEP periodically throughout the year. More than 20% of centers did not have specific written procedures for floods, earthquakes, hurricanes, blizzards, or bomb threats, and approximately half of the centers did not have specific written procedures for urgent medical emergencies such as severe bleeding, unresponsiveness, poisoning, shock/heart or circulation failure, seizures, head injuries, anaphylaxis or allergic reactions, or severe dehydration. A minority of centers reported having medications available to treat an acute asthma attack or anaphylaxis. Also, 77% (95% CI, 73%-80%) of child care centers require first aid training for each one of its staff members, and 33% (95% CI, 29%-37%) require CPR training. Although many of the child care centers we surveyed are in compliance with the recommendations for emergency and disaster preparedness, specific areas for improvement include increasing the frequency

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

OpenAIRE

Vilkonis, Rytis

2005-01-01

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

Formal model-based development for safety-critical embedded software

International Nuclear Information System (INIS)

Kim, Jin Hyun; Choi, Jin Young

2005-01-01

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

Formal model-based development for safety-critical embedded software

Energy Technology Data Exchange (ETDEWEB)

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

2005-11-15

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

Development of Network Protocol for the Integrated Safety System

Energy Technology Data Exchange (ETDEWEB)

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

2007-06-15

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

Development of Network Protocol for the Integrated Safety System

International Nuclear Information System (INIS)

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

2007-06-01

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

1978 annual report of the safety department

International Nuclear Information System (INIS)

Kiefer, H.; Koelzer, W.

1979-04-01

The Safety Officer and the Security Officer, respectively, are responsible for radiation protection and technical safety, both conventional and nuclear, for the physical protection as well as the security of nuclear materials and radioactive substances within the Kernforschungszentrum Karlsruhe GmbH. (KfK). To fulfill these functions they rely on the assitance of the Safety Department. The duties of this Department cover tasks relative to radiation protection, safety and security on behalf of the institutes and departments of KfK and environmental monitoring for the whole Karlsruhe Nuclear Research Center as well as research and development work, mainly performed under the Nuclear Safety Project and the Nuclear Safeguards Project. The centers of interest of r and d activities are: investigation of the atmospheric diffusion of nuclear pollutants on the micro- and meso-scales, evaluation of the radiological consequences of accidents in reactors under probabilistic aspects, studies of the physical and chemical behavior of radionuclides with particularly high biological effectiveness in the environment, implementation of nuclear fuel safequarding systems, improvements in radiation protection measurement technology. This report gives details of the different duties, indicates the results of 1978 routine tasks, and reports about new results of investigations and developments of the working groups of the Department. (orig.) [de

Annual Report 1979 of the Safety Department

International Nuclear Information System (INIS)

Kiefer, H.; Koelzer, W.; Koenig, L.A.

1980-04-01

The Safety Officer and the Security Officer, respectively, are responsible for radiation protection and technical safety, both conventional and nuclear, for the physical protection as well as the security of nuclear materials and radioactive substances within the Kernforschungszentrum Karlsruhe GmbH. (KfK). To fulfill these functions they rely on the assistance of the Safety Department. The duties of this Department cover tasks relative to radiation protection, safety and security on behalf of the institutes and departments of KfK and environmental monitoring for the whole Karlsruhe Nuclear Research Center as well as research and development work, mainly performed under the Nuclear Safety Project and the Nuclear Safeguards Project. The centers of interest of r and d activities are: investigation of the atmospheric diffusion of nuclear pollutants on the micro- and meso-scales, evaluation of the radiological consequences of accidents in reactors under probabilistic aspects, studies of the physical and chemical behavior of radionuclides with particularly high biological effectiveness in the environment, implemantation of nuclear fuel safeguarding systems, improvements in radiation protection measurement technology. This report gives details of the different duties, indicates the results of 1979 routine tasks, and reports about results of investigations and developments of the working groups of the Department. (orig.) [de

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

Science.gov (United States)

Ejilemele, A A; Ojule, A C

2004-01-01

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

Development of IFC based fire safety assesment tools

DEFF Research Database (Denmark)

Taciuc, Anca; Karlshøj, Jan; Dederichs, Anne

2016-01-01

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

Development and application of digital safety system in NPPs

International Nuclear Information System (INIS)

Kwon, Keechoon; Kim, Changhwoi; Lee, Dongyoung

2012-01-01

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

Development and application of digital safety system in NPPs

Energy Technology Data Exchange (ETDEWEB)

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

2012-03-15

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

Challenges on innovations of newly-developed safety analysis codes

International Nuclear Information System (INIS)

Yang, Yanhua; Zhang, Hao

2016-01-01

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

Challenges on innovations of newly-developed safety analysis codes

Energy Technology Data Exchange (ETDEWEB)

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

2016-05-15

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

RSAS: a Reactor Safety Assessment System

International Nuclear Information System (INIS)

Sebo, D.E.; Dixon, B.W.; Bray, M.A.

1985-01-01

The Reactor Safety Assessment System (RSAS) is an expert system under development for the United States Nuclear Regulatory Commission (NRC). RSAS is being developed for use at the NRC's Operations Center in the event of a serious incident at a licensed nuclear power plant. The system generates situation assessments for the NRC Reactor Safety Team based on a limited number of plant parameters, known operator actions, and plant status data. The RSAS rule base currently covers one reactor type. The extension of the rule base to other reactor types is also discussed

Development of photovoltaic array and module safety requirements

Science.gov (United States)

1982-01-01

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

Development of the safety PLC for plant protection system

Energy Technology Data Exchange (ETDEWEB)

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

2005-11-15

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

Development of an environmental safety case guidance manual

International Nuclear Information System (INIS)

Wellstead, Matthew John

2014-01-01

NDA RWMD is currently considering the scope, purpose and structure of a safety case manual that covers the development of nuclear operational, transport and environmental safety cases for a geological disposal facility in the United Kingdom. This paper considers the Environmental Safety Case (ESC) input into such a manual (herein referred to as the 'ESC Manual'), looking at the drivers and benefits that a guidance manual in this area may provide. (authors)

Development of safety review advisory system for nuclear power plants

International Nuclear Information System (INIS)

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

2001-01-01

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

Architectural Design of a Nuclear Research Center with Radiation Safety Considerations, in North Western Coast of Egypt (Using Auto CAD and 3ds Max Programs)

International Nuclear Information System (INIS)

Farahat, M.A.Z.

2016-01-01

This research discusses the design of nuclear research centers to help architects and engineers who will design these centers. Also, the research covers the site characteristics which are used in site selection of nuclear research centers. It covers the principles and standards used in design and planning of nuclear research centers. The master plan of a nuclear research center should be designed based on the system of segregation according to the level of radioactivity. Radiation safety is an important aspect in the design of nuclear research centers. The Egyptian Atomic Energy Authority consists of three nuclear research centers, namely, the Nuclear Research Center in Inshas (Grid Planning Concept), the Hot Laboratories and Waste Management Center in Inshas (Grid Planning Concept) and The National Center for Radiation Research and Technology in Nasr City (Linear Planning Concept). The Radial Planning Concept is the best among all the Planning Concepts as regard radiation safety considerations. Therefore, an architectural design of a new nuclear research center was proposed in a suitable site in North Western Coast of Egypt (Radial Planning Concept) using Auto CAD and 3ds Max programs. This site is suitable and satisfies many of the site requirements. It is recommended that the architectural design of nuclear research centers should be supervised by an architectural engineer experienced in architectural design of nuclear facilities

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

Science.gov (United States)

Chuang-Stein, Christy; Xia, H Amy

2013-01-01

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

33 CFR 55.11 - How are child development center fees established?

Science.gov (United States)

2010-07-01

... 33 Navigation and Navigable Waters 1 2010-07-01 2010-07-01 false How are child development center... HOMELAND SECURITY PERSONNEL CHILD DEVELOPMENT SERVICES General § 55.11 How are child development center fees established? (a) Fees for the provision of services at child development centers shall be set by...

Carbon Monoxide Information Center

Medline Plus

Full Text Available ... Education Centers Carbon Monoxide Information Center Carbon Monoxide Information Center En Español The Invisible Killer Carbon monoxide, ... Install one and check its batteries regularly. View Information About CO Alarms Other CO Topics Safety Tips ...

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)

Development of Safety Assessment Information System (SAIS)

International Nuclear Information System (INIS)

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

2007-01-01

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

Development of Safety Assessment Information System (SAIS)

Energy Technology Data Exchange (ETDEWEB)

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

2007-10-15

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

Development of a new methodology for quantifying nuclear safety culture

International Nuclear Information System (INIS)

Han, Kiyoon; Jae, Moosung

2017-01-01

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

Development of a new methodology for quantifying nuclear safety culture

Energy Technology Data Exchange (ETDEWEB)

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

2017-01-15

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

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

International Nuclear Information System (INIS)

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

1982-01-01

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

Development of Safety Analysis Technology for Integral Reactor

Energy Technology Data Exchange (ETDEWEB)

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

2000-03-01

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

Annual report 1985 of the KfK Central Safety Department

International Nuclear Information System (INIS)

Kiefer, H.; Koelzer, W.; Koenig, L.A.

1986-04-01

The Central Safety Department is responsible for handling all problems of radiation protection, safety and security of the institutes and departments of the Karlsruhe Nuclear Research Center, for waste water activity measurements and environmental monitoring of the whole area of the Center, and for research and development work mainly focusing on nuclear safety and radiation protection measures. The r+d work concentrates on the following aspects: physical and chemical behavior of biologically particularly active radionuclides, behavior of HT in the air/plant/soil system, biophysics of multicellular systems, improvement in radiation protection measurement and personnel dosimetry. This report gives details of the different duties, indicates the results of 1985 routine tasks and reports about results of investigations and developments of the working groups of the Department. The reader is referred to the English translation of the Table of Contents and of Chapter 1 describing the duties and organization of the Central Safety Department. (orig./HP) [de

48 CFR 970.3501 - Federally funded research and development centers.

Science.gov (United States)

2010-10-01

... Development Contracting 970.3501 Federally funded research and development centers. ... 48 Federal Acquisition Regulations System 5 2010-10-01 2010-10-01 false Federally funded research and development centers. 970.3501 Section 970.3501 Federal Acquisition Regulations System DEPARTMENT...

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

International Nuclear Information System (INIS)

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

2009-01-01

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

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

International Nuclear Information System (INIS)

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

1997-07-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

1997-07-01

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

Proceedings of The First National Seminar on Safety, Public Health and Environment

International Nuclear Information System (INIS)

Hiswara, Eri; Bunawas; Dumais, Johannes P.; Alatas, Zubaidah; Melyani

2001-11-01

The first national seminar of safety, public health and environment was held in 23-24 Oct 2001 at the center for research and development of radiation safety and nuclear biomedicine natural energy agency, Indonesia have presented 27 papers, about safety, public health and environment the proceedings is expected to give illustration of the research result on safety, health and environment. (PPIN)

Technology Development for Hydrogen Propellant Storage and Transfer at the Kennedy Space Center (KSC)

Science.gov (United States)

Youngquist, Robert; Starr, Stanley; Krenn, Angela; Captain, Janine; Williams, Martha

2016-01-01

The National Aeronautics and Space Administration (NASA) is a major user of liquid hydrogen. In particular, NASA's John F. Kennedy (KSC) Space Center has operated facilities for handling and storing very large quantities of liquid hydrogen (LH2) since the early 1960s. Safe operations pose unique challenges and as a result NASA has invested in technology development to improve operational efficiency and safety. This paper reviews recent innovations including methods of leak and fire detection and aspects of large storage tank health and integrity. We also discuss the use of liquid hydrogen in space and issues we are addressing to ensure safe and efficient operations should hydrogen be used as a propellant derived from in-situ volatiles.

Microbiological food safety: a dilemma of developing societies.

Science.gov (United States)

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

2014-11-01

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

The Life Cycle of the Child Care Center -- Understanding Center Growth and Development.

Science.gov (United States)

Bess, Gary; Ratekin, Cindy

2001-01-01

Identifies the seven stages of the life cycle for child care centers: entrepreneurial; development; formalization; maturity; stagnation; death; and renewal. Suggests that critical transition points exist for organizational development, and that, if they are aware of and understand each stage of development, administrators may intervene at those…

Development of Safety Kit for Industrial Radiography Application

International Nuclear Information System (INIS)

Mohd Noorul Ikhsan Ahmad; Amry Amin Abas

2011-01-01

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

Preliminary Study on the Development of Quantitative Safety Culture Index

International Nuclear Information System (INIS)

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

2005-01-01

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

Nuclear safety culture in Finland and Sweden - Developments and challenges

International Nuclear Information System (INIS)

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

2011-02-01

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

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

International Nuclear Information System (INIS)

Song, Tae Young

2007-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2007-07-01

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

Development of a measure of safety climate

Directory of Open Access Journals (Sweden)

N. R. Barnes

1990-06-01

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

Recent Experiences of the NASA Engineering and Safety Center (NESC) GN and C Technical Discipline Team (TDT)

Science.gov (United States)

Dennehy, Cornelius J.

2010-01-01

The NASA Engineering and Safety Center (NESC), initially formed in 2003, is an independently funded NASA Program whose dedicated team of technical experts provides objective engineering and safety assessments of critical, high risk projects. The GN&C Technical Discipline Team (TDT) is one of fifteen such discipline-focused teams within the NESC organization. The TDT membership is composed of GN&C specialists from across NASA and its partner organizations in other government agencies, industry, national laboratories, and universities. This paper will briefly define the vision, mission, and purpose of the NESC organization. The role of the GN&C TDT will then be described in detail along with an overview of how this team operates and engages in its objective engineering and safety assessments of critical NASA projects. This paper will then describe selected recent experiences, over the period 2007 to present, of the GN&C TDT in which they directly performed or supported a wide variety of NESC assessments and consultations.

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

International Nuclear Information System (INIS)

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

2004-01-01

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

Safety-related operator actions: methodology for developing criteria

International Nuclear Information System (INIS)

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

1984-03-01

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

Development of safety analysis technology for LMR

International Nuclear Information System (INIS)

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

2005-03-01

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

Progress of nuclear safety research-2004

International Nuclear Information System (INIS)

Anoda, Yoshinari; Ebine, Noriya; Chuto, Toshinori; Sato, Satoshi; Ishikawa, Jun; Yamamoto, Toshihiro; Munakata, Masahiro; Asakura, Toshihide; Yamaguchi, Tetsuji; Kida, Takashi; Matsui, Hiroki; Haneishi, Akihiro; Araya, Fumimasa

2005-03-01

JAERI is conducting nuclear safety research primarily at the Nuclear Safety Research Center in close cooperation with the related departments in accordance with the Long Term Plan for Development and Utilization of Nuclear Energy and Annual Plan for Safety Research issued by the Japanese government. The fields of conducting safety research at JAERI are the engineering safety of nuclear power plants and nuclear fuel cycle facilities, and radioactive waste management as well as advanced technology for safety improvement or assessment. Also, JAERI has conducted international collaboration to share the information on common global issues of nuclear safety and to supplement own research. Moreover, when accidents occurred at nuclear facilities, JAERI has taken a responsible role by providing technical experts and investigation for assistance to the government or local public body. This report summarizes the nuclear safety research activities of JAERI from April 2002 through March 2004 and utilized facilities. (author)

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.)

Annual report 1982 of the Central Safety Department

International Nuclear Information System (INIS)

Kiefer, H.; Koelzer, W.; Koenig, L.A.

1983-04-01

The Safety Officer and the Security Officer are responsible for radiation protection and technical safety, both conventional and nuclear, for the physical protection as well as the safeguards of nuclear materials and radioactive substances within the Kernforschungszentrum Karlsruhe GmbH (KfK). To fulfill these functions they rely on the assistance of the Safety Department. The duties of this Department cover tasks relative to radiation protection, safety and security on behalf of the institutes and departments of KfK and environmental monitoring for the whole Karlsruhe Nuclear Research Center as well as research and development work, mainly performed under the Nuclear Safety Project. The centers of interest of r + d activities are: investigation of the atmospheric diffusion of nuclear pollutants on the micro- and meso-scales, evaluation of the radiological consequences of accidents in reactors under probabilistic aspects, studies of the physical and chemical behavior of radionuclides with particularly high biological effectiveness in the environment, improvements in radiation protection measurement technology. This report gives details of the different duties, indicates the results of 1982 routine tasks and reports about results of investigations and developments of the working groups of the Department. The reader is referred to the English translation of the Table of Contents and of Chapter 1 describing the duties and organization of the Central Safety Department. (orig.) [de

The advantages of reliability centered maintenance for standby safety systems

International Nuclear Information System (INIS)

Dam, R.F.; Ayazzudin, S.; Nickerson, J.H.; DeLong, A.I.

2002-01-01

Full text: On standby safety systems, nuclear plants have to balance the requirements of demonstrating the reliability of each system, while maintaining the system and plant availability. With the goal of demonstrating statistical reliability, these systems have extensive testing programs, which often makes the system unavailable and this can impact the plant capacity. The inputs to the process are often safety and regulatory related, resulting in programs that provide a high level of scrutiny on the systems being considered. In such cases, the value of the application of a maintenance optimization strategy, such as Reliability Centered Maintenance (RCM), is questioned. Part of the question stems from the use of the word 'Reliability' in RCM, which implies a level of redundancy when applied to a system maintenance program driven by reliability requirements. A deeper look at the RCM process, however, shows that RCM has the goal of ensuring that the system operates 'reliably' through the application of an integrated maintenance strategy. This is a subtle, but important distinction. Although the system reliability requirements are an important part of the strategy evaluation, RCM provides a broader context where testing is only one part of an overall strategy focused on ensuring that component function is maintained through a combination of monitoring technologies (including testing), predictive techniques, and intrusive maintenance strategies. Each strategy is targeted to identify known component degradation mechanisms. The conclusion is that a maintenance program driven by reliability requirements will tend to have testing defined at a frequency intended to support the needed statistics. The testing demonstrates that the desired function is available today. Maintenance driven by functional requirements and known failure causes, as developed through an RCM assessment, will have frequencies tied to industry experience with components and rely on a higher degree of

Development and use of safety indicators at STUK

International Nuclear Information System (INIS)

Tiipana, P.

2001-01-01

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

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

Directory of Open Access Journals (Sweden)

Tong Xie

2017-01-01

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

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)

Reactor Safety Assessment System

International Nuclear Information System (INIS)

Sebo, D.E.; Bray, M.A.; King, M.A.

1987-01-01

The Reactor Safety Assessment System (RSAS) is an expert system under development for the United States Nuclear Regulatory Commission (USNRC). RSAS is designed for use at the USNRC Operations Center in the event of a serious incident at a licensed nuclear power plant. RSAS is a situation assessment expert system which uses plant parametric data to generate conclusions for use by the NRC Reactor Safety Team. RSAS uses multiple rule bases and plant specific setpoint files to be applicable to all licensed nuclear power plants in the United States. RSAS currently covers several generic reactor categories and multiple plants within each category

Reactor safety assessment system

International Nuclear Information System (INIS)

Sebo, D.E.; Bray, M.A.; King, M.A.

1987-01-01

The Reactor Safety Assessment System (RSAS) is an expert system under development for the United States Nuclear Regulatory Commission (USNRC). RSA is designed for use at the USNRC Operations Center in the event of a serious incident at a licensed nuclear power plant. RSAS is a situation assessment expert system which uses plant parametric data to generate conclusions for use by the NRC Reactor Safety Team. RSAS uses multiple rule bases and plant specific setpoint files to be applicable to all licensed nuclear power plants in the United States. RSAS currently covers several generic reactor categories and multiple plants within each category

48 CFR 235.017 - Federally Funded Research and Development Centers.

Science.gov (United States)

2010-10-01

... DEVELOPMENT CONTRACTING 235.017 Federally Funded Research and Development Centers. (a) Policy. (2) No DoD... Funded Research and Development Center (FFRDC) if a member of its board of directors or trustees... 48 Federal Acquisition Regulations System 3 2010-10-01 2010-10-01 false Federally Funded Research...

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

International Nuclear Information System (INIS)

El-Shanawany, Mamdouh

2011-01-01

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

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

International Nuclear Information System (INIS)

El-Shanawany, Mamdouh

2011-01-01

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

Development of the Advanced Nuclear Safety Information Management (ANSIM) System

Energy Technology Data Exchange (ETDEWEB)

Sohn, Jae Min; Ko, Young Cheol; Song, Tai Gil [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2012-05-15

Korea has become a technically independent nuclear country and has grown into an exporter of nuclear technologies. Thus, nuclear facilities are increasing in significance at KAERI (Korea Atomic Energy Research Institute), and it is time to address the nuclear safety. The importance of nuclear safety cannot be overemphasized. Therefore, a management system is needed urgently to manage the safety of nuclear facilities and to enhance the efficiency of nuclear information. We have established ISP (Information Strategy Planning) for the Integrated Information System of nuclear facility and safety management. The purpose of this paper is to develop a management system for nuclear safety. Therefore, we developed the Advanced Nuclear Safety Information Management system (hereinafter referred to as the 'ANSIM system'). The ANSIM system has been designed and implemented to computerize nuclear safety information for standardization, integration, and sharing in real-time. Figure 1 shows the main home page of the ANSIM system. In this paper, we describe the design requirements, contents, configurations, and utilizations of the ANSIM system

The Trauma Center Organizational Culture Survey: development and conduction.

Science.gov (United States)

Davis, Matthew L; Wehbe-Janek, Hania; Subacius, Haris; Pinto, Ruxandra; Nathens, Avery B

2015-01-01

The Trauma Center Organizational Culture Survey (TRACCS) instrument was developed to assess organizational culture of trauma centers enrolled in the American College of Surgeons Trauma Quality Program (ACS TQIP). The objective is to provide evidence on the psychometric properties of the factors of TRACCS and describe the current organizational culture of TQIP-enrolled trauma centers. A cross-sectional study was conducted by surveying a sampling of employees at 174 TQIP-enrolled trauma centers. Data collection was preceded by multistep survey development. Psychometric properties were assessed by an exploratory factor analysis (construct validity) and the item-total correlations and Cronbach alpha were calculated (internal reliability). Statistical outcomes of the survey responses were measured by descriptive statistics and mixed effect models. The response rate for trauma center participation in the study was 78.7% (n = 137). The factor analysis resulted in 16 items clustered into three factors as described: opportunity, pride, and diversity, trauma center leadership, and employee respect and recognition. TRACCS was found to be highly reliable with a Cronbach alpha of 0.90 in addition to the three factors (0.91, 0.90, and 0.85). Considerable variability of TRACCS overall and factor score among hospitals was measured, with the largest interhospital deviations among trauma center leadership. More than 80% of the variability in the responses occurred within rather than between hospitals. TRACCS was developed as a reliable tool for measuring trauma center organizational culture. Relationships between TQIP outcomes and measured organizational culture are under investigation. Trauma centers could apply TRACCS to better understand current organizational culture and how change tools can impact culture and subsequent patient and process outcomes. Copyright © 2015 Elsevier Inc. All rights reserved.

Development of safety analysis technology for LMR

International Nuclear Information System (INIS)

Hahn, Do Hee; Kwon, Y. M.; Suk, S. D.

2002-05-01

In the present study, the KALIMER safety analysis has been made for the transients considered in the design concept, hypothetical core disruptive accident (HCDA), and containment performance with the establishment of the design basis. Such analyses have not been possible without the computer code improvement, and the experience attained during this research period must have greatly contributed to the achievement of the self reliance in the domestic technology establishment on the safety analysis areas of the conceptual design. The safety analysis codes have been improved to extend their applicable ranges for detailed conceptual design, and a basic computer code system has been established for HCDA analysis. A code-to-code comparison analysis has been performed as a part of code verification attempt, and the leading edge technology of JNC also has been brought for the technology upgrade. In addition, the research and development on the area of the database establishment has been made for the efficient and systematic project implementation of the conceptual design, through performances on the development of a project scheduling management, integration of the individually developed technology, establishment of the product database, and so on, taking into account coupling of the activities conducted in each specific area

Application of software to development of reactor-safety codes

International Nuclear Information System (INIS)

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

1980-09-01

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

Advanced Messaging Concept Development Basic Safety Message

Data.gov (United States)

Department of Transportation — Contains all Basic Safety Messages (BSMs) collected during the Advanced Messaging Concept Development (AMCD) field testing program. For this project, all of the Part...

European type NPP electric power and vent systems. For safety improvement and proposal of international center

International Nuclear Information System (INIS)

Sugiyama, Kenichiro

2011-01-01

For prevention of reactor accidents of nuclear power plants, multiplicity and redundancy of emergency power would be most important. At station blackout accident, European type manually operated vent operation could minimize release amount of radioactive materials and keep safety of neighboring residents. After Fukushima Daiichi accident, nuclear power plants could not restart operation even after completion of periodical inspection. This article introduced European type emergency power and vent systems in Swiss, Sweden and Germany with state of nuclear power phaseout for reference at considering to upgrade safety and accident mitigation measures for better understanding of the public. In addition, it would be important to recover trust of nuclear technology to continue to disseminate latest information on new knowledge of accident site and decontamination technologies to domestic and overseas people. As its implementation, establishment of Fukushima international center was proposed. (T. Tanaka)

Status Report on the Development of Micro-Scheduling Software for the Advanced Outage Control Center Project

Energy Technology Data Exchange (ETDEWEB)

Germain, Shawn St. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Thomas, Kenneth [Idaho National Lab. (INL), Idaho Falls, ID (United States); Farris, Ronald [Idaho National Lab. (INL), Idaho Falls, ID (United States); Joe, Jeffrey [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2014-09-01

The long-term viability of existing nuclear power plants (NPPs) in the United States (U.S.) is dependent upon a number of factors, including maintaining high capacity factors, maintaining nuclear safety, and reducing operating costs, particularly those associated with refueling outages. Refueling outages typically take 20-30 days, and for existing light water NPPs in the U.S., the reactor cannot be in operation during the outage. Furthermore, given that many NPPs generate between $1-1.5 million/day in revenue when in operation, there is considerable interest in shortening the length of refueling outages. Yet, refueling outages are highly complex operations, involving multiple concurrent and dependent activities that are difficult to coordinate. Finding ways to improve refueling outage performance while maintaining nuclear safety has proven to be difficult. The Advanced Outage Control Center project is a research and development (R&D) demonstration activity under the Light Water Reactor Sustainability (LWRS) Program. LWRS is a R&D program which works with industry R&D programs to establish technical foundations for the licensing and managing of long-term, safe, and economical operation of current NPPs. The Advanced Outage Control Center project has the goal of improving the management of commercial NPP refueling outages. To accomplish this goal, this INL R&D project is developing an advanced outage control center (OCC) that is specifically designed to maximize the usefulness of communication and collaboration technologies for outage coordination and problem resolution activities. This report describes specific recent efforts to develop a capability called outage Micro-Scheduling. Micro-Scheduling is the ability to allocate and schedule outage support task resources on a sub-hour basis. Micro-Scheduling is the real-time fine-tuning of the outage schedule to react to the actual progress of the primary outage activities to ensure that support task resources are

Nuclear safety culture in Finland and Sweden - Developments and challenges

Energy Technology Data Exchange (ETDEWEB)

Reiman, T.; Pietikaeinen, E. (Technical Research Centre of Finland, VTT (Finland)); Kahlbom, U. (RiskPilot AB (Sweden)); Rollenhagen, C. (Royal Institute of Technology (KTH) (Sweden))

2011-02-15

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

Nuclear safety culture based on the organizational and individual culture

International Nuclear Information System (INIS)

Li Jingxi; Ren Ou

2005-01-01

The nuclear safety culture is used increasingly and developed by countries that have nu- clear plants all over the world, since the term 'safety culture' was first introduced by IAEA in 1986. Enterprises culture reflects many terms in an enterprise, such as management level and staff quality. The safety culture is the center in a nuclear enterprises culture, and relates directly to the safety and outstanding achievement of operation. This paper discusses the nuclear safety culture from the viewpoints of the organizational and individual cultures. (authors)

76 FR 9351 - Patient Safety Organizations: Voluntary Delisting From West Virginia Center for Patient Safety

Science.gov (United States)

2011-02-17

... Patient Safety, a component entity of West Virginia Hospital Association, West Virginia Medical Institute (WVMI), and West Virginia State Medical. Association (WVSMA), of its status as a Patient Safety... Patient Safety, a component entity of West Virginia Hospital Association, West Virginia Medical Institute...

Suggestions on the Development of Safety Culture Assessment Method

International Nuclear Information System (INIS)

Choi, Young Sung; Choi, Kwang Sik; Kim, Woong Sik

2006-01-01

Several efforts have been made to assess safety culture of organization that operates nuclear power plants in Korea. The MOST and KINS played a major role to develop assessment methods and KHNP applied them to its NPPs. This paper explains the two methods developed by KINS briefly and presents the insights obtained from the two different applications. It concludes with some suggestions for safety culture assessment based on the insights

The Development, Content, Design, and Conduct of the 2011 Piloted US DOE Nuclear Criticality Safety Program Criticality Safety Engineering Training and Education Project

International Nuclear Information System (INIS)

Hopper, Calvin Mitchell

2011-01-01

In May 1973 the University of New Mexico conducted the first nationwide criticality safety training and education week-long short course for nuclear criticality safety engineers. Subsequent to that course, the Los Alamos Critical Experiments Facility (LACEF) developed very successful 'hands-on' subcritical and critical training programs for operators, supervisors, and engineering staff. Since the inception of the US Department of Energy (DOE) Nuclear Criticality Technology and Safety Project (NCT and SP) in 1983, the DOE has stimulated contractor facilities and laboratories to collaborate in the furthering of nuclear criticality as a discipline. That effort included the education and training of nuclear criticality safety engineers (NCSEs). In 1985 a textbook was written that established a path toward formalizing education and training for NCSEs. Though the NCT and SP went through a brief hiatus from 1990 to 1992, other DOE-supported programs were evolving to the benefit of NCSE training and education. In 1993 the DOE established a Nuclear Criticality Safety Program (NCSP) and undertook a comprehensive development effort to expand the extant LACEF 'hands-on' course specifically for the education and training of NCSEs. That successful education and training was interrupted in 2006 for the closing of the LACEF and the accompanying movement of materials and critical experiment machines to the Nevada Test Site. Prior to that closing, the Lawrence Livermore National Laboratory (LLNL) was commissioned by the US DOE NCSP to establish an independent hands-on NCSE subcritical education and training course. The course provided an interim transition for the establishment of a reinvigorated and expanded two-week NCSE education and training program in 2011. The 2011 piloted two-week course was coordinated by the Oak Ridge National Laboratory (ORNL) and jointly conducted by the Los Alamos National Laboratory (LANL) classroom education and facility training, the Sandia National

Development of ABWR-2 and its safety design

International Nuclear Information System (INIS)

Takafumi, Anegawa; Kenji, Tateiwa

2002-01-01

This paper reports the current status of development project on ABWR-II, a next generation reactor design based on ABWR, and its safety design. This project was initiated over a decade ago and has completed three phases to date. In Phase I (1991-92), basic design requirements were discussed and several plant concepts were studied. In Phase II (1993-95), key design features were selected in order to establish a reference reactor concept. In Phase III (1996-2000), based on the reference reactor concept, modifications and improvements were made to fulfill the design requirements. By adopting large electric output (1 700 MW), large fuel bundle, modified ECCS, and passive heat removal systems, among other design features, we achieved a design concept capable of increasing both economic competitiveness and safety performance. Main focus of this paper will be on the safety design, safety performance, and further research needs related to safety. (authors)

Generic Safety Requirements for Developing Safe Insulin Pump Software

Science.gov (United States)

Zhang, Yi; Jetley, Raoul; Jones, Paul L; Ray, Arnab

2011-01-01

Background The authors previously introduced a highly abstract generic insulin infusion pump (GIIP) model that identified common features and hazards shared by most insulin pumps on the market. The aim of this article is to extend our previous work on the GIIP model by articulating safety requirements that address the identified GIIP hazards. These safety requirements can be validated by manufacturers, and may ultimately serve as a safety reference for insulin pump software. Together, these two publications can serve as a basis for discussing insulin pump safety in the diabetes community. Methods In our previous work, we established a generic insulin pump architecture that abstracts functions common to many insulin pumps currently on the market and near-future pump designs. We then carried out a preliminary hazard analysis based on this architecture that included consultations with many domain experts. Further consultation with domain experts resulted in the safety requirements used in the modeling work presented in this article. Results Generic safety requirements for the GIIP model are presented, as appropriate, in parameterized format to accommodate clinical practices or specific insulin pump criteria important to safe device performance. Conclusions We believe that there is considerable value in having the diabetes, academic, and manufacturing communities consider and discuss these generic safety requirements. We hope that the communities will extend and revise them, make them more representative and comprehensive, experiment with them, and use them as a means for assessing the safety of insulin pump software designs. One potential use of these requirements is to integrate them into model-based engineering (MBE) software development methods. We believe, based on our experiences, that implementing safety requirements using MBE methods holds promise in reducing design/implementation flaws in insulin pump development and evolutionary processes, therefore improving

Thermal-hydraulics technological strategy roadmap for LWR safety improvement and development

International Nuclear Information System (INIS)

Nakamura, Hideo; Arai, Kenji; Oikawa, Hirohide

2015-01-01

New version of the Thermal-Hydraulics Safety Evaluation Fundamental Technology Enhancement Strategy Roadmap (TH-RM) was developed by the Atomic Energy Society of Japan (AESJ) for LWR safety improvement and development. The 1st version of TH-RM was prepared in 2009 under collaboration of utilities, vendors, universities, research institutes and technical support organizations (TSO) for regulatory body. The revision was made by three sub-working groups (SWGs) by considering the lessons learned from the Fukushima Daiichi Accident. The 'safety assessment' SWG pursued development of computer codes for safety assessment. The 'fundamental technology' SWG pursued safety improvement and risk reduction via accident management (AM) measures by referring the technical map for severe accident (SA) established by the 'severe accident' SWG. Phenomena and components for counter-measures and/or proper prediction are identified by going through SA progression in both reactor and spent-fuel pool of PWR and BWR. Twelve important technology development subjects were identified, which include melt coolability enhancement to maintain integrity of containment vessel. Fact Sheet was developed to describe each of identified and selected R and D subjects. External hazards are also considered how to cope with from thermal-hydraulic safety point of view. This paper summarizes the revised TH-RM with several examples and future perspectives. (author)

Developing software for safety-critical applications

International Nuclear Information System (INIS)

Chudleigh, M.

1989-01-01

The effective implementation of many safety-critical systems involves microprocessors running software which needs to be of very high integrity. This article describes some of the problems of producing such software and the place of software within the total system. A development strategy is proposed based on three principles: the goal of defect-free development, the use of mathematical formalism, and the use of an independent team for testing. (author)

Development and design of a computer-assisted information management system for radiation safety management at the University of Washington

International Nuclear Information System (INIS)

Riches, C.G.; Riordan, F.J.; Robb, D.; Grieb, C.; Pence, G.; O'Brien, M.J.

1984-01-01

The Radiation Safety Office (RSO) at the University of Washington (UW) found that it needed a computerized information system to help manage the campus radiation safety program and to help provide the records necessary to show compliance with regulations and license requirements. The John L. Locke Computer Center at the UW had just developed the GLAMOR system to aid information entry and query for their computer when the RSO turned to them for assistance. The module that was developed provided a mechanism for controlling and monitoring radioactive materials on campus. This became one part of a multi-faceted system that registers users, employees, sealed sources and radiation-producing machines. The system is designed to be interactive, for immediate information recall, and powerful enough to provide routine and special reports on compliance status. The RSO information system is designed to be flexible and can easily incorporate additional features. Some future features include an interactive SNM control program, an interface to the information system currently being developed for the occupational safety and health program and an interface to the database provided by the commercial film badge service used by the University. Development of this program lead the RSO to appreciate the usefulness of having health physics professionals on the staff who were also knowledgeable about computers and who could develop programs and reports necessary to their activities

Safety activities and human resource development at NCA

International Nuclear Information System (INIS)

Kumanomido, Hironori; Sakurada, Koichi; Yanagisawa, Shigeru; Masuyama, Tadaharu

2015-01-01

Toshiba Nuclear Critical Assembly (NCA) has been safely operated since the first criticality in December 1963. The topics covered in this Yayoi Meeting Report are: (1) the outline of NCA, (2) the safety control situation mainly after the Great East Japan Earthquake in 2011, (3) educational training incorporates the lessons learned in this earthquake, and (4) human resource development during 2008-2015. Regarding safety control, facility maintenance has been conducted systematically according to the maintenance plan from the viewpoint of preventive maintenance. Regarding educational training, two disaster handling training based on the safety regulation and one nuclear emergency drill based on the emergency drill plan for licensee of nuclear energy activity based on the Act of Special Measures Concerning Nuclear Emergency Preparedness every year. Regarding human resource development, development training was given to 358 people including students. This year, training that does not require NCA operation was conducted including gamma-ray spectrum measurement of NCA fuel rod and neutron deceleration property measurement using 252 Cf neutron source. (S.K.)

Carbon Monoxide Information Center

Medline Plus

Full Text Available ... Reports Injury Statistics NEISS Injury Data Consumer Opinion Surveys About CPSC About CPSC Chairman Commissioners Contact / FAQ ... Guide View All CO Safety Guides ")); jQuery(".node-type-safety-education-center .region-sidebar-second").css('display', " ...

Northwest Hazardous Waste Research, Development, and Demonstration Center: Program Plan

International Nuclear Information System (INIS)

1988-02-01

The Northwest Hazardous Waste Research, Development, and Demonstration Center was created as part of an ongoing federal effort to provide technologies and methods that protect human health and welfare and environment from hazardous wastes. The Center was established by the Superfund Amendments and Reauthorization Act (SARA) to develop and adapt innovative technologies and methods for assessing the impacts of and remediating inactive hazardous and radioactive mixed-waste sites. The Superfund legislation authorized $10 million for Pacific Northwest Laboratory to establish and operate the Center over a 5-year period. Under this legislation, Congress authorized $10 million each to support research, development, and demonstration (RD and D) on hazardous and radioactive mixed-waste problems in Idaho, Montana, Oregon, and Washington, including the Hanford Site. In 1987, the Center initiated its RD and D activities and prepared this Program Plan that presents the framework within which the Center will carry out its mission. Section 1.0 describes the Center, its mission, objectives, organization, and relationship to other programs. Section 2.0 describes the Center's RD and D strategy and contains the RD and D objectives, priorities, and process to be used to select specific projects. Section 3.0 contains the Center's FY 1988 operating plan and describes the specific RD and D projects to be carried out and their budgets and schedules. 9 refs., 18 figs., 5 tabs

Center Independent Research & Developments: JSC IRAD Program

Data.gov (United States)

National Aeronautics and Space Administration — JSC provides and applies its preeminent capabilities in science and technology to develop, operate, and integrate human exploration missions.  The center...

The Development of Laboratory Safety Questionnaire for Middle School Science Teachers

Science.gov (United States)

Akpullukcu, Simge; Cavas, Bulent

2017-01-01

The purpose of this paper is to develop a "valid and reliable laboratory safety questionnaire" which could be used to identify science teachers' understanding about laboratory safety issues during their science laboratory activities. The questionnaire was developed from a literature review and prior instruments developed on laboratory…

Final Report. Center for Scalable Application Development Software

Energy Technology Data Exchange (ETDEWEB)

Mellor-Crummey, John [Rice Univ., Houston, TX (United States)

2014-10-26

The Center for Scalable Application Development Software (CScADS) was established as a part- nership between Rice University, Argonne National Laboratory, University of California Berkeley, University of Tennessee – Knoxville, and University of Wisconsin – Madison. CScADS pursued an integrated set of activities with the aim of increasing the productivity of DOE computational scientists by catalyzing the development of systems software, libraries, compilers, and tools for leadership computing platforms. Principal Center activities were workshops to engage the research community in the challenges of leadership computing, research and development of open-source software, and work with computational scientists to help them develop codes for leadership computing platforms. This final report summarizes CScADS activities at Rice University in these areas.

A conceptual framework to development of construction safety culture in Indonesia

Science.gov (United States)

Armyn Machfudiyanto, Rossy; Latief, Yusuf

2017-12-01

Working accidents in the construction industry are among the highest in the world, affecting the three levels of both macro (National) mezzo (Enterprise) and micro (Projects) that need to be integrated in building a safety culture. The purpose of this research is to develop a conceptual framework in improving safety culture in the construction industry in Indonesia. The methodology was developed using literature study and deductive analysis which then performed expert validation to ensure the concept developed. The result of this research is that policy and institution as input to build safety culture which need to be followed up with increasing of company maturity which have implication to safety performance and construction project performance.

New Possibilities for development of the internal health and safety organisation

DEFF Research Database (Denmark)

Hasle, Peter; Jensen, Per Langå

2004-01-01

Research from several countries indicates that the internal health and safety organisation in most companies is placed in an appendix position. A possibility for developing a stronger and more effective health and safety organisation is to introduce learning. This approach has been applied...... in a Danish network project with eleven companies. The results indicate that health and safety managers and safety representatives have difficulties in fulfilling the role as change agents in mastering such a development project. Only three of the eleven companies turned out to be able to implement successful...

Safety research program of NUCEF

International Nuclear Information System (INIS)

Naito, Y.

1996-01-01

To contribute the safety and establishment of advanced technologies in the area of nuclear fuel cycle, Japan Atomic Energy Research Institute (JAERI) has constructed a new research facility NUCEF (Nuclear Fuel Cycle Safety Engineering Research Facility) as the center for the research and development, particularly on the reprocessing technology and transuranium (TRU) waste management. NUCEF consist of three buildings, administration building, experiment building A and B. Building A has two experiment facilities STACY (Static Experiment Critical Facility) and TRACY (Transient Experiment Critical Facility). The experiment building B is referred to as BECKY (Back-end Fuel Cycle Key Elements Research Facility). Researches on the reprocessing and the waste management are carried out with spent fuels, high-level liquid waste, TRU etc. in the α γ cell and glove boxes. NUCEF was constructed with the following aims. Using STACY and TRACY, are aimed, (1) research on advanced technology for criticality safety control, (2) reconfirmation of criticality safety margin of the Rokkasho reprocessing plant. Using BECKY, are aimed, (1) research on advanced technology of reprocessing process, (2) contribution to develop the scenario for TRU waste disposal, (3) development of new technology for TRU partitioning and volume reduction of radioactive waste. To realize the above aims, following 5 research subjects are settled in NUCEF, (1) Criticality safety research, (2) Research on safety and advanced technology of fuel reprocessing, (3) Research on TRU waste management, (4) Fundamental research on TRU chemistry, (5) Key technology development for TRU processing. (author)

Rules of the Road for Transporting Children--Guidelines for Developing a Motor Vehicle Safety Program.

Science.gov (United States)

Hooker, Bruce; Gearhart, Kentin

1999-01-01

Discusses safety issues for child care centers that provide transportation for children. Notes the importance of vehicle usage and control, driver qualifications, vehicle maintenance, child securement, accident procedures, and driver education and training. (JPB)

Developing glovebox robotics to meet the national robot safety standard and nuclear safety criteria

International Nuclear Information System (INIS)

McMahon, T.T.; Sievers, R.H.

1991-09-01

Development of a glove box based robotic system by the Lawrence Livermore National Laboratory (LLNL) is reported. Safety issues addressed include planning to meet the special constraints of operations within a hazardous material glove box and with hostile environments, compliance with the current and draft national robotic system safety standards, and eventual satisfaction of nuclear material handling requirements. Special attention has been required for the revision to the robot and control system models which antedate adoption of the present national safety standard. A robotic test bed, using non-radioactive surrogates is being activated at the Lawrence Livermore National Laboratory to develop the material handling system and the process interfaces for future special nuclear material processing applications. Part of this effort is to define, test, and revise adequate safety controls to ensure success when the system is eventually deployed at a DOE site. The current system is primarily for demonstration and testing, but will evolve into the baseline configuration from which the production system is to be derived. This results in special hazards associated with research activities which may not be present on a production line. Nuclear safety is of paramount importance and has been successfully addressed for 50 years in the DOE weapons production complex. It carries its particular requirements for robot systems and manual operations, as summarized below: Criticality must be avoided (materials cannot consolidate or accumulate to approach a critical mass). Radioactive materials must be confined. The public and workers must be protected from accountable radiation exposure. Nuclear material must be readily retrievable. Nuclear safety must be conclusively demonstrated through hazards analysis. 7 refs

Environment, safety and health compliance assessment, Feed Materials Production Center, Fernald, Ohio

Energy Technology Data Exchange (ETDEWEB)

1989-09-01

The Secretary of Energy established independent Tiger Teams to conduct environment, safety, and health (ES H) compliance assessments at US Department of Energy (DOE) facilities. This report presents the assessment of the Feed Materials Production Center (FMPC) at Fernald, Ohio. The purpose of the assessment at FMPC is to provide the Secretary with information regarding current ES H compliance status, specific ES H noncompliance items, evaluation of the adequacy of the ES H organizations and resources (DOE and contractor), and root causes for noncompliance items. Areas reviewed included performance under Federal, state, and local agreements and permits; compliance with Federal, state and DOE orders and requirements; adequacy of operations and other site activities, such as training, procedures, document control, quality assurance, and emergency preparedness; and management and staff, including resources, planning, and interactions with outside agencies.

Safety related maintenance in the framework of the reliability centered maintenance concept

International Nuclear Information System (INIS)

1992-07-01

Elevated safety requirements and ever increasing costs of maintenance of nuclear power plants stimulate the interest in different methods and approaches to optimize maintenance activities. Among different concepts, the Reliability Centered Maintenance (RCM) as an approach to improve Preventive Maintenance (PM) programmes is being widely discussed an applied in several IAEA Member States. In order to summarize basic principles and current implementation of the RCM, the IAEA organized a Consultants Meeting in November 1990. The report prepared during that meeting was discussed during the Technical Committee Meeting (TCM) held in May 1991. Numerous technical presentations as well as panel and plenary discussions took place at the TCM. This document contains the report of the Consultants Meeting (modified to include comments of the TCM), a summary of the most important discussions as well as all 14 papers presented at the TCM

Safety management of a complex R and D ground operating system

Science.gov (United States)

Connors, J. F.; Maurer, R. A.

1975-01-01

A perspective on safety program management was developed for a complex R&D operating system, such as the NASA-Lewis Research Center. Using a systems approach, hazardous operations are subjected to third-party reviews by designated-area safety committees and are maintained under safety permit controls. To insure personnel alertness, emergency containment forces and employees are trained in dry-run emergency simulation exercises. The keys to real safety effectiveness are top management support and visibility of residual risks.

Safety of Diagnostic Cerebral and Spinal Digital Subtraction Angiography in a Developing Country: A Single-Center Experience.

Science.gov (United States)

Bashir, Qasim; Ishfaq, Asim; Baig, Ammad Anwar

2018-02-01

Digital subtraction angiography (DSA) remains the gold standard imaging modality for cerebrovascular disorders. In contrast to developed countries, the safety of the procedure is not extensively reported from the developing countries. Herein, we present a retrospective analysis of the basic technique, indications, and outcomes in 286 patients undergoing diagnostic cerebral and spinal angiography in a developing country, Pakistan. A retrospective review of patient demographics, procedural technique and complication rates of 286 consecutive patients undergoing the diagnostic cerebral/spinal angiography procedure at one institution from May 2013 to December 2015 was performed. Neurological, systemic, or local complications occurring within and after 24 h of the procedure were recorded. Mean age reported for all patients was 49.7 years. Of all the 286 cases, 175 were male (61.2%) and the rest female (111, 38.8%). Cerebral DSA was performed in 279 cases (97.6%), with 7 cases of spinal DSA (2.4%). Subarachnoid hemorrhage was the most common indication for DSA accounting for 88 cases (30.8%), closely followed by stroke (26.6%) and arteriosclerotic vascular disease (23.1%). No intra- or post-procedural neurological complications of any severity were seen in any of the 286 cases. One case of asymptomatic aortic dissection was reported (0.3%) in the entire cohort of patient population. Diagnostic cerebral/spinal digital subtraction angiography was found to be safe in Pakistan, with complication rates at par with and comparable to those reported in the developed world.

The Radiation Safety Information Computational Center (RSICC): A Resource for Nuclear Science Applications

International Nuclear Information System (INIS)

Kirk, Bernadette Lugue

2009-01-01

The Radiation Safety Information Computational Center (RSICC) has been in existence since 1963. RSICC collects, organizes, evaluates and disseminates technical information (software and nuclear data) involving the transport of neutral and charged particle radiation, and shielding and protection from the radiation associated with: nuclear weapons and materials, fission and fusion reactors, outer space, accelerators, medical facilities, and nuclear waste management. RSICC serves over 12,000 scientists and engineers from about 100 countries. An important activity of RSICC is its participation in international efforts on computational and experimental benchmarks. An example is the Shielding Integral Benchmarks Archival Database (SINBAD), which includes shielding benchmarks for fission, fusion and accelerators. RSICC is funded by the United States Department of Energy, Department of Homeland Security and Nuclear Regulatory Commission.

Safer Systems: A NextGen Aviation Safety Strategic Goal

Science.gov (United States)

Darr, Stephen T.; Ricks, Wendell R.; Lemos, Katherine A.

2008-01-01

The Joint Planning and Development Office (JPDO), is charged by Congress with developing the concepts and plans for the Next Generation Air Transportation System (NextGen). The National Aviation Safety Strategic Plan (NASSP), developed by the Safety Working Group of the JPDO, focuses on establishing the goals, objectives, and strategies needed to realize the safety objectives of the NextGen Integrated Plan. The three goal areas of the NASSP are Safer Practices, Safer Systems, and Safer Worldwide. Safer Practices emphasizes an integrated, systematic approach to safety risk management through implementation of formalized Safety Management Systems (SMS) that incorporate safety data analysis processes, and the enhancement of methods for ensuring safety is an inherent characteristic of NextGen. Safer Systems emphasizes implementation of safety-enhancing technologies, which will improve safety for human-centered interfaces and enhance the safety of airborne and ground-based systems. Safer Worldwide encourages coordinating the adoption of the safer practices and safer systems technologies, policies and procedures worldwide, such that the maximum level of safety is achieved across air transportation system boundaries. This paper introduces the NASSP and its development, and focuses on the Safer Systems elements of the NASSP, which incorporates three objectives for NextGen systems: 1) provide risk reducing system interfaces, 2) provide safety enhancements for airborne systems, and 3) provide safety enhancements for ground-based systems. The goal of this paper is to expose avionics and air traffic management system developers to NASSP objectives and Safer Systems strategies.

Human Factors Process Task Analysis Liquid Oxygen Pump Acceptance Test Procedure for the Advanced Technology Development Center

Science.gov (United States)

Diorio, Kimberly A.

2002-01-01

A process task analysis effort was undertaken by Dynacs Inc. commencing in June 2002 under contract from NASA YA-D6. Funding was provided through NASA's Ames Research Center (ARC), Code M/HQ, and Industrial Engineering and Safety (IES). The John F. Kennedy Space Center (KSC) Engineering Development Contract (EDC) Task Order was 5SMA768. The scope of the effort was to conduct a Human Factors Process Failure Modes and Effects Analysis (HF PFMEA) of a hazardous activity and provide recommendations to eliminate or reduce the effects of errors caused by human factors. The Liquid Oxygen (LOX) Pump Acceptance Test Procedure (ATP) was selected for this analysis. The HF PFMEA table (see appendix A) provides an analysis of six major categories evaluated for this study. These categories include Personnel Certification, Test Procedure Format, Test Procedure Safety Controls, Test Article Data, Instrumentation, and Voice Communication. For each specific requirement listed in appendix A, the following topics were addressed: Requirement, Potential Human Error, Performance-Shaping Factors, Potential Effects of the Error, Barriers and Controls, Risk Priority Numbers, and Recommended Actions. This report summarizes findings and gives recommendations as determined by the data contained in appendix A. It also includes a discussion of technology barriers and challenges to performing task analyses, as well as lessons learned. The HF PFMEA table in appendix A recommends the use of accepted and required safety criteria in order to reduce the risk of human error. The items with the highest risk priority numbers should receive the greatest amount of consideration. Implementation of the recommendations will result in a safer operation for all personnel.

Development of quantitative goals for inherent safety feature design and licensing

International Nuclear Information System (INIS)

Kastenberg, W.E.; Apostolakis, G.; Dhir, V.K.; Okrent, D.

1987-01-01

There is now considerable interest in the development of advanced fast reactors whose major focus is inherent safety. The achievement of inherent safety can be viewed from several aspects. In the Integral Fast Reactor Concept the approach is to utilize the intrinsic characteristics of pool-type liquid metal fast breeder reactors (LMFBRs) and the properties of metal fuels to integrate a high degree of inherent safety into the design. The PRISM and SAFR concepts focus on other inherent safety features. The reactors discussed above represent a radical departure from existing LWR designs as well as previous LMFBR designs (e.g., CRBRP) which are based, for the most part, on the General Design Criteria found in 10CFR50 Appendix. In view of these parallel developments (advanced reactors exploiting inherent safety and the use of quantitative goals to augment licensing), there appears to be a need to perform research on the development of methods for designing, assessing, and licensing inherent safety features in advanced reactors. The objectives of such research are outlined

General safety basis development guidance for environmental restoration decontamination and decommissioning

International Nuclear Information System (INIS)

Ellingson, D.R.; Kerr, N.; Bohlander, K.; Hansen, J.; Crowley, W.

1994-02-01

Safety analyses have the objective of contributing to two essential ingredients of a successful operation. The first is promoting the safety of the operation through worker involvement in information development (safety basis). The second is obtaining approval to conduct the operation (authorization). Typically these ingredients are assembled under separate programs covered by separate DOE requirements. DOE authorization relies on successful development of a document containing up to 21 topics written in terms and language suited to reviewers and approvers. Safety relies on successful training and procedures that convert the technical documented information into terms and language understandable to the worker. This separation can lead to successful incorporation of one ingredient independent of the other. At best, this separation may result in a safe but unauthorized operation; at worst, the separation may result in an unsafe operation authorized to proceed. This guide is based on experiences gained by contractors who have integrated rather than separated the safety and authorization. The short duration of ER/D ampersand D activities, the uncertainties of hazards, and the publicly expressed desire for demonstrable progress in cleanup activities add emphasis to the need to integrate rather than separate and develop new programs. Experience-based information has been useful to workers, safety analysis practitioners, and reviewers in the following ways: (1) Acquiring or developing the needed information in a useful form; (2) Managing the uncertainties during activity development and operation; (3) Identifying the subset of applicable requirements for an activity; (4) Developing the appropriate level of documentation detail for a specific activity; and (5) Increasing the usefulness and use of safety analysis (ownership)

77 FR 40622 - Mine Safety and Health Research Advisory Committee, National Institute for Occupational Safety...

Science.gov (United States)

2012-07-10

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Mine Safety and Health Research Advisory Committee, National Institute for Occupational Safety and Health (MSHRAC, NIOSH..., oxygen supply partnership, safety culture, occupational health and safety management systems, preventing...

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.

Safety and effective developing nuclear power to realize green and low-carbon development

Directory of Open Access Journals (Sweden)

Qi-Zhen Ye

2016-03-01

Full Text Available This paper analyzes the role of nuclear power of China's energy structure and industry system. Comparing with other renewable energy the nuclear power chain has very low greenhouse gas emission, so it will play more important role in China's low-carbon economy. The paper also discussed the necessity of nuclear power development to achieve emission reduction, energy structure adjustment, nuclear power safety, environmental protection, enhancement of nuclear power technology, nuclear waste treatment, and disposal, as well as nuclear power plant decommissioning. Based on the safety record and situation of the existing power plants in China, the current status of the development of world nuclear power technology, and the features of the independently designed advanced power plants in China, this paper aims to demonstrate the safety of nuclear power. A nuclear power plant will not cause harm either to the environment and nor to the public according to the real data of radioactivity release, which are obtained from an operational nuclear plant. The development of nuclear power technology can enhance the safety of nuclear power. Further, this paper discusses issues related to the nuclear fuel cycle, the treatment, and disposal strategies of nuclear waste, and the decommissioning of a nuclear power plant, all of which are issues of public concern.

Developing the Safety of Atrial Fibrillation Ablation Registry Initiative (SAFARI) as a collaborative pan-stakeholder critical path registry model: a Cardiac Safety Research Consortium "Incubator" Think Tank.

Science.gov (United States)

Al-Khatib, Sana M; Calkins, Hugh; Eloff, Benjamin C; Kowey, Peter; Hammill, Stephen C; Ellenbogen, Kenneth A; Marinac-Dabic, Danica; Waldo, Albert L; Brindis, Ralph G; Wilbur, David J; Jackman, Warren M; Yaross, Marcia S; Russo, Andrea M; Prystowsky, Eric; Varosy, Paul D; Gross, Thomas; Pinnow, Ellen; Turakhia, Mintu P; Krucoff, Mitchell W

2010-10-01

Although several randomized clinical trials have demonstrated the safety and efficacy of catheter ablation of atrial fibrillation (AF) in experienced centers, the outcomes of this procedure in routine clinical practice and in patients with persistent and long-standing persistent AF remain uncertain. Brisk adoption of this therapy by physicians with diverse training and experience highlights potential concerns regarding the safety and effectiveness of this procedure. Some of these concerns could be addressed by a national registry of AF ablation procedures such as the Safety of Atrial Fibrillation Ablation Registry Initiative that was initially proposed at a Cardiac Safety Research Consortium Think Tank meeting in April 2009. In January 2010, the Cardiac Safety Research Consortium, in collaboration with the Duke Clinical Research Institute, the US Food and Drug Administration, the American College of Cardiology, and the Heart Rhythm Society, held a follow-up meeting of experts in the field to review the construct and progress to date. Other participants included the National Heart, Lung, and Blood Institute; the Centers for Medicare and Medicaid Services; the Agency for Healthcare Research and Quality; the AdvaMed AF working group; and additional industry representatives. This article summarizes the discussions that occurred at the meeting of the state of the Safety of Atrial Fibrillation Ablation Registry Initiative, the identification of a clear pathway for its implementation, and the exploration of solutions to potential issues in the execution of this registry. Copyright © 2010 Mosby, Inc. All rights reserved.

Development of the KINS Safety Culture Maturity Model for Self and Independent Assessment

International Nuclear Information System (INIS)

Sheen, C.; Choi, Y.S.

2016-01-01

Safety culture of an organization is cultivated and affected not only by societal and regulatory environment of the organization, but by its philosophies, policies, events and activities experienced in the process of accomplishing its mission. The safety culture would be continuously changed by the interactions between its members along with time as an organic entity. In order to perform a systematic self- or independent assessment of safety culture, a safety culture assessment model (SCAM) properly reflecting cultural characteristics should be necessary. In addition, a SCAM should be helpful not only to establish correct directions, goals, and strategies for safety culture development, but should anticipating obstacles against safety culture development in the implementation process derived from the assessment. In practical terms, a SCAM should be useful for deriving effective guidelines and implementing of corrective action programs for the evaluated organization. Korea Institute of Nuclear Safety (KINS) performed a research project for six years to develop a SCAM satisfying the above prerequisites for self- and independent assessment. The KINS SCAM was developed based on the five stage safety culture maturity model proposed by Professor Patrick Hudson and was modified into four stages to reflect existing safety culture assessment experiences at Korean nuclear power plants. In order to define the change mechanism of safety culture for development and reversion, the change model proposed by Prochaska and DiClemente was introduced into KINS SCAM and developed into the Spiral Change Model.

Health and safety at DNE [Dounreay Nuclear Power Development Establishment

International Nuclear Information System (INIS)

Walford, J.G.; Tyler, G.R.

1988-11-01

This report reviews health and safety experience at the UKAEA's Dounreay Nuclear Power Development Establishment for 1986 and gives relevant data in the fields of health physics and general safety. It includes sections on: organization, policy and training; monitoring of the working environment; personnel monitoring; protection of the public; radiological incidents; and non-radiological health and safety. (author)

Scale development of safety management system evaluation for the airline industry.

Science.gov (United States)

Chen, Ching-Fu; Chen, Shu-Chuan

2012-07-01

The airline industry relies on the implementation of Safety Management System (SMS) to integrate safety policies and augment safety performance at both organizational and individual levels. Although there are various degrees of SMS implementation in practice, a comprehensive scale measuring the essential dimensions of SMS is still lacking. This paper thus aims to develop an SMS measurement scale from the perspective of aviation experts and airline managers to evaluate the performance of company's safety management system, by adopting Schwab's (1980) three-stage scale development procedure. The results reveal a five-factor structure consisting of 23 items. The five factors include documentation and commands, safety promotion and training, executive management commitment, emergency preparedness and response plan and safety management policy. The implications of this SMS evaluation scale for practitioners and future research are discussed. Copyright © 2012 Elsevier Ltd. All rights reserved.

User-centered ecotourism development.

Science.gov (United States)

Talsma, L; Molenbroek, J F M

2012-01-01

The transfer of knowledge in an ecotourism project is never a one-way affair. An approach connected to bottom-up development is the submersion into another culture, while creating a new organizational structure. For co-creation, patterns that are often latent, such as leadership roles, the association with business, or even the color of education can be revealed by carefully facilitated brainstorms or workshops. Especially in countries with a different hierarchical structure, such as Indonesia compared to Holland, a careful analysis is needed before starting cooperation. Although a case is only a temporary view on a situation and not a guarantee for a truly sustainable system, the bottom-up approach tested has interesting starting points for an ecotourism system. Two cases were conducted in Bali, Indonesia, which resulted in guidelines on how to approach user-centered ecotourism development.

The quantifying of road safety developments. Paper presented at the International Conference 'Road Safety in Europe', Birmingham, September 9-11, 1996.

NARCIS (Netherlands)

Koornstra, M.J.

1996-01-01

The evaluation of the effectiveness of road safety policies and measures must be based on quantative information in road safety developments and the relevant variables that influence that development. However, the concept of road safety itself is not well defined theoretically and quantatively. This

Developing an OMERACT Core Outcome Set for Assessing Safety Components in Rheumatology Trials: The OMERACT Safety Working Group.

Science.gov (United States)

Klokker, Louise; Tugwell, Peter; Furst, Daniel E; Devoe, Dan; Williamson, Paula; Terwee, Caroline B; Suarez-Almazor, Maria E; Strand, Vibeke; Woodworth, Thasia; Leong, Amye L; Goel, Niti; Boers, Maarten; Brooks, Peter M; Simon, Lee S; Christensen, Robin

2017-12-01

Failure to report harmful outcomes in clinical research can introduce bias favoring a potentially harmful intervention. While core outcome sets (COS) are available for benefits in randomized controlled trials in many rheumatic conditions, less attention has been paid to safety in such COS. The Outcome Measures in Rheumatology (OMERACT) Filter 2.0 emphasizes the importance of measuring harms. The Safety Working Group was reestablished at the OMERACT 2016 with the objective to develop a COS for assessing safety components in trials across rheumatologic conditions. The safety issue has previously been discussed at OMERACT, but without a consistent approach to ensure harms were included in COS. Our methods include (1) identifying harmful outcomes in trials of interventions studied in patients with rheumatic diseases by a systematic literature review, (2) identifying components of safety that should be measured in such trials by use of a patient-driven approach including qualitative data collection and statistical organization of data, and (3) developing a COS through consensus processes including everyone involved. Members of OMERACT including patients, clinicians, researchers, methodologists, and industry representatives reached consensus on the need to continue the efforts on developing a COS for safety in rheumatology trials. There was a general agreement about the need to identify safety-related outcomes that are meaningful to patients, framed in terms that patients consider relevant so that they will be able to make informed decisions. The OMERACT Safety Working Group will advance the work previously done within OMERACT using a new patient-driven approach.

Development of safety performance indicators of regulatory interest (SAFPER) in Pakistan

International Nuclear Information System (INIS)

Khatoon, Abida

2002-01-01

Safety performance indicators provide a very useful tool for monitoring operational safety of a nuclear power plant. Utilities in many countries have developed plant specific indicators for the assessment of their performance and safety. Regulators can make use of some of these indicators for their regulatory assessment. In addition to these regulatory bodies in some countries have also developed programs for the formulation of safety performance indicators which are used in monitoring operational safety and regulatory decision making. Realizing its usefulness Directorate of Nuclear Safety and Radiation Protection (DNSRP-the regulatory body in Pakistan) has also initiated a country specific program for the development of Safety Performance Indicators (SAFPER) based on data provided by the utility and that collected during the course of regulatory inspections. Selected areas of NPP operation to be monitored are: - Significant events; - Safety systems performance; - Barriers integrity; - Environment protection; - Workers radiation safety; and - Emergency Preparedness. One of the objectives of this program is also to monitor the effectiveness of DNSRP regulatory activities. IAEA framework is taken as one of the bases for our program. Safety performance will be assessed on the basis of Performance Indicators and inspection findings. DNSRP program as shown in Appendix includes the indicators in use and under development. It is felt that the term Safety Performance Indicators may be termed as 'SAFPER Indicators' to be used by the Regulators, as it is clear from this presentation that utility safety performance indicators together with the regulatory effectiveness indicators constitute the measure for the adequate safety to the public and the environment. Additional research is still necessary for: - indicator definition for the proposed and under developed indicators; - data collection systems; - thresholds; - trend analysis; - goal setting (benefit from the trend can be

The development of safety cases for healthcare services: Practical experiences, opportunities and challenges

International Nuclear Information System (INIS)

Sujan, Mark; Spurgeon, Peter; Cooke, Matthew; Weale, Andy; Debenham, Philip; Cross, Steve

2015-01-01

There has been growing interest in the concept of safety cases for medical devices and health information technology, but questions remain about how safety cases can be developed and used meaningfully in the safety management of healthcare services and processes. The paper presents two examples of the development and use of safety cases at a service level in healthcare. These first practical experiences at the service level suggest that safety cases might be a useful tool to support service improvement and communication of safety in healthcare. The paper argues that safety cases might be helpful in supporting healthcare organisations with the adoption of proactive and rigorous safety management practices. However, it is also important to consider the different level of maturity of safety management and regulatory oversight in healthcare. Adaptations to the purpose and use of safety cases might be required, complemented by the provision of education to both practitioners and regulators. - Highlights: • Empirical description of safety case development at service level in healthcare. • Safety cases can support adoption of proactive and rigorous safety management. • Adaptation to purpose and use of safety cases might be required in healthcare. • Education should be provided to practitioners and regulators

Safety assessment in primary Mycobacterium tuberculosis smear microscopy centres in Blantyre Malawi: a facility based cross sectional survey.

Science.gov (United States)

Majamanda, J; Ndhlovu, P; Shawa, I T

2013-12-01

Tuberculosis (TB) is caused by Mycobacterium tuberculosis and is transmitted mainly through aerosolization of infected sputum which puts laboratory workers at risk in spite of the laboratory workers' risk of infection being at 3 to 9 times higher than the general public. Laboratory safety should therefore be prioritized and optimized to provide sufficient safety to laboratory workers. To assess the safety for the laboratory workers in TB primary microscopy centres in Blantyre urban. TB primary microscopy centers in Blantyre urban were assessed in aspects of equipment availability, facility layout, and work practice, using a standardized WHO/AFRO ISO 15189 checklist for the developing countries which sets the minimum safety score at ≥80%. Each center was graded according to the score it earned upon assessment. Only one (1) microscopy center out nine (9) reached the minimum safety requirement. Four (4) centers were awarded 1 star level, four (4) centers were awarded 2 star level and only one (1) center was awarded 3 star level. In Blantyre urban, 89% of the Tuberculosis microscopy centers are failing to provide the minimum safety to the laboratory workers. Government and other stake holders should be committed in addressing the safety challenges of TB microscopy centres in the country to ensure safety for the laboratory workers. It is recommended that the study be conducted at the regional or national level for both public and private laboratories in order to have a general picture of safety in Tb microscopy centres possibly across the country.

Understanding adolescent development: implications for driving safety.

Science.gov (United States)

Keating, Daniel P

2007-01-01

The implementation of Graduated Driver Licensing (GDL) programs has significantly improved the crash and fatality rates of novice teen drivers, but these rates remain unacceptably high. A review of adolescent development research was undertaken to identify potential areas of improvement. Research support for GDL was found to be strong, particularly regarding early acquisition of expertise in driving safety (beyond driving skill), and to limitations that reduce opportunities for distraction. GDL regimes are highly variable, and no US jurisdictions have implemented optimal regimes. Expanding and improving GDL to enhance acquisition of expertise and self-regulation are indicated for implementation and for applied research. Driver training that effectively incorporates safety goals along with driving skill is another target. The insurance industry will benefit from further GDL enhancements. Benefits may accrue to improved driver training, improved simulation devices during training, and automated safety feedback instrumentation.

Developments in safety standards and regulation

International Nuclear Information System (INIS)

Harbison, S.A.

1994-01-01

This paper explains, in broad terms, how regulatory control is exercised over licensed nuclear installations in the UK and how HSE has developed its safety standards to support its regulatory approach. It first sets out the scope of HSE's regulatory responsibilities, which NII exercises on its behalf, and briefly describes the licensing process and compliance monitoring through inspection over the life of a nuclear plant. It also refers to the role of assessment in NII's decision-making processes, and the part played in this by the consideration of costs and safety benefits. It then moves on to consider the challenges that HSE/NII are likely to face from the changing nuclear industry in the second half of the 1990s. (author)

Advanced research workshop: nuclear materials safety

International Nuclear Information System (INIS)

Jardine, L J; Moshkov, M M.

1999-01-01

The Advanced Research Workshop (ARW) on Nuclear Materials Safety held June 8-10, 1998, in St. Petersburg, Russia, was attended by 27 Russian experts from 14 different Russian organizations, seven European experts from six different organizations, and 14 U.S. experts from seven different organizations. The ARW was conducted at the State Education Center (SEC), a former Minatom nuclear training center in St. Petersburg. Thirty-three technical presentations were made using simultaneous translations. These presentations are reprinted in this volume as a formal ARW Proceedings in the NATO Science Series. The representative technical papers contained here cover nuclear material safety topics on the storage and disposition of excess plutonium and high enriched uranium (HEU) fissile materials, including vitrification, mixed oxide (MOX) fuel fabrication, plutonium ceramics, reprocessing, geologic disposal, transportation, and Russian regulatory processes. This ARW completed discussions by experts of the nuclear materials safety topics that were not covered in the previous, companion ARW on Nuclear Materials Safety held in Amarillo, Texas, in March 1997. These two workshops, when viewed together as a set, have addressed most nuclear material aspects of the storage and disposition operations required for excess HEU and plutonium. As a result, specific experts in nuclear materials safety have been identified, know each other from their participation in t he two ARW interactions, and have developed a partial consensus and dialogue on the most urgent nuclear materials safety topics to be addressed in a formal bilateral program on t he subject. A strong basis now exists for maintaining and developing a continuing dialogue between Russian, European, and U.S. experts in nuclear materials safety that will improve the safety of future nuclear materials operations in all the countries involved because of t he positive synergistic effects of focusing these diverse backgrounds of

Development of the Structural Materials Information Center

International Nuclear Information System (INIS)

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

1990-01-01

The US Nuclear Regulatory Commission has initiated a Structural Aging Program at the Oak Ridge National Laboratory to identify potential structural safety issues related to continued service of nuclear power plants and to establish criteria for evaluating and resolving these issues. One of the tasks in this program focuses on the establishment of a Structural Materials Information Center where data and information on the time variation of concrete and other structural material properties under the influence of pertinent environmental stressors and aging factors are being collected and assembled into a data base. This data base will be used to assist in the prediction of potential long-term deterioration of critical structural components in nuclear power plants and to establish limits on hostile environmental exposure for these structures and materials. Two complementary data base formats have been developed. The Structural Materials Handbook is an expandable, hard-copy reference document that contains complete sets of data and information for selected portland cement concrete, metallic reinforcement, prestressing tendon, and structural steel materials. Baseline data, reference properties and environmental information are presented in the handbook as tables, notes and graphs. The handbook, which will be published in four volumes, serves as the information source for the electronic data base. The Structural Materials Electronic Data Base is accessible by an IBM-compatible personal computer and provides an efficient means for searching the various data base files to locate materials with similar properties. Properties will be reported in the International System of Units (SI) and in customary units whenever possible. 7 refs., 3 figs., 4 tabs

An Integrated Development Tool for a safety application using FBD language

Energy Technology Data Exchange (ETDEWEB)

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

2012-05-15

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

Development and validation of a remote home safety protocol.

Science.gov (United States)

Romero, Sergio; Lee, Mi Jung; Simic, Ivana; Levy, Charles; Sanford, Jon

2018-02-01

Environmental assessments and subsequent modifications conducted by healthcare professionals can enhance home safety and promote independent living. However, travel time, expense and the availability of qualified professionals can limit the broad application of this intervention. Remote technology has the potential to increase access to home safety evaluations. This study describes the development and validation of a remote home safety protocol that can be used by a caregiver of an elderly person to video-record their home environment for later viewing and evaluation by a trained professional. The protocol was developed based on literature reviews and evaluations from clinical and content experts. Cognitive interviews were conducted with a group of six caregivers to validate the protocol. The final protocol included step-by-step directions to record indoor and outdoor areas of the home. The validation process resulted in modifications related to safety, clarity of the protocol, readability, visual appearance, technical descriptions and usability. Our final protocol includes detailed instructions that a caregiver should be able to follow to record a home environment for subsequent evaluation by a home safety professional. Implications for Rehabilitation The results of this study have several implications for rehabilitation practice The remote home safety evaluation protocol can potentially improve access to rehabilitation services for clients in remote areas and prevent unnecessary delays for needed care. Using our protocol, a patient's caregiver can partner with therapists to quickly and efficiently evaluate a patient's home before they are released from the hospital. Caregiver narration, which reflects a caregiver's own perspective, is critical to evaluating home safety. In-home safety evaluations, currently not available to all who need them due to access barriers, can enhance a patient's independence and provide a safer home environment.

Perspectives on reactor safety. Revision 1

International Nuclear Information System (INIS)

Haskin, F.E.; Hodge, S.A.

1997-11-01

The US Nuclear Regulatory Commission (NRC) maintains a technical training center at Chattanooga, Tennessee to provide appropriate training to both new and experienced NRC employees. This document describes a one-week course in reactor safety concepts. The course consists of five modules: (1) the development of safety concepts; (2) severe accident perspectives; (3) accident progression in the reactor vessel; (4) containment characteristics and design bases; and (5) source terms and offsite consequences. The course text is accompanied by slides and videos during the actual presentation of the course

Perspectives on reactor safety. Revision 1

Energy Technology Data Exchange (ETDEWEB)

Haskin, F.E. [New Mexico Univ., Albuquerque, NM (United States). Dept. of Chemical and Nuclear Engineering; Camp, A.L. [Sandia National Labs., Albuquerque, NM (United States); Hodge, S.A. [Oak Ridge National Lab., TN (United States). Engineering Technology Div.

1997-11-01

The US Nuclear Regulatory Commission (NRC) maintains a technical training center at Chattanooga, Tennessee to provide appropriate training to both new and experienced NRC employees. This document describes a one-week course in reactor safety concepts. The course consists of five modules: (1) the development of safety concepts; (2) severe accident perspectives; (3) accident progression in the reactor vessel; (4) containment characteristics and design bases; and (5) source terms and offsite consequences. The course text is accompanied by slides and videos during the actual presentation of the course.

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.

Development of French technical safety regulations: safety fundamental rules

International Nuclear Information System (INIS)

Lebouleux, P.

1982-09-01

The technical regulation related to nuclear safety in France is made of a set of regulation texts, of a different nature, that define the requirements for the construction, commissioning and operations of nuclear facilities. Simultaneously, the safety authorities (Service Central de Surete des Installations Nucleaires: SCSIN) issue recommendations or guides which are not strictly speaking regulations in the juridical sense; they are called ''Regles Fondamentales de Surete'' (RFS). The RFS set up and detail the conditions, the respect of which is deemed to be complying with the French regulation pratice, for the subject to which they relate. Their purpose is to make known rules judged acceptable by safety authorities, thus making the safety review easier. The RFS program is described. A RFS -or a letter- can also give the result of the examination of the constructor and operator code (RCC) by safety authorities

Development of French technical safety regulations: safety fundamental rules

International Nuclear Information System (INIS)

Lebouleux, P.

1983-01-01

The technical regulation related to nuclear safety in France is made of a set of regulation texts, of a different nature, that define the requirements for the construction, commissioning and operating of nuclear facilities. Simultaneously, the safety authorities (Service Central de Surete des Installations Nucleaires: SCSIN) issue recommendations or guides which are not strictly speaking regulations in the juridicial sense; they are called Regles Fondamentales de Surete (RFS). The RFS set up and detail the conditions, the respect of which is deemed to be complying with the French regulation practice, for the subject to which they relate. Their purpose is to make known rules judged acceptable by safety authorities, thus making the safety review easier. The RFS program is described. A RFS - or a letter - can also give the result of the examination of the constructor and operator codes (RCC) by safety authorities

Development Trends in Nuclear Technology and Related Safety Aspects

International Nuclear Information System (INIS)

Kuczera, B.; Juhn, P.E.; Fukuda, K.

2002-01-01

The IAEA Safety Standards Series include, in a hierarchical manner, the categories of Safety Fundamentals, Safety Requirements and Safety Guides, which define the elements necessary to ensure the safety of nuclear installations. In the same way as nuclear technology and scientific knowledge advance continuously, also safety requirements may change with these advances. Therefore, in the framework of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) one important aspect among others refers to user requirements on the safety of innovative nuclear installations, which may come into operation within the next fifty years. In this respect, the major objectives of the INPRO sub-task 'User Requirements and Nuclear Energy Development Criteria in the Area of Safety' have been: a. to overview existing national and international requirements in the safety area, b. to define high level user requirements in the area of safety of innovative nuclear technologies, c. to compile and to analyze existing innovative reactor and fuel cycle technology enhancement concepts and approaches intended to achieve a high degree of safety, and d. to identify the general areas of safety R and D needs for the establishment of these technologies. During the discussions it became evident that the application of the defence in depth strategy will continue to be the overriding approach for achieving the general safety objective in nuclear power plants and fuel cycle facilities, where the emphasis will be shifted from mitigation of accident consequences more towards prevention of accidents. In this context, four high level user requirements have been formulated for the safety of innovative nuclear reactors and fuel cycles. On this basis safety strategies for innovative reactor designs are highlighted in each of the five levels of defence in depth and specific requirements are discussed for the individual components of the fuel cycle. (authors)

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.

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.

Nuclear Reaction Data Centers

International Nuclear Information System (INIS)

McLane, V.; Nordborg, C.; Lemmel, H.D.; Manokhin, V.N.

1988-01-01

The cooperating Nuclear Reaction Data Centers are involved in the compilation and exchange of nuclear reaction data for incident neutrons, charged particles and photons. Individual centers may also have services in other areas, e.g., evaluated data, nuclear structure and decay data, reactor physics, nuclear safety; some of this information may also be exchanged between interested centers. 20 refs., 1 tab

Development of an evaluation framework for African-European hospital patient safety partnerships.

Science.gov (United States)

Rutter, Paul; Syed, Shamsuzzoha B; Storr, Julie; Hightower, Joyce D; Bagheri-Nejad, Sepideh; Kelley, Edward; Pittet, Didier

2014-04-01

Patient safety is recognised as a significant healthcare problem worldwide, and healthcare-associated infections are an important aspect. African Partnerships for Patient Safety is a WHO programme that pairs hospitals in Africa with hospitals in Europe with the objective to work together to improve patient safety. To describe the development of an evaluation framework for hospital-to-hospital partnerships participating in the programme. The framework was structured around the programme's three core objectives: facilitate strong interhospital partnerships, improve in-hospital patient safety and spread best practices nationally. Africa-based clinicians, their European partners and experts in patient safety were closely involved in developing the evaluation framework in an iterative process. The process defined six domains of partnership strength, each with measurable subdomains. We developed a questionnaire to measure these subdomains. Participants selected six indicators of hospital patient safety improvement from a short-list of 22 based on their relevance, sensitivity to intervention and measurement feasibility. Participants proposed 20 measures of spread, which were refined into a two-part conceptual framework, and a data capture tool created. Taking a highly participatory approach that closely involved its end users, we developed an evaluation framework and tools to measure partnership strength, patient safety improvements and the spread of best practice.

Development of small reactor safety criteria in Canada

International Nuclear Information System (INIS)

Ernst, P.C.; French, P.M.; Axford, D.J.; Snell, V.G.

1990-01-01

A number of new small reactor designs have been proposed in Canada over the last several years and some have reached the stage where licensing discussions have been initiated with the Atomic Energy Control Board (AECB). An inter-organizational Small Reactor Criteria (SRC) working group was formed in 1988 to propose safety and licensing criteria for these small reactors. Two levels of criteria are proposed. The first level forms a safety philosophy and the second is a set of criteria for specific reactor applications. The safety philosophy consists of three basic safety objectives together with evaluation criteria, and fourteen fundamental principles measured by specific criteria, which must be implemented to meet the safety objectives. Two of the fourteen principles are prime: defence in depth, and safety culture; the other twelve principles can be seen as deriving from them. A benefit of this approach is that the concepts of defence in depth and safety culture become well-defined. The objectives and principles are presented in the paper and their criteria are summarized. The second level of criteria, under development, will form a safety application set and will provide small reactor criteria in a number of general areas, such as regulatory process and safety assessment, as well as for specific reactor life-cycle activities, from siting through to decommissioning. The criteria are largely deterministic. However, the frequencies and consequences of postulated accidents are assessed against numerical criteria to assist in judging the acceptability of plant design, operation, and proposed siting. All criteria proposed are designed to be testable in some evidentiary fashion, readily enabling an assessment of compliance for a given proposal

System safety engineering in the development of advanced surface transportation vehicles

Science.gov (United States)

Arnzen, H. E.

1971-01-01

Applications of system safety engineering to the development of advanced surface transportation vehicles are described. As a pertinent example, the paper describes a safety engineering efforts tailored to the particular design and test requirements of the Tracked Air Cushion Research Vehicle (TACRV). The test results obtained from this unique research vehicle provide significant design data directly applicable to the development of future tracked air cushion vehicles that will carry passengers in comfort and safety at speeds up to 300 miles per hour.

Take Effective Measures to Promote the Development of Food Safety Science

Directory of Open Access Journals (Sweden)

Zongming Li

2014-04-01

Full Text Available Food safety concerns people's health, life, even social harmony and stability. Also, it is an important scientific problem of the development of mankind. How could we strengthen our national food security? Firstly, a long-lasting scientific system of food safety should be formed. Only by enhancing the construction of this scientific system, building up the development platform of food safety, improving the science and technology level in this field, carrying out the rapid detection skills of food safety, controlling technology research, forming a joint force of government regulation and public surveillance, we could ensure food security fundamentally. Secondly, we need form a management system with strict legal liability and clear public responsibility, and need establish a food safety warning system and risk assessment system, strengthen the food information construction, improve the international standards of food quality, and constantly increase the level of food safety, so as to control the food pollution, reduce the foodborne diseases, and ensure the consumer’s health.

User-centered development of a smart phone mobile application delivering personalized real-time advice on sun protection.

Science.gov (United States)

Buller, David B; Berwick, Marianne; Shane, James; Kane, Ilima; Lantz, Kathleen; Buller, Mary Klein

2013-09-01

Smart phones are changing health communication for Americans. User-centered production of a mobile application for sun protection is reported. Focus groups (n = 16 adults) provided input on the mobile application concept. Four rounds of usability testing were conducted with 22 adults to develop the interface. An iterative programming procedure moved from a specification document to the final mobile application, named Solar Cell. Adults desired a variety of sun protection advice, identified few barriers to use and were willing to input personal data. The Solar Cell prototype was improved from round 1 (seven of 12 tasks completed) to round 2 (11 of 12 task completed) of usability testing and was interoperable across handsets and networks. The fully produced version was revised during testing. Adults rated Solar Cell as highly user friendly (mean = 5.06). The user-centered process produced a mobile application that should help many adults manage sun safety.

Aube storage center for short-lived low- and intermediate-level wastes. Annual report 2010

International Nuclear Information System (INIS)

2011-06-01

The National Radioactive Waste Management Agency (Andra), was established by the December 1991 Waste Act as a public body in charge of the long-term management of all radioactive waste, under the supervision of the Ministry of Ecology, Energy, Sustainable Development and the Sea (formerly the Ministry of Industry and the Ministry of Environment), and the Ministry of Research. The Andra operates two storage centers in the Aube region (France): the center for short-lived low- and intermediate-level wastes, and the center for very-low-level radioactive wastes. This document is the 2010 activity report of the center for short-lived low- and intermediate-level wastes. It presents a review of the activities of the center: presentation of the installations, safety and radiation protection, events or incidents, environmental monitoring, wastes management, public information, recommendations of the Health and safety Committee (CHSCT)

Structural Analysis Peer Review for the Static Display of the Orbiter Atlantis at the Kennedy Space Center Visitors Center

Science.gov (United States)

Minute, Stephen A.

2013-01-01

Mr. Christopher Miller with the Kennedy Space Center (KSC) NASA Safety & Mission Assurance (S&MA) office requested the NASA Engineering and Safety Center's (NESC) technical support on March 15, 2012, to review and make recommendations on the structural analysis being performed for the Orbiter Atlantis static display at the KSC Visitor Center. The principal focus of the assessment was to review the engineering firm's structural analysis for lifting and aligning the orbiter and its static display configuration

DEVELOPMENT OF RISK-BASED AND TECHNOLOGY-INDEPENDENT SAFETY CRITERIA FOR GENERATION IV SYSTEMS

Energy Technology Data Exchange (ETDEWEB)

William E. Kastenberg; Edward Blandford; Lance Kim

2009-03-31

This project has developed quantitative safety goals for Generation IV (Gen IV) nuclear energy systems. These safety goals are risk based and technology independent. The foundations for a new approach to risk analysis has been developed, along with a new operational definition of risk. This project has furthered the current state-of-the-art by developing quantitative safety goals for both Gen IV reactors and for the overall Gen IV nuclear fuel cycle. The risk analysis approach developed will quantify performance measures, characterize uncertainty, and address a more comprehensive view of safety as it relates to the overall system. Appropriate safety criteria are necessary to manage risk in a prudent and cost-effective manner. This study is also important for government agencies responsible for managing, reviewing, and for approving advanced reactor systems because they are charged with assuring the health and safety of the public.

DEVELOPMENT OF RISK-BASED AND TECHNOLOGY-INDEPENDENT SAFETY CRITERIA FOR GENERATION IV SYSTEMS

International Nuclear Information System (INIS)

Kastenberg, William E.; Blandford, Edward; Kim, Lance

2009-01-01

This project has developed quantitative safety goals for Generation IV (Gen IV) nuclear energy systems. These safety goals are risk based and technology independent. The foundations for a new approach to risk analysis has been developed, along with a new operational definition of risk. This project has furthered the current state-of-the-art by developing quantitative safety goals for both Gen IV reactors and for the overall Gen IV nuclear fuel cycle. The risk analysis approach developed will quantify performance measures, characterize uncertainty, and address a more comprehensive view of safety as it relates to the overall system. Appropriate safety criteria are necessary to manage risk in a prudent and cost-effective manner. This study is also important for government agencies responsible for managing, reviewing, and for approving advanced reactor systems because they are charged with assuring the health and safety of the public

The initiative of the ICES MR: Children teach their parents[International Center for Environmental Safety of Minatom of Russia (ICES MR)

Energy Technology Data Exchange (ETDEWEB)

Krupenina, Faina [International Center for Environmental Safety of Minatom of Russia, (ICES MR), 26, Staromonetny per., 109180 Moscow (Russian Federation)

2002-07-01

Air and soil pollution, increased water discharge and energy consumption, forest and plant fires are often caused by low general and ecological culture. Nuclear power has long been a main target of environmental campaigners, in Europe as well as America. The past 200 years have seemed to reinforce their case: the Chernobyl accident was compounded by fears that a similar disaster could occur in any of the antiquated graphite-cooled reactors, revelations that leaks and mishaps from Windscale/Sellafield were far worse than originally reported, campaigns against reprocessing in Germany and Japan and alarming data on nuclear hazards from sunken Russian submarines and leaking waste storage tanks. The International Center for Environmental Safety of Minatom of Russia (ICES MR) is an autonomous non-commercial organisation. The mission of the Center is to assist in environment improving and consolidation of international contacts in environmental safety, to assist in development of te positive public perception of nuclear power. We attach great significance to interaction with the public, administrations of regions and State Duma deputies. Very often a dread of radiation and protests against nuclear power development are caused by lack or insufficiency of information concerning what is radiation, how it influences a human being and nature, where is real and not made-up danger. Here it is very important to organize work with the youth. Our first experience was a Children Ecological Olympiad 'Sozvezdie'. The Olympiad was held in the Russian Cosmonauts Training Center in Zvezdny gorodok in May 2001. It has a success and showed the strong interest of schoolchildren, their parents and teachers in environmental problems, in the nuclear power as an environment friendly energy production. Together with the UNESCO department and the Youth Department of Russian Nuclear Society for youth interaction we have prepared proposals concerning establishing Youth Environmental Centers in

Occupational chemical exposures: a collaboration between the Georgia Poison Center and the Occupational Safety and Health Administration.

Science.gov (United States)

Tustin, Aaron W; Jones, Alison; Lopez, Gaylord P; Ketcham, Glenn R; Hodgson, Michael J

2018-01-01

In the United States, regional poison centers frequently receive calls about toxic workplace exposures. Most poison centers do not share call details routinely with governmental regulatory agencies. Worker health and safety could be enhanced if regulators such as the Occupational Safety and Health Administration (OSHA) had the ability to investigate these events and prevent similar incidents. With this goal in mind, the Georgia Poison Center (GPC) began referring occupational exposures to OSHA in July 2014. GPC began collecting additional employer details when handling occupational exposure calls. When workers granted permission, GPC forwarded call details to the OSHA Regional Office in Atlanta. These referrals enabled OSHA to initiate several investigations. We also analyzed all occupational exposures reported to GPC during the study period to characterize the events, detect violations of OSHA reporting requirements, and identify hazardous scenarios that could form the basis for future OSHA rulemaking or guidance. GPC was informed about 953 occupational exposures between 1 July, 2014 and 7 January, 2016. Workers were exposed to 217 unique substances, and 70.3% of victims received treatment in a healthcare facility. Hydrogen sulfide was responsible for the largest number of severe clinical effects. GPC obtained permission to refer 89 (9.3%) calls to OSHA. As a result of these referrals, OSHA conducted 39 investigations and cited 15 employers for "serious" violations. OSHA forwarded several other referrals to other regulatory agencies when OSHA did not have jurisdiction. At least one employer failed to comply with OSHA's new rule that mandates reporting of all work-related hospitalizations. This collaboration increased OSHA's awareness of dangerous job tasks including hydrofluoric acid exposure among auto detailers and carbon monoxide poisoning with indoor use of gasoline-powered tools. Collaboration with the GPC generated a useful source of referrals to OSHA. OSHA

Development of safety evaluation methods and analysis codes applied to the safety regulations for the design and construction stage of fast breeder reactor

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-08-15

The purposes of this study are to develop the safety evaluation methods and analysis codes needed in the design and construction stage of fast breeder reactor (FBR). In JFY 2012, the following results are obtained. As for the development of safety evaluation methods needed in the safety examination conducted for the reactor establishment permission, development of the analysis codes, such as core damage analysis code, were carried out following the planned schedule. As for the development of the safety evaluation method needed for the risk informed safety regulation, the quantification technique of the event tree using the Continuous Markov chain Monte Carlo method (CMMC method) were studied. (author)

Mathematical modeling of efficacy and safety for anticancer drugs clinical development.

Science.gov (United States)

Lavezzi, Silvia Maria; Borella, Elisa; Carrara, Letizia; De Nicolao, Giuseppe; Magni, Paolo; Poggesi, Italo

2018-01-01

Drug attrition in oncology clinical development is higher than in other therapeutic areas. In this context, pharmacometric modeling represents a useful tool to explore drug efficacy in earlier phases of clinical development, anticipating overall survival using quantitative model-based metrics. Furthermore, modeling approaches can be used to characterize earlier the safety and tolerability profile of drug candidates, and, thus, the risk-benefit ratio and the therapeutic index, supporting the design of optimal treatment regimens and accelerating the whole process of clinical drug development. Areas covered: Herein, the most relevant mathematical models used in clinical anticancer drug development during the last decade are described. Less recent models were considered in the review if they represent a standard for the analysis of certain types of efficacy or safety measures. Expert opinion: Several mathematical models have been proposed to predict overall survival from earlier endpoints and validate their surrogacy in demonstrating drug efficacy in place of overall survival. An increasing number of mathematical models have also been developed to describe the safety findings. Modeling has been extensively used in anticancer drug development to individualize dosing strategies based on patient characteristics, and design optimal dosing regimens balancing efficacy and safety.

Carbon Monoxide Information Center

Science.gov (United States)

... 한국어 Español ภาษาไทย Tiếng Việt Text Size: Decrease Font Increase Font Contact CPSC Consumers: Businesses: Report an Unsafe Product ... Guide View All CO Safety Guides ")); jQuery(".node-type-safety-education-center .region-sidebar-second").css('display', " ...

Development and formation of safety cultures

International Nuclear Information System (INIS)

Merry, M.W.J.; Rycraft, H.S.

1995-01-01

The Thermal Oxide Reprocessing Plant (THORP) is the largest project ever undertaken by British Nuclear Fuels plc (BNFL) and its success is important for the future of the company. The company recognised at the planning stage that to be profitable, THORP had to operate both safely and with a smaller workforce. The establishment of an appropriate culture which saw safety and productivity as essential and complimentary at the beginning of the life of the plant was therefore vital for the future success of THORP The key factors in the THORP Culture formation were : The recruitment policy; the training policy; measures taken to ensure participation from the workforce; teamworking support; communication initiatives; clear statement of cultural principles; clear and demonstrable leadership. The current stage of evolution has seen some positive results namely: A clear commitment to involving all personnel in problem solving and task organisation, including safety; a confident workforce with an improved ability to communicate; the capability of the majority of the workforce to work as a team; safety awareness of the workforce is generally high along with an awareness of environmental, commercial and (political) external issues affecting the THORP business; a commitment to continuous improvement. The development of the safety culture within THORP has also had challenges, some as a result of the composite nature of the workforce, and others as side effects of the culture shaping measures. Management have recognised these, and using the results of attitude surveys, are working with the workforce to overcome their effects. Clear recognition has been achieved that the establishment of positive behaviours is a key. step in generating the culture required summarising, there is recognition that the design of safety management systems and improvement programmes, should be based on the principles of human psychology and behaviour. which includes wide participation by the workforce

Implementation of Information Management System for Radiation Safety of Personnel at the Russian Northwest Center for Radioactive Waste Management 'SevRAO' - 13131

Energy Technology Data Exchange (ETDEWEB)

Chizhov, K.; Simakov, A.; Seregin, V.; Kudrin, I.; Shandala, N.; Tsovyanov, A.; Kryuchkov, V. [Burnasyan Federal Medical Biophysical Center of Federal Medical Biological Agency, RF Ministry of Health and Social Development. 46, Zhivopisnaya St., Moscow, 123182 (Russian Federation); Krasnoschekov, A.; Kosnikov, A. [Northwest Center for Radioactive Waste Management ' SevRAO' - a branch of the Federal State Unitary Enterprise ' Enterprise for Radioactive Waste Management' ' RosRAO' 183017, Murmansk, Lobova st., 100 (Russian Federation); Kemsky, I. [Regional management - 120 of the Federal Medical-Biological Agency, 184682, Snezhnogorsk, Valentina Biryukova St., 5/1 (Russian Federation); Sneve, M. [Norwegian Radiation Protection Authority, Postboks 55, 1332 Oesteraas (Norway)

2013-07-01

The report is an overview of the information-analytical system designed to assure radiation safety of workers. The system was implemented in the Northwest Radioactive Waste Management Center 'SevRAO' (which is a branch of the Federal State Unitary Enterprise 'Radioactive Waste Management Enterprise RosRAO'). The center is located in the Northwest Russia. In respect to 'SevRAO', the Federal Medical-Biological Agency is the regulatory body, which deals with issues of radiation control. The main document to regulate radiation control is 'Reference levels of radiation factors in radioactive wastes management center'. This document contains about 250 parameters. We have developed a software tool to simplify control of these parameters. The software includes: input interface, the database, dose calculating module and analytical block. Input interface is used to enter radiation environment data. Dose calculating module calculates the dose on the route. Analytical block optimizes and analyzes radiation situation maps. Much attention is paid to the GUI and graphical representation of results. The operator can enter the route at the industrial site or watch the fluctuations of the dose rate field on the map. Most of the results are presented in a visual form. Here we present some analytical tasks, such as comparison of the dose rate in some point with control levels at this point, to be solved for the purpose of radiation safety control. The program helps to identify points making the largest contribution to the collective dose of the personnel. The tool can automatically calculate the route with the lowest dose, compare and choose the best route. The program uses several options to visualize the radiation environment at the industrial site. This system will be useful for radiation monitoring services during the operation, planning of works and development of scenarios. The paper presents some applications of this system on real data

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

International Nuclear Information System (INIS)

González, F.; Villadóniga, J. I.

2016-01-01

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

The impact of nursing leadership on patient safety in a developing country.

Science.gov (United States)

Stewart, Lee; Usher, Kim

2010-11-01

This article is a report of a study to identify the ways nursing leaders and managers in a developing country have an impact on patient safety. The attempt to address the problem of patient safety in health care is a global issue. Literature addressing the significant impact that nursing leadership has on patient safety is extensive and focuses almost exclusively on the developed world. A critical ethnography was conducted with senior registered nursing leaders and managers throughout the Fiji Islands, specifically those in the Head Office of the Fiji Ministry of Health and the most senior nurse in a hospital or community health service. Semi-structured interviews were conducted with senior nursing leaders and managers in Fiji. Thematic analysis of the interviews was undertaken from a critical theory perspective, with reference to the macro socio-political system of the Fiji Ministry of Health. Four interrelated issues regarding the nursing leaders and managers' impact on patient safety emerged from the study. Empowerment of nursing leaders and managers, an increased focus on the patient, the necessity to explore conditions for front-line nurses and the direct relationship between improved nursing conditions and increased patient safety mirrored literature from developed countries. The findings have significant implications for developing countries and it is crucial that support for patient safety in developing countries become a focus for the international nursing community. Nursing leaders and managers' increased focus on their own place in the hierarchy of the health care system and on nursing conditions as these affect patient safety could decrease adverse patient outcomes. The findings could assist the global nursing community to better support developing countries in pursuing a patient safety agenda. © 2010 Blackwell Publishing Ltd.

Integrated risk management of safety and development on transportation corridors

International Nuclear Information System (INIS)

Thekdi, Shital A.; Lambert, James H.

2015-01-01

Prioritization of investments to protect safety and performance of multi-regional transportation networks from adjacent land development is a key concern for infrastructure agencies, land developers, and other stakeholders. Despite ample literature describing relationships between transportation and land use, no evidence-based methods exist for monitoring corridor needs on a large scale. Risk analysis is essential to the preservation of system safety and capacity, including avoidance of costly retrofits, regret, and belated action. This paper introduces the Corridor Trace Analysis (CTA) for prioritizing corridor segments that are vulnerable to adjacent land development. The method integrates several components: (i) estimation of likelihood of adjacent land development, using influence diagram and rule-based modeling, (ii) characterization of access point density using geospatial methods, and (iii) plural-model evaluation of corridors, monitoring indices of land development likelihood, access point densities, and traffic volumes. The results inform deployment of options that include closing access points, restricting development, and negotiation of agencies and developers. The CTA method is demonstrated on a region encompassing 6000 centerline miles (about 10,000 km) of transportation corridors. The method will be of interest to managers investing in safety and performance of infrastructure systems, balancing safety, financial, and other criteria of concern for diverse stakeholders. - Highlights: • The Corridor Trace Analysis (CTA) method for prioritizing transportation corridors. • The CTA method studies corridors vulnerable to adjacent land development. • The CTA method quantifies the influence of risk scenarios on agency priorities. • The CTA method is demonstrated on 6000 miles of critical transportation corridor

Proceedings of the First Seminar on Radiation Safety Technology and Nuclear Biomedicine

International Nuclear Information System (INIS)

Suprihadi, Topo

2003-01-01

The First Seminar on Radiation Safety Technology and Nuclear Biomedicine was held on 10-11 April 2001 at the Center for Research and Development of Radiation Safety and Nuclear Biomedicine have presented 19 papers about upgrading manpower resources, researcher, investigator, manager, and user of nuclear facilities, to go out against free market era

Developing patient safety in dentistry.

Science.gov (United States)

Pemberton, M N

2014-10-01

Patient safety has always been important and is a source of public concern. Recent high profile scandals and subsequent reports, such as the Francis report into the failings at Mid Staffordshire, have raised those concerns even higher. Mortality and significant morbidity associated with the practice of medicine has led to many strategies to help improve patient safety, however, with its lack of associated mortality and lower associated morbidity, dentistry has been slower at systematically considering how patient safety can be improved. Recently, several organisations, researchers and clinicians have discussed the need for a patient safety culture in dentistry. Strategies are available to help improve patient safety in healthcare and deserve further consideration in dentistry.

Development of XML Schema for Broadband Digital Seismograms and Data Center Portal

Science.gov (United States)

Takeuchi, N.; Tsuboi, S.; Ishihara, Y.; Nagao, H.; Yamagishi, Y.; Watanabe, T.; Yanaka, H.; Yamaji, H.

2008-12-01

There are a number of data centers around the globe, where the digital broadband seismograms are opened to researchers. Those centers use their own user interfaces and there are no standard to access and retrieve seismograms from different data centers using unified interface. One of the emergent technologies to realize unified user interface for different data centers is the concept of WebService and WebService portal. Here we have developed a prototype of data center portal for digital broadband seismograms. This WebService portal uses WSDL (Web Services Description Language) to accommodate differences among the different data centers. By using the WSDL, alteration and addition of data center user interfaces can be easily managed. This portal, called NINJA Portal, assumes three WebServices: (1) database Query service, (2) Seismic event data request service, and (3) Seismic continuous data request service. Current system supports both station search of database Query service and seismic continuous data request service. Data centers supported by this NINJA portal will be OHP data center in ERI and Pacific21 data center in IFREE/JAMSTEC in the beginning. We have developed metadata standard for seismological data based on QuakeML for parametric data, which has been developed by ETH Zurich, and XML-SEED for waveform data, which was developed by IFREE/JAMSTEC. The prototype of NINJA portal is now released through IFREE web page (http://www.jamstec.go.jp/pacific21/).

Agility in Development of Safety-Critical Software: A Conceptual Model

DEFF Research Database (Denmark)

Tordrup Heeager, Lise; Nielsen, Peter Axel

2018-01-01

Safety-critical information systems are being used increasingly as we see applications in new areas such as personal medical devices, traffic control and detection of pathogens. A current research debate is whether safety-critical systems must be developed with traditional waterfall processes...

Development of Manitoba Hydro's public water safety around dams management guidelines

Energy Technology Data Exchange (ETDEWEB)

Bonin, Dave; McPhail, Gord; Murphy, Shayla; Schellenberg, Gord [KGS Acres, Winnipeg, (Canada); Read, Nick [Manitoba Hydro, Winnipeg, (Canada)

2010-07-01

Several drowning fatalities and safety incidents have occurred around dams in Ontario, Manitoba and other jurisdictions in Canada. Following these incidents, Manitoba Hydro implemented several measures to improve public safety around its dams with the development of a warning signs manual. Manitoba Hydro found that a standard centralized approach to the process of improving public safety is better for ensuring compliance and consistency, even though they have safety measures in place. This paper described the process that Manitoba Hydro has followed in developing a formal set of public water safety around dams (PWSD) guidelines and a program for implementing these guidelines. This program was developed with the intent of providing a high standard of public protection and continuous improvement and monitoring on par with the effect spent on similar dam safety type programs. This paper focused on the development of the pilot PWSD management plan for Pine Falls generating station in order to test the effectiveness and usability of the guidelines.

Contemporary Approaches to Safety Culture: Lessons from Developing a Regulatory Oversight Approach

International Nuclear Information System (INIS)

Goebel, V.; Heppell-Masys, K.

2016-01-01

The Canadian Nuclear Safety Commission (CNSC) regulates the use of nuclear energy and materials to protect health, safety, security and the environment, and to implement Canada’s international commitments on the peaceful use of nuclear energy; and to disseminate objective scientific, technical and regulatory information to the public. In the late 1990s, the CNSC conducted research into an Organization and Management (O&M) assessment method. Based on this research the CNSC conducted O&M assessments at all Canadian nuclear power plants and conducted additional assessments of nuclear research and uranium mine and mill operations. The results of these assessments were presented to licencees and used to inform their ongoing actions related to safety culture. Additional safety culture outreach and oversight activities provided licencees with opportunities to develop effective safety culture assessment methods, to share best practices across industry, and to strive for continual improvement of their organizations. Recent changes to the Canadian Standards Association (CSA) management system standard have resulted in the inclusion of requirements associated to safety culture and human performance. Representatives from several sectors of Canada’s nuclear industry, as well as participation from regulators such as the CNSC took part to the development of this consensus standard. Specifically, these requirements focus on monitoring and understanding safety culture, integrating safety into all of the requirements of the management system, committing workers to adhere to the management system and supporting excellence in workers’ performance. The CNSC is currently developing a regulatory document on safety culture which includes key concepts applicable to all licencees and specific requirements related to self-assessment, and additional guidance for nuclear power plants. Developing a regulatory document on safety culture requires consultation and fact finding initiatives at

10CFR50.59 safety evaluation training and expert system development

International Nuclear Information System (INIS)

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

1988-01-01

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

Center Planning and Development Student Engineer at KSC

Science.gov (United States)

Jenkins, Kenneth T., Jr.

2015-01-01

This summer I was the Student Trainee (Engineering) Pathways Intern (co-op) at the Kennedy Space Center (KSC) in the Center Planning & Development (CPD) Directorate. CPD works with commercial companies who are interested in using KSC's unique capabilities for spaceflight, spacecraft processing, ground systems and Research & Development (R&D) projects that fall in line with NASA's Mission and Vision. CPD is divided into three (3) groups: (1) AD-A, which works on the Master Planning for the center, (2) AD-B (where I am), which works on project control, management and integration, and (3) AD-C, which works on partnership development. CPD's main goal is to make KSC the world's preeminent multi-user spaceport and maintain the center as a leader in space exploration. CPD is a very diverse group of employees having a wide knowledge of not only the Space Shuttle, but also Expendable Launch Vehicles (ELV). The director of CPD, Scott Colloredo, is on the advisory board for Commercial Space Operations (CSO) and has a degree from ERAU. I worked on a number of different tasks for AD-B, as well as CPD, that includes, but not limited to: reviewing and reissuing engineering documents, weekly notes for CPD and senior management, engineering familiarizations with facilities at KSC, leading a tour for the Embry-Riddle Aeronautical University Career Services office, and working on actual agreements/proposals that will be used in the partnership process with multiple partners, along with other projects. Most of the work I have done is sensitive information and cannot be disclosed.

Annual report of Technical Development Division of the Tono Geoscience Center, PNC in 1996 fiscal year

International Nuclear Information System (INIS)

1997-04-01

This is a report collected working results of research and development conducted at Technical Development Division of the Tono Geoscience Center, PNC (Power Reactor and Nuclear Fuel Development Corporation) in 1996 fiscal year. In this fiscal year, Ore Bed Analysis and Evaluation Group entered into this division by changing name of Resource Analysis and Evaluation Group, which was shared to conduct some actions such as survey of resource information, analysis of potential, evaluation of ore bed, and so forth. The other conducted works were same as those in last fiscal year. Beside them, as taking the Monju reactor accident on December 8, 1995 an opportunity, safety management of facility was reconsidered as the most important item, preparation of the mining facilities such as renewal of lifting winder in vertical road for survey, new construction of general management building, preparation around the precipitation pond, and so on were executed, as a response to normal work for the yearly elapsed change in the Tono Mine. (G.K.)

Safety of High Speed Ground Transportation Systems : Analytical Methodology for Safety Validation of Computer Controlled Subsystems : Volume 2. Development of a Safety Validation Methodology

Science.gov (United States)

1995-01-01

This report describes the development of a methodology designed to assure that a sufficiently high level of safety is achieved and maintained in computer-based systems which perform safety cortical functions in high-speed rail or magnetic levitation ...

KCC1: First Nanoparticle developed by KAUST Catalysis Center

KAUST Repository

Basset, Jean-Marie

2010-08-01

KCC1 is the first Nanoparticle developed by KAUST Catalysis Center. Director of KAUST Catalysis Center, Dr. Jean-Marie Basset, Senior Research Scientist at KCC, Dr. Vivek Polshettiwar, and Dr. Dongkyu Cha of the Advanced Nanofabrication Imaging & Characterization Core Laboratory discuss the details of this recent discovery. This video was produced by KAUST Visualization Laboratory and KAUST Technology Transfer and Innovation - Terence McElwee, Director, Technology Transfer and Innovation - IP@kaust.edu.sa This technology is part of KAUST\\'s technology commercialization program that seeks to stimulate development and commercial use of KAUST-developed technologies. For more information email us at ip@kaust.edu.sa.

Cultivating and Development — 30 Years Practice of Safety Culture in China

International Nuclear Information System (INIS)

Hu, L.; Zhang, Y.; Zhang, W.; Xu, G.

2016-01-01

The safety culture has been cultivated and promoted in China since its very beginning by IAEA. The 1st stage—stage of start and exploration—was from 1984 to 2007, in which the international concept of safety culture was imported and studied, with the process of combination and convergence with the positive elements of Chinese traditional culture. The basic ideas, such as the principles and directing ideas for the nuclear safety, were established in China. The 2nd stage — stage of practice and growing — was from 2007 to 2014, where safety culture was promoted by the Government, and the regulatory body NNSA established its basic supervision value based on the safety culture. The Chinese nuclear industry was encouraged to develop their of safety culture in a vivid form of presenting. The 3rd stage — stage of fast development — is from 2014 to now. The Chinese president Xi announce the Chinese Nuclear Safety View in The Hague in March 2014, showing the states position regarding the nuclear safety and safety culture. The policy declaration was issued and the nuclear safety promotion special action was carried out by NNSA. Safety culture is widely accepted and acknowledged by the nuclear and radioactivity relevant industry. (author)

Progress in the development of methodology for fusion safety systems studies

International Nuclear Information System (INIS)

Ho, S.K.; Cambi, G.; Ciattaglia, S.; Fujii-e, Y.; Seki, Y.

1994-01-01

The development of fusion safety systems-study methodology, including the aspects of schematic classification of overall fusion safety system, qualitative assessment of fusion system for identification of critical accident scenarios, quantitative analysis of accident consequences and risk for safety design evaluation, and system-level analysis of accident consequences and risk for design optimization, by a consortium of international efforts is presented. The potential application of this methodology into reactor design studies will facilitate the systematic assessment of safety performance of reactor designs and enhance the impacts of safety considerations on the selection of design configurations

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

Science.gov (United States)

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

2007-10-01

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

Progress of nuclear safety research. 2002

Energy Technology Data Exchange (ETDEWEB)

Anoda, Yoshinari; Kudo, Tamotsu; Tobita, Tohru (eds.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment] (and others)

2002-11-01

JAERI is conducting nuclear safety research primarily at the Nuclear Safety Research Center in close cooperation with the related departments in accordance with the Long Term Plan for Development and Utilization of Nuclear Energy and Annual Plan for Safety Research issued by the Japanese government. The fields of conducting safety research at JAERI are the engineering safety of nuclear power plants and nuclear fuel cycle facilities, and radioactive waste management as well as advanced technology for safety improvement or assessment. Also, JAERI has conducted international collaboration to share the information on common global issues of nuclear safety and to supplement own research. Moreover, when accidents occurred at nuclear facilities, JAERI has taken a responsible role by providing technical experts and investigation for assistance to the government or local public body. This report summarizes the nuclear safety research activities of JAERI from April 2000 through April 2002 and utilized facilities. This report also summarizes the examination of the ruptured pipe performed for assistance to the Nuclear and Industrial Safety Agency (NISA) for investigation of the accident at the Hamaoka Nuclear Power Station Unit-1 on November, 2001. (author)

Progress of nuclear safety research - 2005

International Nuclear Information System (INIS)

Anoda, Yoshinari; Amaya, Masaki; Saito, Junichi; Sato, Atsushi; Sono, Hiroki; Tamaki, Hitoshi; Tonoike, Kotaro; Nemoto, Yoshiyuki; Motoki, Yasuo; Moriyama, Kiyofumi; Yamaguchi, Tetsuji; Araya, Fumimasa

2006-03-01

The Japan Atomic Energy Research Institute (JAERI), one of the predecessors of the Japan Atomic Energy Agency (JAEA), had conducted nuclear safety research primarily at the Nuclear Safety Research Center in close cooperation with the related departments in accordance with the Long Term Plan for Development and Utilization of Nuclear Energy and Five-Years Program for Safety Research issued by the Japanese government. The fields of conducting safety research at JAERI were the engineering safety of nuclear power plants and nuclear fuel cycle facilities, and radioactive waste management as well as advanced technology for safety improvement or assessment. Also, JAERI had conducted international collaboration to share the information on common global issues of nuclear safety and to supplement own research. Moreover, when accidents occurred at nuclear facilities, JAERI had taken a responsible role by providing experts in assistance to conducting accident investigations or emergency responses by the government or local government. These nuclear safety research and technical assistance to the government have been taken over as an important role by JAEA. This report summarizes the nuclear safety research activities of JAERI from April 2003 through September 2005 and utilized facilities. (author)

Calculating the cost of research and Development in nuclear and radiation safety

International Nuclear Information System (INIS)

Matsulevich, N.Je.; Nosovs'ka, A.A.

2010-01-01

Methodological support assessing the cost of research and development in the area of nuclear and radiation safety regulation is considered. Basic methodological recommendations for determining labor expenditures for research and development in nuclear and radiation safety are provided.

Scenario Development Workshop Synopsis. Integration Group for the Safety Case - June 2015

International Nuclear Information System (INIS)

Smith, Paul; Voinis, Sylvie; Griffault, Lise; De Meredieu, Jean; Kwong, Gloria; ); Van Luik, Abraham; Bailey, Lucy; Capouet, Manuel; Depaus, Christophe; Makino, Hitoshi; Leigh, Christi; Kirkes, Ross; Leino, Jaakko; Niemeyer, Matthias; Wolf, Jens; Watson, Sarah; Franke, Bettina; Ilett, Doug; Pastina, Barbara; Weetjens, Eef

2016-03-01

Scenario development and selection describes the collection and organisation of the scientific and technical information relevant to the potential paths of evolution of a radioactive waste disposal facility (repository) that is necessary to assess its long-term performance and safety. In 1999, the NEA held its first workshop on scenario development in Madrid, Spain, with the objective to review the methods for developing scenarios in safety assessments and their application. Since then, the process of scenario development and analysis for the disposal of radioactive waste has changed and, in 2015, the NEA Integration Group for the Safety Case (IGSC) held a second workshop on this topic at its offices in Paris to further evaluate the experience acquired in developing scenarios since 1999. To prepare for this workshop, the IGSC also launched a survey in 2014 to gather the latest scenario development and uncertainty management strategies used in IGSC member countries. The purposes of the workshop were to (i) provide a forum to review and discuss methods for scenario development and their contribution to the development of recent safety cases (since the 1999 workshop); (ii) examine the latest methods and compare their scope, consistency and function within the overall safety assessment process, based on practical experience of applications; and (iii) provide a basis for producing the present report summarising the current status of scenario methodologies, identifying where sufficient methods exist and any outstanding problem areas. This report provides an overview of the state of the art in scenario development related to the long-term safety of geological repositories for radioactive waste. In particular, it discusses how potential scenarios are developed in safety assessments of radioactive waste that contains long-lived radionuclides. Safety assessment is the process of quantitatively and qualitatively evaluating the safety of a repository, often in support of a

NASA-Langley Research Center's Aircraft Condition Analysis and Management System Implementation

Science.gov (United States)

Frye, Mark W.; Bailey, Roger M.; Jessup, Artie D.

2004-01-01

This document describes the hardware implementation design and architecture of Aeronautical Radio Incorporated (ARINC)'s Aircraft Condition Analysis and Management System (ACAMS), which was developed at NASA-Langley Research Center (LaRC) for use in its Airborne Research Integrated Experiments System (ARIES) Laboratory. This activity is part of NASA's Aviation Safety Program (AvSP), the Single Aircraft Accident Prevention (SAAP) project to develop safety-enabling technologies for aircraft and airborne systems. The fundamental intent of these technologies is to allow timely intervention or remediation to improve unsafe conditions before they become life threatening.

Report of transparency and nuclear safety 2007 CEA Fontenay aux Roses

International Nuclear Information System (INIS)

2007-01-01

This report presents the activities of the CEA Center of Fontenay aux roses for the year 2007. After many years of decommissioning and dismantling of nuclear installations, the Center is now devoted (since 2005) to the development of research programmes on biology and biomedical technologies. The actions concerning the safety, the radiation protection, the significant events, the release control and the environmental impacts and the wastes stored on the center are discussed. (A.L.B.)

Development and initial validation of an Aviation Safety Climate Scale.

Science.gov (United States)

Evans, Bronwyn; Glendon, A Ian; Creed, Peter A

2007-01-01

A need was identified for a consistent set of safety climate factors to provide a basis for aviation industry benchmarking. Six broad safety climate themes were identified from the literature and consultations with industry safety experts. Items representing each of the themes were prepared and administered to 940 Australian commercial pilots. Data from half of the sample (N=468) were used in an exploratory factor analysis that produced a 3-factor model of Management commitment and communication, Safety training and equipment, and Maintenance. A confirmatory factor analysis on the remaining half of the sample showed the 3-factor model to be an adequate fit to the data. The results of this study have produced a scale of safety climate for aviation that is both reliable and valid. This study developed a tool to assess the level of perceived safety climate, specifically of pilots, but may also, with minor modifications, be used to assess other groups' perceptions of safety climate.

Carbon Monoxide Information Center

Medline Plus

Full Text Available ... 한국어 Español ภาษาไทย Tiếng Việt Text Size: Decrease Font Increase Font Contact CPSC Consumers: Businesses: Report an Unsafe Product ... Guide View All CO Safety Guides ")); jQuery(".node-type-safety-education-center .region-sidebar-second").css('display', " ...

Developing guidance in the nuclear criticality safety assessment for fuel cycle facilities

International Nuclear Information System (INIS)

Galet, C.; Evo, S.

2012-01-01

In this poster IRSN (Institute for radiation protection and nuclear safety) presents its safety guides whose purpose is to transmit the safety assessment know-how to any 'junior' staff or even to give a view of the safety approach on the overall risks to any staff member. IRSN has written a first version of such a safety guide for fuel cycle facilities and laboratories. It is organized into several chapters: some refer to types of assessments, others concern the types of risks. Currently, this guide contains 13 chapters and each chapter consists of three parts. In parallel to the development of criticality chapter of this guide, the IRSN criticality department has developed a nuclear criticality safety guide. It follows the structure of the three parts fore-mentioned, but it presents a more detailed first part and integrates, in the third part, the experience feedback collected on nuclear facilities. The nuclear criticality safety guide is online on the IRSN's web site

Activity of safety review for the facilities using nuclear material (2). Safety review results and maintenance experiences for hot laboratories

International Nuclear Information System (INIS)

Amagai, Tomio; Fujishima, Tadatsune; Mizukoshi, Yasutaka; Sakamoto, Naoki; Ohmori, Tsuyoshi

2009-01-01

In the site of O-arai Research and Development Center of Japan Atomic Energy Agency (JAEA), five hot laboratories for post-irradiation examination and development of plutonium fuels are operated more than 30 years. A safety review method for preventive maintenance on these hot laboratories includes test facilities and devices are established in 2003. After that, the safety review of these facilities and devices are done and taken the necessary maintenance based on the results in each year. In 2008, 372 test facilities and devices in these hot laboratories were checked and reviewed by this method. As a results of the safety review, repair issues of 38 facilities of above 372 facilities were resolved. This report shows the review results and maintenance experiences based on the results. (author)

The critical issue of nuclear power plant safety in developing countries

International Nuclear Information System (INIS)

Rosen, M.

1977-01-01

A little more than a decade from now, large commercial nuclear power facilities will be in operation in almost 40 countries, of which approximately one-half are presently considered industrially less developed. Ambitious nuclear programmes coupled with minimal and frequently under-staffed regulatory and utility organizations are only one aspect of the difficulties related to the safety of nuclear plants that face these developing countries. Inherent problems of meeting current safety standards and requirements for the significantly non-standard nuclear power plant exports can be compounded by financial considerations that may lead to purchases of reactors of various types, from more than one supplier country and with different safety standards and requirements. An examination of these issues points to the necessity and opportunity for effective action which could include provision for adequate funding for safety considerations in the purchase contract, and for sufficient regulatory assistance and training from the developed countries. The article will introduce the topic, discuss specific examples, and offer some suggestions. (author)

Development of the reactor safety film

International Nuclear Information System (INIS)

Sheheen, N.N.; Hodson, P.J.

1981-01-01

The first computer-generated film of LASL's Reactor Safety efforts was developed using the ANIMATE framework, a program that adds visual capabilities to MAPPER. Numerous software limitations had to be overcome within a very limited production schedule. A significant achievement was the 15,000-vector-per-frame sequence depicting a pressurized water reactor core with parts flashing while pumps circulate fluid through the system

The Dynamics of Agile Practices for Safety-Critical Software Development

DEFF Research Database (Denmark)

Nielsen, Peter Axel; Tordrup Heeager, Lise

2017-01-01

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

Safety analysis of the proposed Canadian geologic nuclear waste repository

International Nuclear Information System (INIS)

Prowse, D.R.

1977-01-01

The Canadian program for development and qualification of a geologic repository for emplacement of high-level and long-lived, alpha-emitting waste from irradiated nuclear fuel has been inititiated and is in its initial development stage. Fieldwork programs to locate candidate sites with suitable geological characteristics have begun. Laboratory studies and development of models for use in safety analysis of the emplaced nuclear waste have been initiated. The immediate objective is to complete a simplified safety analysis of a model geologic repository by mid-1978. This analysis will be progressively updated and will form part of an environmental Assessment Report of a Model Fuel Center which will be issued in mid-1979. The long-term objectives are to develop advanced safety assessment models of a geologic repository which will be available by 1980

Perspective on Secure Development Activities and Features of Safety I and C Systems

International Nuclear Information System (INIS)

Kang, Youngdoo; Yu, Yeong Jin; Kim, Hyungtae; Kwon, Yong il; Park, Yeunsoo; Choo, Jaeyul; Son, Jun Young; Jeong, Choong Heui

2015-01-01

The Enforcement Decree of the Act on Physical Protection and Radiological Emergency (ED-APPRE) was revised December 2013 to include security requirements on computer systems at nuclear facilities to protect those systems against malicious cyber-attacks. It means Cyber-Security-related measures, controls and activities of safety I and C systems against cyber-attacks shall meet the requirements of ED-APPRE. Still regulation upon inadvertent access or non-malicious modifications to the safety I and C systems is covered under the Nuclear Safety Act. The objective of this paper is to propose KINS' regulatory perspective on secure development and features against non-malicious access or modification of safety I and C systems. Secure development activities and features aim to prevent inadvertent and non-malicious access, and to prevent unwanted action from personnel or connected systems for ensuring reliable operation of safety I and C systems. Secure development activities of safety I and C systems are life cycle activities to ensure unwanted, unneeded and undocumented code is not incorporated into the systems. Secure features shall be developed, verified and qualified throughout the development life cycle

Perspective on Secure Development Activities and Features of Safety I and C Systems

Energy Technology Data Exchange (ETDEWEB)

Kang, Youngdoo; Yu, Yeong Jin; Kim, Hyungtae; Kwon, Yong il; Park, Yeunsoo; Choo, Jaeyul; Son, Jun Young; Jeong, Choong Heui [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2015-05-15

The Enforcement Decree of the Act on Physical Protection and Radiological Emergency (ED-APPRE) was revised December 2013 to include security requirements on computer systems at nuclear facilities to protect those systems against malicious cyber-attacks. It means Cyber-Security-related measures, controls and activities of safety I and C systems against cyber-attacks shall meet the requirements of ED-APPRE. Still regulation upon inadvertent access or non-malicious modifications to the safety I and C systems is covered under the Nuclear Safety Act. The objective of this paper is to propose KINS' regulatory perspective on secure development and features against non-malicious access or modification of safety I and C systems. Secure development activities and features aim to prevent inadvertent and non-malicious access, and to prevent unwanted action from personnel or connected systems for ensuring reliable operation of safety I and C systems. Secure development activities of safety I and C systems are life cycle activities to ensure unwanted, unneeded and undocumented code is not incorporated into the systems. Secure features shall be developed, verified and qualified throughout the development life cycle.

78 FR 40743 - Mine Safety and Health Research Advisory Committee, National Institute for Occupational Safety...

Science.gov (United States)

2013-07-08

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Mine Safety and Health Research Advisory Committee, National Institute for Occupational Safety and Health (MSHRAC, NIOSH... Director, NIOSH, on priorities in mine safety and health research, including grants and contracts for such...

Lessons learned - development of the tritium facilities 5480.23 safety analysis report and technical safety requirements

International Nuclear Information System (INIS)

Cappucci, A.J. Jr.; Bowman, M.E.; Goff, L.

1997-01-01

A review was performed which identified open-quotes Lessons Learnedclose quotes from the development of the 5480.23 Tritium Safety Analysis Report (SAR) and the Technical Safety Requirements (TSR) for the Tritium Facilities (TF). The open-quotes Lessons Learnedclose quotes were based on an evaluation of the use of the SRS procedures, processes, and work practices which contributed to the success or lack thereof. This review also identified recommendations and suggestions for improving the development of SARs and TSRs at SRS. The 5480.23 SAR describes the site for the TF, the various process systems in the process buildings, a complete hazards and accident analysis of the most significant hazards affecting the nearby offsite population, and the selection of safety systems, structures, and components to protect both the public and site workers. It also provides descriptions of important programs and processes which add defense in depth to public and worker protection

Development of a British Road Safety Education Support Materials Curriculum.

Science.gov (United States)

Bouck, Linda H.

Road safety education needs to be a vital component in the school curriculum. This paper describes a planned road safety education support materials curriculum developed to aid educators in the Wiltshire County (England) primary schools. Teaching strategies include topic webs, lecture, class discussion, group activities, and investigative learning…

Development of Safety Grade PLC (POSAFE-Q) and Performance Test Results

International Nuclear Information System (INIS)

Kim, Chang Hwoi; Park, Won Man; Choi, Jong Gyun; Lee, Dong Young; No, Young Hun; Song, Seung Hwan

2006-01-01

The safety grade PLC (POSAFE-Q) is being developed in the Korea Nuclear Instrumentation and Control System (KNICS) R and D project. The PLC satisfies Safety Class 1E, Quality Class 1, and Seismic Category I. The software such as the RTOS and firmware are being developed according to the safety critical software life cycle. Especially, the formal method is applied to design the SRS (Software Requirement Spec.) and the SDS (Software Design Specification.) to be error-free. The POSAFE-Q has several modules such as processor module, input and output modules, communication modules, redundant processor module, redundant power modules, etc,. To verify the function and performance, several tests such as CT, IT and ST were performed. And also, the equipment qualification test for environment, EMI and EMC, and seismic ware performed. All tests are satisfied with the requirements and specification for safety grade PLC, and the criteria for safety system in nuclear power plants

Development of Safety Grade PLC (POSAFE-Q) and Performance Test Results

Energy Technology Data Exchange (ETDEWEB)

Kim, Chang Hwoi; Park, Won Man; Choi, Jong Gyun; Lee, Dong Young [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of); No, Young Hun; Song, Seung Hwan [POSCON, Seoul (Korea, Republic of)

2006-07-01

The safety grade PLC (POSAFE-Q) is being developed in the Korea Nuclear Instrumentation and Control System (KNICS) R and D project. The PLC satisfies Safety Class 1E, Quality Class 1, and Seismic Category I. The software such as the RTOS and firmware are being developed according to the safety critical software life cycle. Especially, the formal method is applied to design the SRS (Software Requirement Spec.) and the SDS (Software Design Specification.) to be error-free. The POSAFE-Q has several modules such as processor module, input and output modules, communication modules, redundant processor module, redundant power modules, etc,. To verify the function and performance, several tests such as CT, IT and ST were performed. And also, the equipment qualification test for environment, EMI and EMC, and seismic ware performed. All tests are satisfied with the requirements and specification for safety grade PLC, and the criteria for safety system in nuclear power plants.

White paper on nuclear safety in 1981

International Nuclear Information System (INIS)

1981-01-01

The measures to research, develop and utilize atomic energy in Japan have been strengthened since the Atomic Energy Act was instituted in 1955, always on the major premise of securing the safety. The Nuclear Safety Commission established in October, 1978, has executed various measures to protect the health and safety of the nation as the center of the atomic energy safety regulation administration in Japan. Now, the Nuclear Safety Commission has published this annual report on atomic energy safety, summarizing various activities for securing the safety of atomic energy since its establishment to the end of March, 1981. This report is the inaugural issue, and the course till the Nuclear Safety Commission has made its start is also described. The report is composed of general remarks, response to the TMI accident, the safety regulation and security of nuclear facilities, the treatment and disposal of radioactive wastes, the investigation of environmental radioactivity, the countermeasures for preventing disasters around nuclear power stations and others, the research on the safety of atomic energy, international cooperation, and the improvement of the basis for securing the safety. Various related materials are attached. (Kako, I.)

Analysis of international approaches which are used at development of theoperational safety performance indicators

International Nuclear Information System (INIS)

Lyigots'kij, O.Yi.; Nosovs'kij, A.V.; Chemeris, Yi.O.

2009-01-01

Description of international approaches and experience of the use of theoperational safety performance indicators system is provided for estimationof current status and making a decision on corrections in the operationpractice. The state of development of the operational safety performanceindicators system by the operating organization is overviewed. Thepossibility of application of international approaches during development ofthe integral safety performance indicators system is analyzed. Aims and tasksof future researches are formulated in relation to development of theintegral safety performance indicators system.

Development of a Safety Management Web Tool for Horse Stables.

Science.gov (United States)

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

2015-11-12

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

Radiation Protection and Safety Department - annual report 1977

International Nuclear Information System (INIS)

Kiefer, H.; Koelzer, W.

1978-03-01

The duties cover tasks relative to radiation protection and safety on behalf of the institutes and departments of Kernforschungszentrum Karlsruhe and environmental monitoring for the whole Nuclear Research Center as well as own research and development work, mainly performed under the Nuclear Research Center and the Nuclear Safeguards Project. The centers of interest of R and D activities were: investigation of the atmospheric diffusion in the micro- and meso-scale, study of the radiological consequences of accidents in reactors under probabilistic aspects, implementation of nuclear fuel safeguarding systems, improvements in radiation protection measurement technology. This report gives details of the different duties, indicates the results of 1977 routine measurements, and reports about new results of investigations and developments of the working groups of the department. (orig.) [de

Modeling the Relationship between Safety Climate and Safety Performance in a Developing Construction Industry: A Cross-Cultural Validation Study.

Science.gov (United States)

Zahoor, Hafiz; Chan, Albert P C; Utama, Wahyudi P; Gao, Ran; Zafar, Irfan

2017-03-28

This study attempts to validate a safety performance (SP) measurement model in the cross-cultural setting of a developing country. In addition, it highlights the variations in investigating the relationship between safety climate (SC) factors and SP indicators. The data were collected from forty under-construction multi-storey building projects in Pakistan. Based on the results of exploratory factor analysis, a SP measurement model was hypothesized. It was tested and validated by conducting confirmatory factor analysis on calibration and validation sub-samples respectively. The study confirmed the significant positive impact of SC on safety compliance and safety participation , and negative impact on number of self-reported accidents/injuries . However, number of near-misses could not be retained in the final SP model because it attained a lower standardized path coefficient value. Moreover, instead of safety participation , safety compliance established a stronger impact on SP. The study uncovered safety enforcement and promotion as a novel SC factor, whereas safety rules and work practices was identified as the most neglected factor. The study contributed to the body of knowledge by unveiling the deviations in existing dimensions of SC and SP. The refined model is expected to concisely measure the SP in the Pakistani construction industry, however, caution must be exercised while generalizing the study results to other developing countries.

University building safety index measurement using risk and implementation matrix

Science.gov (United States)

Rahman, A.; Arumsari, F.; Maryani, A.

2018-04-01

Many high rise building constructed in several universities in Indonesia. The high-rise building management must provide the safety planning and proper safety equipment in each part of the building. Unfortunately, most of the university in Indonesia have not been applying safety policy yet and less awareness on treating safety facilities. Several fire accidents in university showed that some significant risk should be managed by the building management. This research developed a framework for measuring the high rise building safety index in university The framework is not only assessed the risk magnitude but also designed modular building safety checklist for measuring the safety implementation level. The safety checklist has been developed for 8 types of the university rooms, i.e.: office, classroom, 4 type of laboratories, canteen, and library. University building safety index determined using risk-implementation matrix by measuring the risk magnitude and assessing the safety implementation level. Building Safety Index measurement has been applied in 4 high rise buildings in ITS Campus. The building assessment showed that the rectorate building in secure condition and chemical department building in beware condition. While the library and administration center building was in less secure condition.

Assessment of the safety of injection practices and injection-related procedures in family health units and centers in Alexandria.

Science.gov (United States)

Elhoseeny, Taghareed A; Mourad, Juidan K

2014-08-01

The Safe Injection Global Network (SIGN) developed an intervention strategy for reducing overuse of injections and promoting the administration of safe injections. Tool C--Revised is designed to assess the safety of the most common procedures that puncture the skin within health services. The aim of the study was to assess injection safety within the primary healthcare facilities in Alexandria using Tool C--Revised. A total of 45 family health units and centers in Alexandria were selected by proportional allocation from the eight regions of Alexandria. The Tool C--Revised of the WHO was used for observation of the entire facility, injection practices and injection-related procedures, and sterilization practices. Interview of different health providers and immediate supervisor of injections was carried out. Indicators that reflect risk included: deficiency of alcohol-based hand rub for cleansing hands (13.3%), compliance with hand wash before preparing a procedure (56.9% before injection practices, 61.3% before phlebotomy, and 67.6% before lancet puncture), and wearing a new pair of gloves before new procedures (48.6% before injection practices, 9.7% for phlebotomy, 11.8% for lancet puncture, and 80% for both intravenous injections and infusions). Enough disposable equipment in all facilities for at least 2 weeks dependent on the statement of the average numbers of procedures per week was shown. Only 38% of the providers had received training regarding injection safety in the last 2 years and 62.5% had completed their three doses of hepatitis B vaccine. Only 42.2% of staffs who handled healthcare waste had access to heavy gloves. Indicators related to injection and injection-related practices that reflect risk to patients include deficiency of alcohol-based hand rub tools, nonadherence to hand hygiene before preparing an injection, and inadequate adherence to using a clean barrier when opening a glass ampule and use of gloves. Indicators that may reflect risk to

Challenges in developing competency-based training curriculum for food safety regulators in India

Directory of Open Access Journals (Sweden)

Anitha Thippaiah

2014-01-01

Full Text Available Context: The Food Safety and Standards Act have redefined the roles and responsibilities of food regulatory workforce and calls for highly skilled human resources as it involves complex management procedures. Aims: 1 Identify the competencies needed among the food regulatory workforce in India. 2 Develop a competency-based training curriculum for food safety regulators in the country. 3 Develop training materials for use to train the food regulatory workforce. Settings and Design: The Indian Institute of Public Health, Hyderabad, led the development of training curriculum on food safety with technical assistance from the Royal Society for Public Health, UK and the National Institute of Nutrition, India. The exercise was to facilitate the implementation of new Act by undertaking capacity building through a comprehensive training program. Materials and Methods: A competency-based training needs assessment was conducted before undertaking the development of the training materials. Results: The training program for Food Safety Officers was designed to comprise of five modules to include: Food science and technology, Food safety management systems, Food safety legislation, Enforcement of food safety regulations, and Administrative functions. Each module has a facilitator guide for the tutor and a handbook for the participant. Essentials of Food Hygiene-I (Basic level, II and III (Retail/ Catering/ Manufacturing were primarily designed for training of food handlers and are part of essential reading for food safety regulators. Conclusion: The Food Safety and Standards Act calls for highly skilled human resources as it involves complex management procedures. Despite having developed a comprehensive competency-based training curriculum by joint efforts by the local, national, and international agencies, implementation remains a challenge in resource-limited setting.

78 FR 37228 - Cooperative Agreement To Support the Western Center for Food Safety

Science.gov (United States)

2013-06-20

... FSMA activities. FDA regards the development and strengthening of public-private partnerships to be a... agricultural producers, along with other public and private stakeholders. This established UC Davis network... study the agro- ecological differences that may impact food safety in the agricultural sector. WCFS has...

Development of E-Learning Materials for Machining Safety Education

Science.gov (United States)

Nakazawa, Tsuyoshi; Mita, Sumiyoshi; Matsubara, Masaaki; Takashima, Takeo; Tanaka, Koichi; Izawa, Satoru; Kawamura, Takashi

We developed two e-learning materials for Manufacturing Practice safety education: movie learning materials and hazard-detection learning materials. Using these video and sound media, students can learn how to operate machines safely with movie learning materials, which raise the effectiveness of preparation and review for manufacturing practice. Using these materials, students can realize safety operation well. Students can apply knowledge learned in lectures to the detection of hazards and use study methods for hazard detection during machine operation using the hazard-detection learning materials. Particularly, the hazard-detection learning materials raise students‧ safety consciousness and increase students‧ comprehension of knowledge from lectures and comprehension of operations during Manufacturing Practice.

75 FR 12554 - Mine Safety and Health Research Advisory Committee, National Institute for Occupational Safety...

Science.gov (United States)

2010-03-16

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Mine Safety and Health Research Advisory Committee, National Institute for Occupational Safety and Health (MSHRAC, NIOSH... priorities in mine safety and health research, including grants and contracts for such research, 30 U.S.C...

Improving occupational safety and health by integration into product development

DEFF Research Database (Denmark)

Broberg, Ole

1996-01-01

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

Current Situation and Developing Countermeasures of Postgraduate Innovation Center in China

Directory of Open Access Journals (Sweden)

Li Can

2017-01-01

Full Text Available Innovation is the driving force to promote the development of our nation. Postgraduate education, as an important approach to cultivate high-level talents, is a major part of the national innovation system. The establishment of the Postgraduate Innovation Center has an important significance for the cultivation of innovative talents in colleges and universities. This paper expounds the connotation and characteristics of Postgraduate Innovation Center and analyzes its current situation, operation mode, function orientation, institution settings and the innovative products. The paper also points out the problems in the current situation of the Postgraduate Innovation Center and finds the factors which restrict the development of the center. Finally, the paper puts forward some corresponding countermeasures.

Development of safety enhancement technology of containment building

International Nuclear Information System (INIS)

Seo, Jeong Moon; Choun, Y. S.; Choi, I. K.

2002-04-01

This study consists of four research areas, (1) Seismic safety assessment, (2) Aging assessment of a containment building, (3) Prediction of long-term behavior and analysis of a containment building, (4) Performance verification of a containment building. In the seismic safety assessment area, responses of a containment building were monitored and the analysis method was verified. Also performed are the identification of earthquake characteristics and improvement of the seismic fragility analysis method. In the area of aging assessment of a containment building, we developed aging management code SLMS and database. Aging tests were performed for containment building materials and aging models were developed. Techniques for investigation, detection, and evaluation of aging were developed. In the area of prediction of long-term behavior and analysis of a containment building, we developed a non-linear structural analysis code NUCAS and material models. In the area of performance verification of a containment building, we analyzed the crack behavior of a containment wall and the behavior of the containment under internal pressure. We also improved the ISI methods for prestressed containment

The development of NPP operational safety training courses

International Nuclear Information System (INIS)

Lee, Chang Kun; Lee, Duk Sun; Lee, Byung Sun; Lee, Won Koo; Juhn, Heng Run; Moon, Byung Soo; Cho, Min Sik; Lee, Han Young; Moon, Hak Won; Seo, Yeon Ho

1987-12-01

The objective of the project is to develop a training course text for the betterment of reactor operation and assurance of its safety in general by providing training materials of the advanced compact nuclear simulator which will become operation in September 1988. Main scope and contents of the project are as follows: - compilation of basic data related to simulator operation and maintenance as well as the comparative analysis with respect to simulator materials in foreign countries - method of training by simulator - review the training status by simulator in foreign countries - development of training course in the field of reactor safety It is expected that the results will be reflected to the actual training and retraining of the reactor operating crew so as to improve and update their capabilities in training fashion. (Author)

Finding Your Voice: Talent Development Centers and the Academic Talent Search

Science.gov (United States)

Rushneck, Amy S.

2012-01-01

Talent Development Centers are just one of many tools every family, teacher, and gifted advocate should have in their tool box. To understand the importance of Talent Development Centers, it is essential to also understand the Academic Talent Search Program. Talent Search participants who obtain scores comparable to college-bound high school…

Development and Testing of the Glenn Research Center Visitor's Center Grid-Tied Photovoltaic Power System

Science.gov (United States)

Eichenberg, Dennis J.

2009-01-01

The NASA Glenn Research Center (GRC) has developed, installed, and tested a 12 kW DC grid-tied photovoltaic (PV) power system at the GRC Visitor s Center. This system utilizes a unique ballast type roof mount for installing the photovoltaic panels on the roof of the Visitor s Center with no alterations or penetrations to the roof. The PV system has generated in excess of 15000 kWh since operation commenced in August 2008. The PV system is providing power to the GRC grid for use by all. Operation of the GRC Visitor s Center PV system has been completely trouble free. A grid-tied PV power system is connected directly to the utility distribution grid. Facility power can be obtained from the utility system as normal. The PV system is synchronized with the utility system to provide power for the facility, and excess power is provided to the utility. The project transfers space technology to terrestrial use via nontraditional partners. GRC personnel glean valuable experience with PV power systems that are directly applicable to various space power systems, and provides valuable space program test data. PV power systems help to reduce harmful emissions and reduce the Nation s dependence on fossil fuels. Power generated by the PV system reduces the GRC utility demand, and the surplus power aids the community. Present global energy concerns reinforce the need for the development of alternative energy systems. Modern PV panels are readily available, reliable, efficient, and economical with a life expectancy of at least 25 years. Modern electronics has been the enabling technology behind grid-tied power systems, making them safe, reliable, efficient, and economical with a life expectancy of at least 25 years. Based upon the success of the GRC Visitor s Center PV system, additional PV power system expansion at GRC is under consideration. The GRC Visitor s Center grid-tied PV power system was successfully designed and developed which served to validate the basic principles

Role of management in the development of safety culture at the operating organization

Energy Technology Data Exchange (ETDEWEB)

Zhong, W [International Atomic Energy Agency, Vienna (Austria)

1997-09-01

Role of management in the development of safety culture at the operating organization to offer practical suggestions to assist in the development or improvement of a progressive safety culture. 2 figs.

Role of management in the development of safety culture at the operating organization

International Nuclear Information System (INIS)

Zhong, W.

1997-01-01

Role of management in the development of safety culture at the operating organization to offer practical suggestions to assist in the development or improvement of a progressive safety culture. 2 figs