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Sample records for active safety systems

  1. Future testing of active safety systems

    Hendriks, F.M.; Pelders, H.A.A.W.

    2010-01-01

    Active safety systems are increasingly becoming available in trucks and passenger vehicles. Developments in the field of active safety are shifting from increasing driver comfort towards increasing occupant safety. Furthermore, this shift is seen within active safety systems: safety functions are ad

  2. Prestandardisation Activities for Computer Based Safety Systems

    Taylor, J. R.; Bologna, S.; Ehrenberger, W.;

    1981-01-01

    Questions of technical safety become more and more important. Due to the higher complexity of their functions computer based safety systems have special problems. Researchers, producers, licensing personnel and customers have met on a European basis to exchange knowledge and formulate positions....... The Commission of the european Community supports the work. Major topics comprise hardware configuration and self supervision, software design, verification and testing, documentation, system specification and concurrent processing. Preliminary results have been used for the draft of an IEC standard...

  3. The Management System for Facilities and Activities. Safety Requirements

    This publication establishes requirements for management systems that integrate safety, health, security, quality assurance and environmental objectives. A successful management system ensures that nuclear safety matters are not dealt with in isolation but are considered within the context of all these objectives. The aim of this publication is to assist Member States in establishing and implementing effective management systems that integrate all aspects of managing nuclear facilities and activities in a coherent manner. It details the planned and systematic actions necessary to provide adequate confidence that all these requirements are satisfied. Contents: 1. Introduction; 2. Management system; 3. Management responsibility; 4. Resource management; 5. Process implementation; 6. Measurement, assessment and improvement.

  4. The Management System for Facilities and Activities. Safety Requirements

    This publication establishes requirements for management systems that integrate safety, health, security, quality assurance and environmental objectives. A successful management system ensures that nuclear safety matters are not dealt with in isolation but are considered within the context of all these objectives. The aim of this publication is to assist Member States to establish and implement effective management systems that integrate all aspects of managing nuclear facilities and activities in a coherent manner. It details the planned and systematic actions necessary to provide adequate confidence that all these requirements are satisfied

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

    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.

  6. A Novel Control Algorithm for Integration of Active and Passive Vehicle Safety Systems in Frontal Collisions

    Daniel Wallner

    2010-10-01

    Full Text Available The present paper investigates an approach to integrate active and passive safety systems of passenger cars. Worldwide, the introduction of Integrated Safety Systems and Advanced Driver Assistance Systems (ADAS is considered to continue the today

  7. EC-sponsored research activities on innovative passive safety systems

    On April 26th 1994, the European Union (EU) adopted via a Council Decision a EURATOM Multiannual Programme for community activities in the field of Nuclear Fission Safety (NFS) Research for the period 1994 to 1998. An area of work having, as an objective, to 'explore innovative approaches' to improve the safety of future and existing reactors, was introduced in this programme. Most of the projects selected in this area, which have been grouped under a common cluster known as 'INNO', are currently being carried out on a 'cost-shared' basis, i.e. contribution of the European Commission is up to 50% of the total cost. At present, the 'INNO' cluster is composed of 10 projects in which 25 different organisations, representing research centres, universities, regulators, utilities and vendors from 7 EU member states and Switzerland, are involved. These projects are proving to be an efficient means to gain the necessary phenomenological knowledge and to solve the challenging problems, many times of generic nature, posed among others by the characteristically small driving forces of the systems studied and by the lack of really prototypical test facilities. (author)

  8. Handbook of driver assistance systems basic information, components and systems for active safety and comfort

    Hakuli, Stephan; Lotz, Felix; Singer, Christina

    2016-01-01

    This fundamental work explains in detail systems for active safety and driver assistance, considering both their structure and their function. These include the well-known standard systems such as Anti-lock braking system (ABS), Electronic Stability Control (ESC) or Adaptive Cruise Control (ACC). But it includes also new systems for protecting collisions protection, for changing the lane, or for convenient parking. The book aims at giving a complete picture focusing on the entire system. First, it describes the components which are necessary for assistance systems, such as sensors, actuators, mechatronic subsystems, and control elements. Then, it explains key features for the user-friendly design of human-machine interfaces between driver and assistance system. Finally, important characteristic features of driver assistance systems for particular vehicles are presented: Systems for commercial vehicles and motorcycles.

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

    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

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

    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.

  11. Mechanical plan and activator system tool for nuclear radiation safety Boaster

    Its has been done a mechanical plan and nuclear radiation safety boaster tool activator system. The mechanical system consists of: frame, source holder, collimator and shielding holder. The activator system axis threads and crank stick handle that can be rotated either clockwise or counter clockwise. The axis thread is to be designed can be coupled with either convention.al activator system or activator that controlled a control system that by can be set forward and backward,or close and for to the source and detector. This system has freedom variable of 1000 mm between source and detector equipped with distance scale in mm. The shielding holder can be set its thickness as according to the shielding to be used. This design it is expected that the system can be used for any experiment related to protection system and safety as a function of distance factor time, and shielding. (author)

  12. Analysis of the reliability of the active injection safety systems of Angra I

    The reliability of the active emergency core cooling systems of Angra I nuclear power plant is evaluated. The fault tree analysis is employed. The unavailability of the above cited systems, is calculated. A parametric sensitivity analysis has been performed, due to the existing scattering in the failure and repair rate data of these system's components. The minimal cut sets were determined and, as a final step, a reliability importance analysis has been performed. This final step has required the development of a computer program. The methodology and data from the 'Reactor Safety Study' (Wash-1400) (in which the reliability of safety systems of a tipical PWR plant is calculated), is employed. The unavailability values for the safety systems analysed are too low, thus showing that in most cases the systems analysed are available to mitigate the effects of a loss-of-coolant accident. (Author)

  13. Application of the Management System for Facilities and Activities. Safety Guide

    This publication provides guidance for following the requirements for management systems that integrate safety, health, security, quality assurance and environmental objectives. A successful management system ensures that nuclear safety matters are not dealt with in isolation but are considered within the context of all these objectives. The aim of this publication is to assist Member States to establish and implement effective management systems that coherently integrate all aspects of managing nuclear facilities and activities. Contents: 1. Introduction; 2. Management system; 3. Management responsibility; 4. Resource management; 5. Process implementation; 6. Measurement, assessment and improvement; Appendix I: Transition to an integrated management system; Appendix II: Activities in the document control process; Appendix III: Activities in the procurement process; Appendix IV: Performance of independent assessments; Annex I: Electronic document management system; Annex II: Media for record storage; Annex III: Record retention and storage; Glossary.

  14. Benchmarking promotion and deployment activities regarding intelligent vehicle safety systems in the EU

    Kievit, M. de; Malone, K.M.; Zwijnenberg, H.; Arem, B. van

    2008-01-01

    This paper presents the results of a Benchmarking study performed in the European Union on Awareness and Promotion & Deployment activities related to Intelligent Vehicle Safety (IVS) systems (1). The study, commissioned by the European Commission under the Intelligent Car Initiative (a i2010 flagshi

  15. MSFC Skylab airlock module, volume 2. [systems design and performance, systems support activity, and reliability and safety programs

    1974-01-01

    System design and performance of the Skylab Airlock Module and Payload Shroud are presented for the communication and caution and warning systems. Crew station and storage, crew trainers, experiments, ground support equipment, and system support activities are also reviewed. Other areas documented include the reliability and safety programs, test philosophy, engineering project management, and mission operations support.

  16. Radiation safety audit system - safety perspectives

    In 2005 Safety and Health at the University of Western Australia (UWA) implemented a system of Radiation Safety Audits. The system was implemented to ensure complete audits were carried out annually for each section of the University with radiation safety issues. The audits cover those aspects of radiation safety regulated in the Radiation Safety Act of Western Australia and include high powered lasers, UV emitting devices, radioactive materials, x-ray machines. In relation to these there are regulated considerations for equipment registration, location of use and storage registration, licensing of individual to use radiation, training, documentation, working rules, personal monitoring, calibrations and supervision. Within the University there are University systems to control materials and equipment coming onto campus, risk assessment protocols required for each new project or type of work, local permits and waste disposal. UWA Safety and Health have an active role in delivering control of radiation safety and ensuring that safety systems are appropriate relevant and used in an immediate and useful manner. Safety and Health has importantly built a network of key people on campus, made sure they are assisted, valued and that the systems are seen as a way to improve efficiency in delivering real, relevant and useful radiation safety outcomes. The systems include uniform documentation across campus, clear expectations and an ongoing interest from Safety and Health to ensure the systems remain alive. This has allowed the audits to become efficient and effective both for the sections involved but also for Safety and health in its recording systems and improvement follow up process.

  17. Handling and safety enhancement of race cars using active aerodynamic systems

    Diba, Fereydoon; Barari, Ahmad; Esmailzadeh, Ebrahim

    2014-09-01

    A methodology is presented in this work that employs the active inverted wings to enhance the road holding by increasing the downward force on the tyres. In the proposed active system, the angles of attack of the vehicle's wings are adjusted by using a real-time controller to increase the road holding and hence improve the vehicle handling. The handling of the race car and safety of the driver are two important concerns in the design of race cars. The handling of a vehicle depends on the dynamic capabilities of the vehicle and also the pneumatic tyres' limitations. The vehicle side-slip angle, as a measure of the vehicle dynamic safety, should be narrowed into an acceptable range. This paper demonstrates that active inverted wings can provide noteworthy dynamic capabilities and enhance the safety features of race cars. Detailed analytical study and formulations of the race car nonlinear model with the airfoils are presented. Computer simulations are carried out to evaluate the performance of the proposed active aerodynamic system.

  18. System safety education focused on flight safety

    Holt, E.

    1971-01-01

    The measures necessary for achieving higher levels of system safety are analyzed with an eye toward maintaining the combat capability of the Air Force. Several education courses were provided for personnel involved in safety management. Data include: (1) Flight Safety Officer Course, (2) Advanced Safety Program Management, (3) Fundamentals of System Safety, and (4) Quantitative Methods of Safety Analysis.

  19. A Development Framework for Software Security in Nuclear Safety Systems: Integrating Secure Development and System Security Activities

    The protection of nuclear safety software is essential in that a failure can result in significant economic loss and physical damage to the public. However, software security has often been ignored in nuclear safety software development. To enforce security considerations, nuclear regulator commission recently issued and revised the security regulations for nuclear computer-based systems. It is a great challenge for nuclear developers to comply with the security requirements. However, there is still no clear software development process regarding security activities. This paper proposes an integrated development process suitable for the secure development requirements and system security requirements described by various regulatory bodies. It provides a three-stage framework with eight security activities as the software development process. Detailed descriptions are useful for software developers and licensees to understand the regulatory requirements and to establish a detailed activity plan for software design and engineering

  20. Functional Safety for Safety-Related Systems: 10 Common Mistakes

    Brissaud, Florent; Turcinovic, Didier

    2015-01-01

    International audience The functional safety is the part of the overall safety relating to equipment/ system/ installation and their control systems that depends on the correct functioning of the safety-related systems. Due to the critical role of safety-related systems for managing risks, international standards have been developed to provide guidelines and requirements for all their safety lifecycle activities. The IEC 61508 and IEC 61511 are now recognized all around the world and have ...

  1. Reactor system safety assurance

    The philosophy of reactor safety is that design should follow established and conservative engineering practices, there should be safety margins in all modes of plant operation, special systems should be provided for accidents, and safety systems should have redundant components. This philosophy provides ''defense in depth.'' Additionally, the safety of nuclear power plants relies on ''safety systems'' to assure acceptable response to design basis events. Operating experience has shown the need to study plant response to more frequent upset conditions and to account for the influence of operators and non-safety systems on overall performance. Defense in depth is being supplemented by risk and reliability assessment

  2. Waste safety activities

    Safety standards develop by the IAEA in the Safety Standard Series and other publication are reviewed. The Waste Safety Action plan includes: Action 1: Develop a common framework for the management and disposal of different types of radioactive waste, paying particular attention to large volumes of waste containing long-lived naturally occurring radionuclides. Action 2: Assess the safety implications of the extended storage of radioactive waste and of any future reconditioning which may be necessary and develop safety standards for the long-term storage of radioactive waste. Action 3: Promptly develop safety standards for geological disposal, addressing inter alia, issues of human intrusion, institutional control, retrievability, the content of the safety case and any implications of nuclear safeguards requirements for the design of the repositories. Action 4: Develop an internationally accepted and harmonized approach for controlling the removal of materials and sites from regulatory control. Action 5: Develop a structured and systematic programme to ensure adequate application of the Agency waste safety standards and facilitate their application in implementation of the Joint Convention. Action 6: Explore ways to ensure that information, knowledge and skills concerning radioactive waste management are made available to future generations. Action 7: Address the broader societal dimensions of radioactive waste management. Action 8: Review the new developments related to policies for the control of radioactive discharges to the environment, taking into account the availability and cost-effectiveness of discharge reduction technologies and the broader implications for radioactive waste management of reducing discharges. Action 9: Explore international mechanisms for facilitating the management of spent sealed radioactive sources. Some other activities as training courses and technical cooperation are also presented

  3. Modeling and Simulation of integrated steering and braking control for vehicle active safety system

    Beibei Zhang

    2011-03-01

    Full Text Available Active chassis systems like braking, steering, suspension and propulsion systems are increasingly entering the market. In addition to their basic functions, these systems may be used for functions of integrated vehicle dynamics control. An experimental platform which aims to study the integration control of steering and braking is designed due to the research requirement of vehicle active safety control strategy in this paper. A test vehicle which is equipped with the systems of steer-by-wire and brake-bywire is provided and the Autobox, combined with Matlab/simulink and MSCCarsim, is used to fulfill the RCP (Rapid Control Prototyping and HIL (Hardware-in-loop. The seven-freedom vehicle model is constructed first and the approach of vehicle parameters estimation based on the Extended Kalman Filter (EKF is proposed. Testing the vehicle state through the sensor has its own disadvantage that the cost is high and easily affected by environment outside. To find a actual method of receiving the vehicle state using the ready-made sensors in vehicle, the researchers put forward various estimation method, of which have advantages and disadvantages. Based on the above, this paper applies the EKF to estimate the vehicle state, making the actual estimation come true. The primary control methods and controller designment is carried out to prove the validation of the platform.

  4. Safety system function trends

    This paper describes research to develop risk-based indicators of plant safety performance. One measure of the safety-performance of operating nuclear power plants is the unavailability of important safety systems. Brookhaven National Laboratory and Science Applications International Corporation are evaluating ways to aggregate train-level or component-level data to provide such an indicator. This type of indicator would respond to changes in plant safety margins faster than the currently used indicator of safety system unavailability (i.e., safety system failures reported in licensee event reports). Trends in the proposed indicator would be one indication of trends in plant safety performance and maintenance effectiveness. This paper summarizes the basis for such an indicator, identifies technical issues to be resolved, and illustrates the potential usefullness of such indicators by means of computer simulations and case studies

  5. Instructional Resources Monograph Series: Safety in Wastewater Treatment Systems. Selected Instructional Activities and References.

    Coon, Herbert L.

    Described are instructional and reference materials that may be useful to managers, supervisors, foremen and others who are interested in the safety education of workers in wastewater systems. Emphasis is upon items relevant to the development and presentation of wastewater treatment training programs. Part I contains descriptions and excerpts…

  6. 76 FR 67201 - Information Collection Activities: Oil and Gas Production Safety Systems; Submitted for Office of...

    2011-10-31

    ... Production Safety Systems; Submitted for Office of Management and Budget (OMB) Review; Comment Request ACTION... Information and Regulatory Affairs, OMB, Attention: Desk Officer for the Department of the Interior (1014-0003...: Cheryl Blundon 381 Elden Street, Herndon, Virginia 20170- 4817. Please reference 1014-0003 in...

  7. 78 FR 50079 - Information Collection Activities: Safety and Environmental Management Systems (SEMS); Proposed...

    2013-08-16

    ... From the Federal Register Online via the Government Publishing Office DEPARTMENT OF THE INTERIOR Bureau of Safety and Environmental Enforcement [Docket ID BSEE-2013-0005; OMB Control Number 1014-0017... Management Systems (SEMS); Proposed Collection; Comment Request Correction In notice document...

  8. 78 FR 48890 - Information Collection Activities: Safety and Environmental Management Systems (SEMS); Proposed...

    2013-08-12

    ... Bureau of Safety and Environmental Enforcement [Docket ID BSEE-2013-0005; OMB Control Number 1014-0017... Management Systems (SEMS); Proposed Collection; Comment Request ACTION: 60-day Notice. SUMMARY: To comply...) is inviting comments on a collection of information that we will resubmit to the Office of...

  9. Safety system status monitoring

    The Pacific Northwest Laboratory has studied the safety aspects of monitoring the preoperational status of safety systems in nuclear power plants. The goals of the study were to assess for the NRC the effectiveness of current monitoring systems and procedures, to develop near-term guidelines for reducing human errors associated with monitoring safety system status, and to recommend a regulatory position on this issue. A review of safety system status monitoring practices indicated that current systems and procedures do not adequately aid control room operators in monitoring safety system status. This is true even of some systems and procedures installed to meet existing regulatory guidelines (Regulatory Guide 1.47). In consequence, this report suggests acceptance criteria for meeting the functional requirements of an adequate system for monitoring safety system status. Also suggested are near-term guidelines that could reduce the likelihood of human errors in specific, high-priority status monitoring tasks. It is recommended that (1) Regulatory Guide 1.47 be revised to address these acceptance criteria, and (2) the revised Regulatory Guide 1.47 be applied to all plants, including those built since the issuance of the original Regulatory Guide

  10. Planned activities to improve safety

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

  11. Reactor safety systems

    The spectrum of possible accidents may become characterized by the 'maximum credible accident', which will/will not happen. Similary, the performance of safety systems in a multitude of situations is sometimes simplified to 'the emergency system will/will not work' or even 'reactors are/ are not safe'. In assessing safety, one must avoid this fallacy of reducing a complicated situation to the simple black-and-white picture of yes/no. Similarly, there is a natural tendency continually to improve the safety of a system to assure that it is 'safe enough'. Any system can be made safer and there is usually some additional cost. It is important to balance the increased safety against the increased costs. (orig.)

  12. IAEA Safety Standards on Management Systems and Safety Culture

    The IAEA has developed a new set of Safety Standard for applying an integrated Management System for facilities and activities. The objective of the new Safety Standards is to define requirements and provide guidance for establishing, implementing, assessing and continually improving a Management System that integrates safety, health, environmental, security, quality and economic related elements to ensure that safety is properly taken into account in all the activities of an organization. With an integrated approach to management system it is also necessary to include the aspect of culture, where the organizational culture and safety culture is seen as crucial elements of the successful implementation of this management system and the attainment of all the goals and particularly the safety goals of the organization. The IAEA has developed a set of service aimed at assisting it's Member States in establishing. Implementing, assessing and continually improving an integrated management system. (author)

  13. EDA activities related to safety

    This article reviews the accomplishments in ITER safety analysis during the course of the Engineering Design Activities (EDA). The key aspects of ITER safety analysis are: effluents and emissions from normal operation, including planned maintenance activities; occupational safety for workers at the facility; radioactive materials and wastes generated during operation and from decommissioning ; potential incidents and accidents and the resulting transients. As a result of the work during the EDA it is concluded that ITER is safe

  14. PWRs with passive safety systems

    The development activities in the area of nuclear plant design in recent years have caused widespread interest in the plants incorporating passive safety features and simplified system designs. In recent years, design studies were undertaken to use passive phenomena such as natural circulation and gravity to provide safety functions, rather than to rely on the active systems requiring power supply and control systems. The resulting simplification leads to reduced capital costs and shortened construction period. Westinghouse developed the AP600 plant, which is a 600 MWe PWR and features passive safety systems, simplified plant design and the decreased reliance on operator interface. In 1988, the program was initiated to investigate the application of AP600 technology to the use in Japan with more appropriate design features. This plant with 960 MWe rating is designated 'Simplified pressurized water reactor' (SPWR). The key objectives of the SPWR design are shown. The reactor cooling system, the plant instrumentation and control, the passive engineered safety features, the testing program, the plant arrangement and seismic consideration, the safety analysis and the plant simplification and economics of the SPWR are reported. (K.I.)

  15. ITER system study---Safety aspects

    One of the tasks of the ITER Systems Analysis Group has been safety and environmental analyses. The safety analyses show that radiological doses from operational effluents and accidents are consistent with anticipated regulatory dose limits. To improve safety further and to meet the ambitious goal of ''passive safety,'' further efforts to reduce inventories of tritium and activation products are proposed. Most major safety issues are now associated with Plasma Facing Components (PFC). 2 tabs

  16. Co-injection Current Transformer: An Active Device in the AGS Facility Safety System

    Reece, R. K.; Smith, G. A.

    1997-05-01

    The AGS facility can change operating parameters (particle, intensity, extraction mode, etc.) in a pulse-to-pulse mode. This will soon become essential in order to fill the RHIC accelerator rings interleaved with providing beam to the fixed target experiments at the AGS. However, since the AGS intensity for fixed targets is much greater than that required for RHIC, a means of ensuring that only the proper beam and intensity is extracted to RHIC has been developed. A beam current transformer in the AGS accelerator chain will detect the beam intensity and provide the necessary permits for extraction to RHIC only if the beam intensity is below a specified threshold. System details of this dual, redundant current transformer, as well as the system constraints imposed by the various safety requirements, will be presented. The interdependence of these two issues and evolution of the overall design will also be described.

  17. Safety System functional inspections

    The basic purpose of Safety System Functional Inspections (SSFI) is to carry out an impartial and independent assessment of previously selected safety systems, in order to determine whether they have been installed, tested, operated and managed in accordance with the original Design Bases and with the applicable regulatory requirements, codes and standards, that is, their Licensing Bases. These functional inspections are performed within the framework established by the Quality Assurance Programmes of electric utility owners, and in accordance with specifically prepared procedures previously approved for each power plant. These SSFIs verify, for safety systems and their support systems (eg HVAC systems, etc), the operational availability of inspected systems of components by researching and determining whether there have been generic or programmed deficiencies in the course of Operation, that will prevent the systems from adequately performing the functions for which they were originally designed. PSA and IPE results are used as the basis for selecting the systems that should undergo functional inspections. As a consequence of these SSFIs, final reports will be prepared, summarizing actions taken at the plants and contemplating discrepancies or deviations detected during inspection. The necessary corrective actions for these discrepancies will be indicated in either the design documentation or the Operation and Maintenance Procedures. (Author)

  18. Safety analysis and review system

    Westinghouse Savannah River Company (WSRC) has developed a comprehensive Safety Analysis and Review System that satisfies Department of Energy safety analysis report requirements. This system consists of interrelated criteria for hazard classification, risk assessment, selection of Safety Class Items (SCIs), and selection of Operational Safety Requirements (OSRs). The system provides input for design decisions at appropriate project milestones as required by the life cycle of a project. The criteria used for selection in hazard classification, risk assessment, Safety Class Items (SCI) identification, and Operational Safety Requirement (OSR) identification are the subject of this paper

  19. Systems engineered health and safety criteria for safety analysis reports

    The world of safety analysis is filled with ambiguous words: codes and standards, consequences and risks, hazard and accident, and health and safety. These words have been subject to disparate interpretations by safety analysis report (SAR) writers, readers, and users. open-quotes Principal health and safety criteriaclose quotes has been one of the most frequently misused phrases; rarely is it used consistently or effectively. This paper offers an easily understood definition for open-quotes principal health and safety criteriaclose quotes and uses systems engineering to convert an otherwise mysterious topic into the primary means of producing an integrated SAR. This paper is based on SARs being written for environmental restoration and waste management activities for the U.S. Department of Energy (DOE). Requirements for these SARs are prescribed in DOE Order 5480-23, open-quotes Nuclear Safety Analysis Reports.close quotes

  20. JRC activities in nuclear safety

    Manna Giustino

    2009-01-01

    Full Text Available Nuclear energy is today the largest single source of carbon free and base-load electricity in Europe. While highlighting its important role in the overall energy mix, it is necessary to address sustainability, safety, and security concerns, in particular nuclear safety and nuclear waste management issues, which influence the public acceptance of nuclear energy. The present paper describes the Joint Research Centre activities in support to the EU nuclear safety policy. It describes the Joint Research Centre role in the EU institutional context, identifies the various customers to which the Joint Research Centre delivers its services, and provides some results of the Joint Research Centre scientific work inherent to nuclear safety.

  1. Evaluating safety management system implementation

    Canada is committed to not only maintaining, but also improving upon our record of having one of the safest aviation systems in the world. The development, implementation and maintenance of safety management systems is a significant step towards improving safety performance. Canada is considered a world leader in this area and we are fully engaged in implementation. By integrating risk management systems and business practices, the aviation industry stands to gain better safety performance with less regulatory intervention. These are important steps towards improving safety and enhancing the public's confidence in the safety of Canada's aviation system. (author)

  2. Software Quality Assurance for Nuclear Safety Systems

    The US Department of Energy has undertaken an initiative to improve the quality of software used to design and operate their nuclear facilities across the United States. One aspect of this initiative is to revise or create new directives and guides associated with quality practices for the safety software in its nuclear facilities. Safety software includes the safety structures, systems, and components software and firmware, support software and design and analysis software used to ensure the safety of the facility. DOE nuclear facilities are unique when compared to commercial nuclear or other industrial activities in terms of the types and quantities of hazards that must be controlled to protect workers, public and the environment. Because of these differences, DOE must develop an approach to software quality assurance that ensures appropriate risk mitigation by developing a framework of requirements that accomplishes the following goals: (smbullet) Ensures the software processes developed to address nuclear safety in design, operation, construction and maintenance of its facilities are safe (smbullet) Considers the larger system that uses the software and its impacts (smbullet) Ensures that the software failures do not create unsafe conditions Software designers for nuclear systems and processes must reduce risks in software applications by incorporating processes that recognize, detect, and mitigate software failure in safety related systems. It must also ensure that fail safe modes and component testing are incorporated into software design. For nuclear facilities, the consideration of risk is not necessarily sufficient to ensure safety. Systematic evaluation, independent verification and system safety analysis must be considered for software design, implementation, and operation. The software industry primarily uses risk analysis to determine the appropriate level of rigor applied to software practices. This risk-based approach distinguishes safety

  3. Traceability of Software Safety Requirements in Legacy Safety Critical Systems

    Hill, Janice L.

    2007-01-01

    How can traceability of software safety requirements be created for legacy safety critical systems? Requirements in safety standards are imposed most times during contract negotiations. On the other hand, there are instances where safety standards are levied on legacy safety critical systems, some of which may be considered for reuse for new applications. Safety standards often specify that software development documentation include process-oriented and technical safety requirements, and also require that system and software safety analyses are performed supporting technical safety requirements implementation. So what can be done if the requisite documents for establishing and maintaining safety requirements traceability are not available?

  4. Safety in networks and systems

    State authorities have set safety criteria in the field of information technology as standard. A specific research and development direction has been initiated in order to fulfil these standards. At Siemens it is called ''network and system safety''. This edition of the Siemens magazine Special Research and Development gives an overview of the research and development works carried out in order to guarantee safety and reliability of Siemens products and systems. Computer networks, chips, fax coding, safety of railway signalling technique, control technology, telecommunication and safety control technique in nuclear power plants. (DG)

  5. Safety logic systems of PFBR

    Full text : PFBR is provided with two independent, fast acting and diverse shutdown systems to detect any abnormalities and to initiate safety action. Each system consists of sensors, signal processing systems, logics, drive mechanisms and absorber rods. The absorber rods of the first system are Control and Safety Rods (CSR) and that of the second are called as Diverse Safety Rods (DSR). There are nine CSR and three DSR. While CSR are used for startup, control of reactor power, controlled shutdown and SCRAM, the DSR are used only for SCRAM. The respective drive mechanisms are called as CSRDM and DSRDM. Each of these two systems is capable of executing the shutdown satisfactorily with single failure criteria. Two independent safety logic systems based on diverse principles have been designed for the two shut down systems. The analog outputs of the sensors of Core Monitoring Systems comprising of reactor flux monitoring, core temperature monitoring, failed fuel detection and core flow monitoring systems are processed and converted into binary signals depending on their instantaneous values. Safety logic systems receive the binary signals from these core-monitoring systems and process them logically to protect the reactor against postulated initiating events. Neutronic and power to flow (P/Q) signals form the inputs to safety logic system-I and temperature signals are inputs to the safety logic system II. Failed fuel detection signals are processed by both the shut down systems. The two logic systems to actuate the safety rods are also based on two diverse designs and implemented with solid-state devices to meet all the requirements of safety systems. Safety logic system I that caters to neutronic and P/Q signals is designed around combinational logic and has an on-line test facility to detect struck at faults. The second logic system is based on dynamic logic and hence is inherently safe. This paper gives an overview of the two logic systems that have been

  6. CDC STATE System Tobacco Legislation - Fire Safety

    U.S. Department of Health & Human Services — 1995-2016. Centers for Disease Control and Prevention (CDC). State Tobacco Activities Tracking and Evaluation (STATE) System. Legislation – Fire-Safety. The STATE...

  7. Dynamic safety systems in BWR plant safety systems

    Dynamic Safety Systems (DSSs) are reactor safety function systems that are functionally controlled using dynamic rather than static processes. All components including software, whose failure could result in a critical safety system failure, are operationally verified by hard-wired components. Dynamic Safety Systems have been enveloped in the United Kingdom by AEA Technology for use in gas cooled reactors. One such system, known as ISAT trademark, is described in this paper. Through use of scenario testing of a DDS emulator on a Boiling Water Reactor plant training simulator described in this paper. Through use of scenario testing of a DSS emulator on a Boiling Water Reactor plant training simulator, it is shown that a DSS can provide a cost effective safety system in BWR power plants

  8. The Evolution of System Safety at NASA

    Dezfuli, Homayoon; Everett, Chris; Groen, Frank

    2014-01-01

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

  9. Analgesic activity and safety of ash of silver used in Indian system of medicine in mice: A reverse pharmacological study

    Deep Inder

    2012-01-01

    Full Text Available Objective: To study the analgesic activity of ash of silver used in Indian system of medicine and to explore its safety. Materials and Methods: Albino mice of either sex (20-30 gm were used to investigate the role of ash of silver against noxious stimuli: thermal (Eddy′s hot plate and analgesiometer, mechanical (tail clip, and chemical (0.6% acetic acid induced writhing. An effort was made to find nature and site of action of ash of silver following naloxone pre-treatment. Maximum tolerated dose (MTD and lethal dosage 50 (LD50 were also studied along with toxicological aspects of ash of silver. Results: Test drug (ash of silver at a dose of 50 mg/kg p.o exhibited analgesic activity against thermal, mechanical, and chemical stimuli. Analgesic effects were compared with the standard drug, morphine, in thermal and mechanical noxious stimuli and to aspirin in chemical stimulus. Analgesic activity of the test drug was reduced following naloxone pre-treatment. MTD was found out to be greater than 1.5 g/kg p.o. LD50 was 2 g/kg p.o. Fraction of mice showed symptoms of argyria as explained by autopsy reports. Conclusion: Test drug exhibited moderate analgesic activity at 50 mg/kg p.o against all type of noxious stimuli, also suggesting a role of opioidergic system. The ash of silver was been found to be safe upto a dose of 1.5 g/kg p.o. in mice without any untoward toxicity. Further studies are required to explore the effect of ash of silver on pain mediators and excitatory neurotransmitters like glutamate, aspartate, or N-methyl-D-aspartic acid (NMDA.

  10. Safety culture and quality system

    The purpose of this paper is to present the findings of the study conducted by a group of experts from EDF corporate departments on the conditions of the development of safety culture in the French nuclear power plants. The recommendations included in INSAG 4 sound rather like requirements concerning both the desirable attitudes of players and the operation of the organizations. The working group, referring to corporate and French culture, has deemed that the major leverage for cultural development was learning and understanding organization throughout its evolution. The quality system is one of the tools. Such a proposal should be placed against the background of some milestones of French nuclear power plant history. During the development phase, industrial challenge and safety requirements have led to putting a premium on the principles of industrial quality, on structured methods, working procedures, provisional risk and operating sequence analyses which resulted in effective mastery of technology and process. Within this strategy of production organization, human behaviour has been directed by strict guidelines and during this period, man has been perceived as a potential failure inducer. Quality remains the outstanding feature of nuclear industry. Design and plant operations activities as well as human behaviour are governed by quality requirements whose implementation methods are described in the QA manual. During this period, the structuring logics have been implementation, deviation, error. Currently, public opinion, safety authorities, government authorities, the nuclear industry itself are stepping up pressure on safety requirements and we are exploring paths of progress in the enhancement of human and organizational possibilities and resources. The ongoing in-depth transformation of the organization concerns operating methods, structures and management mode. A systemic approach should be a contributing factor to the reliability of this programme. This

  11. Safety balance: Analysis of safety systems

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

  12. Passive safety systems for the next generation of NPP's main R and D activities

    Containment Cooling and Depressurization of the Reactor Coolant, two major topics of mitigation of consequences of beyond design basis core damage accidents are dealt with by passive systems co-developed by Ansaldo and ENEL for the next generation of NPP's in the frame of international co-operation. A Passive Containment Cooling System (PCCS) concept consisting of modular loops, each with inner heat exchanger, outer condenser and interconnecting piping, has been developed for application to PWR units with dual concrete (EUR requirement) containment type. Two versions of the inner heat exchanger have been designed; the first one, under development by ENEL, features a compact tube-bundle with top-bottom natural draught of the air-steam mixture; the second one, under development by Ansaldo, consists of water-jacket modules embedded in the concrete containment. The key-components, the Isolation Condenser and the Passive Containment Cooler, of two passive systems for application to the SBWR, the advanced BWR of GE, for the control of respectively reactor and containment pressure have been developed, designed and tested on full-scale prototypical units. Depressurization of the Reactor Coolant by injection of cold borated water into the steam plenum is the result of the Passive Injection and Depressurization System (PIDS), a completely passive concept, applicable to both PWR and BWR designs

  13. Development and Improvement of Active Vehicle Safety Systems by Means of Smart Tire Technology

    Arat, Mustafa Ali

    2013-01-01

    The dynamic behavior of a vehicle is predominantly controlled by the forces and moments generated at the contact patch between the tire and the road surface. As a result, tire characteristics can dramatically change vehicle response, especially during maneuvers that yields the tires to reach to the limits of its adhesion capacity. To assist the driver in such cases and to prevent other possible instability scenarios, various vehicle control systems e.g. anti-lock brakes (ABS), ...

  14. Specialists' meeting on passive and active safety features of LMFRs

    The objective of the meeting was to discuss and exchange information on passive and active safety concepts and to find some reasonable coupling of these concept, aiming at firmer establishment of plant safety and at the same time of plant cost reduction. The following main topical areas were discussed by delegates: (1) Overview - review of national status on the safety design approaches of LMFRs (2) Safety characteristics of decay heat removal system (DHRS) (3) Safety characteristics of reactor protection system (RPS) and reactor shutdown system (RSS) (4) Core safety characteristics

  15. 77 FR 11120 - Patient Safety Organizations: Voluntary Relinquishment From UAB Health System Patient Safety...

    2012-02-24

    ... mission and primary activity is to conduct activities to improve patient safety and the quality of health... Relinquishment From UAB Health System Patient Safety Organization AGENCY: Agency for Healthcare Research and... relinquishment from the UAB Health System Patient Safety Organization of its status as a Patient......

  16. Plant and safety system model

    The design and development of a digital computer-based safety system for a nuclear power plant is a complex process. The process of design and product development must result in a final product free of critical errors; operational safety of nuclear power plants must not be compromised. This paper focuses on the development of a safety system model to assist designers, developers, and regulators in establishing and evaluating requirements for a digital computer-based safety system. The model addresses hardware, software, and human elements for use in the requirements definition process. The purpose of the safety system model is to assist and serve as a guide to humans in the cognitive reasoning process of establishing requirements. The goals in the use of the model are to: (1) enhance the completeness of the requirements and (2) reduce the number of errors associated with the requirements definition phase of a project

  17. IAEA activities on education and training in radiation and waste safety: Strategic approach for a sustainable system

    The statutory safety functions of the International Atomic Energy Agency (IAEA) include the establishment of and provision for the application of safety standards for protection of health, life and property against ionizing radiation. The safety standards are based on the presumption that a national infrastructure is in place enabling the Government to discharge its responsibilities for protection and safety. Education and training is an essential element of the infrastructure. The IAEA education and training activities follows the resolutions of its General Conferences and reflects the latest IAEA standards and guidance. In response to GC(44)/RES/13, the IAEA prepared a 'Strategic Approach to Education and Training in Radiation and Waste Safety' aiming at establishing, by 2010, sustainable education a training programmes in Member States. This Strategy was endorsed by General Conference resolution GC(45)/RES/10C that, inter alia, urged the Secretariat to implement the Strategy on Education and Training and to continue to strengthen, subject to available resources, its current effort in this area, and in particular to assist Member States' national, regional and collaborating centres in conducting such education and training activities in the relevant official languages of the IAEA. In the last General Conference 2002, the IAEA was urged to continue to implement the Strategy, including the convening of the Steering Committee. The first Technical Committee meeting took place during the week 25-29 November 2002. (author)

  18. Software Safety Risk in Legacy Safety-Critical Computer Systems

    Hill, Janice L.; Baggs, Rhoda

    2007-01-01

    Safety Standards contain technical and process-oriented safety requirements. Technical requirements are those such as "must work" and "must not work" functions in the system. Process-Oriented requirements are software engineering and safety management process requirements. Address the system perspective and some cover just software in the system > NASA-STD-8719.13B Software Safety Standard is the current standard of interest. NASA programs/projects will have their own set of safety requirements derived from the standard. Safety Cases: a) Documented demonstration that a system complies with the specified safety requirements. b) Evidence is gathered on the integrity of the system and put forward as an argued case. [Gardener (ed.)] c) Problems occur when trying to meet safety standards, and thus make retrospective safety cases, in legacy safety-critical computer systems.

  19. System safety education focused on system management

    Grose, V. L.

    1971-01-01

    System safety is defined and characteristics of the system are outlined. Some of the principle characteristics include role of humans in hazard analysis, clear language for input and output, system interdependence, self containment, and parallel analysis of elements.

  20. IAEA Activities on Education and training in Radiation and Waste Safety: Strategic approach for a sustainable system

    The statutory safety functions of the International Atomic Energy(IAEA) include the establishment of and provision for the application of safety standards for protection of health, life and property against ionizing radiation. The safety standards are based on the presumption that a national infrastructure is in place, enabling the Government to discharge its responsibilities for protection and safety. Education and training is an essential element of the infrastructure. the IAEA education and training activities follow the resolutions of its General Conference and reflect the latest IAEA standards and guidance. Several General Conference resolutions have emphasized the importance of education and training (e. g. GC(XXXV)/RES/552 in 1991; GC(XXXVI)/RES/584 in 1992; GC(43)/RES/13 in 1999 and more recently GC(44)/RES/13 in 2000). In response to GC(44)/RES/13, the IAEA prepared a Strategic Approach to Education and Training in Radiation and Waste Safety (Strategy on Education and Training) aiming at establishing, by 2010, sustainable education and training programmes in its Member States. This Strategy was endorsed by the General Conference resolution GC(45)/RES/10C that, inter alia, urged the Secretariat to implement the Strategy on Education and Training, and to continue to strengthen, subject to available resources, its current effort in this area, and in particular to assist Member States national, regional and collaborating centres in conducting such education and training activities in the relevant official languages of the IAEA. A technical meeting was held in Vienna in March 2002 and concluded with an action plan for implementing the strategy up to 2010, the immediate action being the formation of a Steering Committee by the middle of 2002. This Steering Committee has the general remit to advise on the development and implementation of the strategy, as well as monitoring its progress. The first technical meeting of the Steering Committee took place on 25

  1. Current activities of safety improvements at Ukrainian NPPs

    The basic idea leading the program of safety improvements at Ukrainian NPPs is further development of nuclear power required to ensure at least 40% of country's energy supply. Activities concerning safety improvements of Ukrainian NPPs involved four reactor types: WWER-1000 (V-5) large series, WWER-1000 (V-302, V-338) small series, WWER-400 (V-213) and RBMK (second generation). Most significant safety improvements covered reactor core integrity, reactor components and cooling systems integrity, instrumentation and control system, power supply, internal hazards. Additional measures related to WWER-440 were concerned with feedwater supply, instrumentation and control systems, and containment. Improvements related to Chernobylsk NPP unit 3 involved supervision, control and protection systems; safety assessment and supporting systems; fire safety. The role of quality assurance and training is emphasised when operational safety is concerned. Planned safety upgrading measures are mentioned

  2. Inherent failure modes of passive safety systems

    The paper discusses inherent failure modes of passive safety systems and their influence on passive system reliability. With 'inherent failures' means a failure of the system to perform its intended function due to physical reasons and/or phenomena. Such phenomena may occur inside the system, or be due to an external cause. Focus will be on passive cooling or heat removal systems that rely on natural circulation or stored pressure energy. The paper discusses the physical mechanisms due to which system malfunctions can arise, gives examples of phenomenological analyses for several model systems that are typical to proposed advanced passive reactors, discusses various external influences that may cause system malfunctions (drawing insights from operational experience of current plants), and concludes with a discussion of the relevance of such phenomena regarding the reliability of passive safety systems. This work shows that the reliability of passive systems can be strongly influenced by external factors, although comprehensive quantification of external disturbance frequencies is not yet available. Passive safety systems use natural circulation and stored pressure energy as power sources. These power sources have small capacities, which cause their sensitiveness to internal and external physical and thermodynamic conditions. The major advantage of passive safety system is their independence of external power sources and human factors. In this paper inherent failures of passive safety systems were discussed. There are two main types of these failures. Those failures are a failure due to unexpected internal change of physical state and a failure due to environment of the system, e.g. foreign material. When dealing with passive safety systems the environment of these systems plays bigger role compared to active systems. Thorough development, verification and review testing of passive systems should be considered including the environment and surrounding systems. This

  3. CERN Safety System Monitoring - SSM

    Hakulinen, T; Valentini, F; Gonzalez, J; Salatko-Petryszcze, C

    2011-01-01

    CERN SSM (Safety System Monitoring) [1] is a system for monitoring state-of-health of the various access and safety systems of the CERN site and accelerator infrastructure. The emphasis of SSM is on the needs of maintenance and system operation with the aim of providing an independent and reliable verification path of the basic operational parameters of each system. Included are all network-connected devices, such as PLCs, servers, panel displays, operator posts, etc. The basic monitoring engine of SSM is a freely available system-monitoring framework Zabbix [2], on top of which a simplified traffic-light-type web-interface has been built. The web-interface of SSM is designed to be ultra-light to facilitate access from handheld devices over slow connections. The underlying Zabbix system offers history and notification mechanisms typical of advanced monitoring systems.

  4. CERN safety system monitoring - SSM

    CERN SSM (Safety System Monitoring) is a system for monitoring state-of-health of the various access and safety systems of the CERN site and accelerator infrastructure. The emphasis of SSM is on the needs of maintenance and system operation with the aim of providing an independent and reliable verification path of the basic operational parameters of each system. Included are all network-connected devices, such as PLCs (local purpose control unit), servers, panel displays, operator posts, etc. The basic monitoring engine of SSM is a freely available system-monitoring framework Zabbix, on top of which a simplified traffic-light-type web-interface has been built. The web-interface of SSM is designed to be ultra-light to facilitate access from hand-held devices over slow connections. The underlying Zabbix system offers history and notification mechanisms typical of advanced monitoring systems. (authors)

  5. Lightning Safety and Outdoor Sports Activities

    ... Services Contact Us Glossary Lightning Safety and Outdoor Sports Activities I t’s a common situation — a thunderstorm ... associated with outdoor recreational activities. Officials responsible for sports outdoor activities need to understand thunderstorms and lightning ...

  6. Safety of mechanical devices. Safety of automation systems

    The paper deals with the classic procedures of safety engineering in the sectors mechanical engineering, electrical and energy engineering, construction and transport, medicine technology and process technology. Particular stress is laid on the safety of automation systems, control technology, protection of mechanical devices, reactor safety, mechanical constructions, transport systems, railway signalling devices, road traffic and protection at work in chemical plans. (DG)

  7. IAEA activities on education and training in radiation and waste safety: Strategic approach for a sustainable system

    The statutory safety functions of the International Atomic Energy Agency (IAEA) include the establishment of and provision for the application of safety standards for protection of health, life and property against ionizing radiation. The safety standards are based on the presumption that a national infrastructure is in place enabling the Government to discharge its responsibilities for protection and safety. Education and training is an essential element of the infrastructure. The IAEA education and training activities follows the resolutions of its General Conferences and reflects the latest IAEA standards and guidance. Several General Conference resolutions have emphasized the importance of education and training [e.g. GC(XXXV)/RES/552 in 1991; GC(XXXVI)/RES/584 in 1992; GC(43)/RES/13 in 1999 and more recently GC(44)/RES/13 in 2000]. In response to GC(44)/RES/13, the IAEA prepared a 'Strategic Approach to Education and Training in Radiation and Waste Safety' (Strategy on Education and Training) aiming at establishing, by 2010, sustainable education and training programmes in Member States. This Strategy was endorsed by the General Conference resolution GC(45)/RES/10C that, inter alia, urged the Secretariat to implement the Strategy on Education and Training, and to continue to strengthen, subject to available resources, its current effort in this area, and in particular to assist Member States' national, regional and collaborating centres in conducting such education and training activities in the relevant official languages of the IAEA. A technical meeting was organized in Vienna in March 2002 to advise on the implementation of the strategy. The meeting concluded with an action plan for implementing the strategy up to 2010, the immediate action being the formation of a Steering Committee by the middle of 2002. This Steering Committee would have the general remit to advise on the development and implementation of the strategy, as well as monitoring its progress

  8. Regulatory activities in reactor safety

    The safety phylosophy in designs and operation of nuclear power plants and, the steps for evaluating the safety and quality assurance, in the licensing procedure are described. The CNEN organization structure and the licensing procedure for nuclear power plants in Brazil are presented. (M.C.K.)

  9. Safety design guide for safety related systems for CANDU 9

    Lee, Duk Su; Chang, Woo Hyun; Lee, Nam Young [Korea Atomic Energy Research Institute, Daeduk (Korea, Republic of); Wright, A.C.D. [Atomic Energy of Canada Ltd., Toronto (Canada)

    1996-03-01

    In general, two types of safety related systems and structures exist in the nuclear plant; The one is a systems and structures which perform safety functions during the normal operation of the plant, and the other is a systems and structures which perform safety functions to mitigate events caused by failure of the normally operating systems or by naturally occurring phenomena. In this safety design guide, these systems are identified in detail, and the major events for which the safety functions are required and the major safety requirements are identified in the list. As the probabilistic safety assessments are completed during the course of the project, additions or deletions to the list may be justified. 3 tabs. (Author) .new.

  10. The LHC personnel safety system

    Large particle physics installations such as the CERN Large Hadron Collider require specific Personnel Safety Systems (PSS) to protect the personnel against the radiological and industrial hazards. In order to fulfill the French regulation in matter of nuclear installations, the principles of IEC 61508 and IEC 61513 standard are used as a methodology framework to evaluate the criticality of the installation, to design and to implement the PSS.The LHC PSS deals with the implementation of all physical barriers, access controls and interlock devices around the 27 km of underground tunnel, service zones and experimental caverns of the LHC. The system shall guarantee the absence of personnel in the LHC controlled areas during the machine operations and, on the other hand, ensure the automatic accelerator shutdown in case of any safety condition violation, such as an intrusion during beam circulation. The LHC PSS has been conceived as two separate and independent systems: the LHC Access Control System (LACS) and the LHC Access Safety System (LASS). The LACS, using off the shelf technologies, realizes all physical barriers and regulates all accesses to the underground areas by identifying users and checking their authorizations.The LASS has been designed according to the principles of the IEC 61508 and 61513 standards, starting from a risk analysis conducted on the LHC facility equipped with a standard access control system. It consists in a set of safety functions realized by a dedicated fail-safe and redundant hardware guaranteed to be of SIL3 class. The integration of various technologies combining electronics, sensors, video and operational procedures adopted to establish an efficient personnel safety system for the CERN LHC accelerator is presented in this paper. (authors)

  11. System safety education focused on industrial engineering

    Johnston, W. L.; Morris, R. S.

    1971-01-01

    An educational program, designed to train students with the specific skills needed to become safety specialists, is described. The discussion concentrates on application, selection, and utilization of various system safety analytical approaches. Emphasis is also placed on the management of a system safety program, its relationship with other disciplines, and new developments and applications of system safety techniques.

  12. ATMX System Safety Assessment report

    During the course of the ATMX System Safety Assessment (SSA) activity, it was determined that the ATMX structural integrity would be severely impaired technically unacceptable, a major redirection of the SSA effort involving structural modifications was outlined. The redirected effort culminated into four modifications three of which are structural in nature and the fourth is thermal modification. The first structural modification involves strengthening the ATMX hatch covers with 60 tension bolts and stiffening the same with tubular cross bracings. The second modification involves attaching a 3/16 inch plate to bulkhead at the end to prevent intrusion of triangular end frame into cargo compartment. The third modification involves welding the inner side plate to the cast steel underframe. The fourth and the final modification involves thermal insulation of ATMX. The thermal analysis of ATMX indicates that without any insulation, the shell, fiberboard, dunnage bags, and waste boxes and drums will reach temperatures well above the decomposition temperatures of fiberboard and waste products. We have reviewed the QA/QC and fracture testing plans submitted by RFP Rocky Flats Plant and generally agree with their plans. We have noted few exceptions in the QA/QC plans; we have also suggested an alternate fracture testing plan. 10 figs., 3 tabs

  13. Firefighter Safety for PV Systems

    Mathe, Laszlo; Sera, Dezso; Spataru, Sergiu;

    2015-01-01

    An important and highly discussed safety issue for photovoltaic (PV) systems is that as long as the PV panels are illuminated, a high voltage is present at the PV string terminals and cables between the string and inverters that is independent of the state of the inverter's dc disconnection switc....... The presence of these energized conductors on the dc side of the PV system can pose a danger to anyone performing maintenance or firefighting....

  14. IAEA activities on education and training in radiation and waste safety: Strategic approach for a sustainable system

    The IAEA education and training activities follow the resolutions of its General Conferences and reflect the latest IAEA standards and guidance. Several General Conference Resolutions have emphasized the importance of education and training. In response to General Conference Resolution GC(44)/RES/13, the IAEA prepared a Strategic Approach to Education and Training in Radiation and Waste Safety (Strategy on Education and Training) aiming at establishing, by 2010, sustainable education and training programmes in Member States. This strategy was endorsed by General Conference Resolution GC(45)/RES/10C that, inter alia, urged the Secretariat to implement the Strategy on Education and Training, and to continue to strengthen, subject to available resources, its current effort in this area, and in particular to assist Member States' national, regional and collaborating centres in conducting such education and training activities in the relevant official languages of the IAEA. A technical meeting was organized in Vienna in March 2002 to advise on the implementation of the strategy. The meeting concluded with an action plan for implementing the strategy up to 2010, the immediate action being the formation of a steering committee by the middle of 2002. The steering committee would have the general remit to advise on the development and implementation of the strategy, as well as monitoring its progress. In the 2002 General Conference, the IAEA was urged to continue to implement the strategy, including the convening of the steering committee. The first Steering Committee Meeting took place 25-29 November 2002. The paper presents the IAEA's past experience and the newly established Strategic Approach to Education and Training in Radiation and Waste Safety. (author)

  15. An Autonomous Flight Safety System

    Bull, James B.; Lanzi, Raymond J.

    2007-01-01

    The Autonomous Flight Safety System (AFSS) being developed by NASA s Goddard Space Flight Center s Wallops Flight Facility and Kennedy Space Center has completed two successful developmental flights and is preparing for a third. AFSS has been demonstrated to be a viable architecture for implementation of a completely vehicle based system capable of protecting life and property in event of an errant vehicle by terminating the flight or initiating other actions. It is capable of replacing current human-in-the-loop systems or acting in parallel with them. AFSS is configured prior to flight in accordance with a specific rule set agreed upon by the range safety authority and the user to protect the public and assure mission success. This paper discusses the motivation for the project, describes the method of development, and presents an overview of the evolving architecture and the current status.

  16. Nuclear power systems: Their safety

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

  17. Recent Activities on Global Nuclear Safety Regime

    Recently, rapid progress on the globalization of the nuclear safety issues is being made in IAEA (International Atomic Energy Agency) and its member states. With the globalization, the need for international cooperation among international bodies and member states continues to grow for resolving these universal nuclear safety issues. Furthermore, the importance of strengthening the global nuclear safety regime is emphasized through various means, such as efforts in application of IAEA safety standards to all nuclear installations in the world and in strengthening the code of conduct and the convention on nuclear safety. In this regards, it is important for us to keep up with the activities related with the global nuclear safety regime as an IAEA member state and a leading country in nuclear safety regulation

  18. Radiation safety systems at the NSLS

    This report describes design principles that were used to establish the radiation safety systems at the National Synchrotron Light Source. The author described existing safety systems and the history of partial system failures. 1 fig

  19. Safety Assessment for Facilities and Activities. General Safety Requirements

    This publication describes the generally applicable requirements to be fulfilled in safety assessments for facilities and activities, with special attention paid to defence in depth, quantitative analyses and the application of a graded approach to the ranges of facilities and of activities that are addressed. The requirements provide a consistent and coherent basis for safety assessments, facilitating the transfer of good practices between organizations. A review of Safety Requirements publications was commenced in 2011 following the accident in the Fukushima Daiichi nuclear power plant in Japan. The review revealed no significant areas of weakness and resulted in just a small set of amendments to strengthen the requirements and facilitate their implementation, which are contained in the present publication

  20. The ATLAS Detector Safety System

    Helfried Burckhart; Kathy Pommes; Heidi Sandaker

    The ATLAS Detector Safety System (DSS) has the mandate to put the detector in a safe state in case an abnormal situation arises which could be potentially dangerous for the detector. It covers the CERN alarm severity levels 1 and 2, which address serious risks for the equipment. The highest level 3, which also includes danger for persons, is the responsibility of the CERN-wide system CSAM, which always triggers an intervention by the CERN fire brigade. DSS works independently from and hence complements the Detector Control System, which is the tool to operate the experiment. The DSS is organized in a Front- End (FE), which fulfills autonomously the safety functions and a Back-End (BE) for interaction and configuration. The overall layout is shown in the picture below. ATLAS DSS configuration The FE implementation is based on a redundant Programmable Logical Crate (PLC) system which is used also in industry for such safety applications. Each of the two PLCs alone, one located underground and one at the s...

  1. Active gated imaging for automotive safety applications

    Grauer, Yoav; Sonn, Ezri

    2015-03-01

    The paper presents the Active Gated Imaging System (AGIS), in relation to the automotive field. AGIS is based on a fast gated-camera equipped with a unique Gated-CMOS sensor, and a pulsed Illuminator, synchronized in the time domain to record images of a certain range of interest which are then processed by computer vision real-time algorithms. In recent years we have learned the system parameters which are most beneficial to night-time driving in terms of; field of view, illumination profile, resolution and processing power. AGIS provides also day-time imaging with additional capabilities, which enhances computer vision safety applications. AGIS provides an excellent candidate for camera-based Advanced Driver Assistance Systems (ADAS) and the path for autonomous driving, in the future, based on its outstanding low/high light-level, harsh weather conditions capabilities and 3D potential growth capabilities.

  2. Role of computers in CANDU safety systems

    Small digital computers are playing an expanding role in the safety systems of CANDU nuclear generating stations, both as active components in the trip logic, and as monitoring and testing systems. The paper describes three recent applications: (i) A programmable controller was retro-fitted to Bruce ''A'' Nuclear Generating Station to handle trip setpoint modification as a function of booster rod insertion. (ii) A centralized monitoring computer to monitor both shutdown systems and the Emergency Coolant Injection system, is currently being retro-fitted to Bruce ''A''. (iii) The implementation of process trips on the CANDU 600 design using microcomputers. While not truly a retrofit, this feature was added very late in the design cycle to increase the margin against spurious trips, and has now seen about 4 unit-years of service at three separate sites. Committed future applications of computers in special safety systems are also described. (author)

  3. An Integrated Safety Assessment Methodology for Generation IV Nuclear Systems

    Timothy J. Leahy

    2010-06-01

    The Generation IV International Forum (GIF) Risk and Safety Working Group (RSWG) was created to develop an effective approach for the safety of Generation IV advanced nuclear energy systems. Early work of the RSWG focused on defining a safety philosophy founded on lessons learned from current and prior generations of nuclear technologies, and on identifying technology characteristics that may help achieve Generation IV safety goals. More recent RSWG work has focused on the definition of an integrated safety assessment methodology for evaluating the safety of Generation IV systems. The methodology, tentatively called ISAM, is an integrated “toolkit” consisting of analytical techniques that are available and matched to appropriate stages of Generation IV system concept development. The integrated methodology is intended to yield safety-related insights that help actively drive the evolving design throughout the technology development cycle, potentially resulting in enhanced safety, reduced costs, and shortened development time.

  4. Safety system of reactor container

    The safety system of the present invention can shut down a BWR type reactor safely without operator's aid even upon occurrence of an abnormal state. Namely, a pressure/temperature measuring and controlling device is disposed to a dry well in the safety system of a reactor container incorporating a pressure vessel, a space between a dry wall and a wet well and a pressure suppression chamber. Operation signals sent from pipelines of an emergency reactor core cooling system delivered from the pressure vessel are inputted to the pressure/temperature measuring and controlling device. Output signals of the pressure/temperature measuring and controlling device are inputted to a spray device. With such procedures, when actuation of dry well spray is required upon loss of coolants accident, necessity for the actuation of the spray can be judged based on the pressure, temperature in the dry well, reactor water level and a state of operation and duration of abnormal state of other ECCS system using the pressure/temperature measuring and controlling device disposed in the dry well. If actuation of spray is required, the dry wall spray is automatically actuated to reduce pressure and temperature in the container. (I.S.)

  5. ILO activities in the area of chemical safety.

    Obadia, Isaac

    2003-08-21

    The ILO has been active in the area of safety in the use of chemicals at work since the year of its creation in 1919, including the development of international treaties and other technical instruments, the provision of technical assistance to its member States, and the development of chemical safety information systems. The two key ILO standards in this area are the Conventions on safety in the use of chemicals at work (No. 170, 1990), and the Prevention of Major Industrial Accidents (No. 174, 1993). The ILO Programme on occupational safety, health and environment (Safe Work) is currently responsible for ILO chemical safety activities. In the past two decades, most of ILO work in this area has been carried out within the context of inter-agency collaboration frameworks linking the ILO, WHO, UNEP, FAO, UNIDO, UNITAR, and the OECD, including the International Programme on Chemical Safety (IPCS), the Inter-Organisation Programme for the Sound Management of Chemicals (IOMC), and the Intergovernmental Forum on Chemical Safety (IFCS). Apart from the regular development, updating and dissemination of chemical safety information data bases such as the IPCS International Chemical Cards, the elaboration of a Globally harmonized system for the classification and labelling of Chemicals (GHS) has been the most outstanding achievement of this international collaboration on chemical safety. PMID:12909402

  6. Preliminary safety evaluation for CSR1000 with passive safety system

    Highlights: • The basic information of a Chinese SCWR concept CSR1000 is introduced. • An innovative passive safety system is proposed for CSR1000. • 6 Transients and 3 accidents are analysed with system code SCTRAN. • The passive safety systems greatly mitigate the consequences of these incidents. • The inherent safety of CSR1000 is enhanced. - Abstract: This paper describes the preliminary safety analysis of the Chinese Supercritical water cooled Reactor (CSR1000), which is proposed by Nuclear Power Institute of China (NPIC). The two-pass core design applied to CSR1000 decreases the fuel cladding temperature and flattens the power distribution of the core at normal operation condition. Each fuel assembly is made up of four sub-assemblies with downward-flow water rods, which is favorable to the core cooling during abnormal conditions due to the large water inventory of the water rods. Additionally, a passive safety system is proposed for CSR1000 to increase the safety reliability at abnormal conditions. In this paper, accidents of “pump seizure”, “loss of coolant flow accidents (LOFA)”, “core depressurization”, as well as some typical transients are analysed with code SCTRAN, which is a one-dimensional safety analysis code for SCWRs. The results indicate that the maximum cladding surface temperatures (MCST), which is the most important safety criterion, of the both passes in the mentioned incidents are all below the safety criterion by a large margin. The sensitivity analyses of the delay time of RCPs trip in “loss of offsite power” and the delay time of RMT actuation in “loss of coolant flowrate” were also included in this paper. The analyses have shown that the core design of CSR1000 is feasible and the proposed passive safety system is capable of mitigating the consequences of the selected abnormalities

  7. Scientific Opinion on the safety assessment of the active substances, sodium erythorbate, sodium carbonate, sodium bicarbonate, iron sulphate, activated carbon, cellulose, calcium hydroxide, calcium chloride and water, for use as active system in food contact materials

    EFSA Panel on Food Contact Materials, Enzymes, Flavourings and Processing Aids (CEF

    2014-02-01

    Full Text Available This scientific opinion of EFSA Panel on Food Contact Materials, Enzymes, Flavourings and Processing Aids deals with the safety assessment of the active substances sodium erythorbate, sodium carbonate, sodium bicarbonate, iron sulfate, activated carbon, cellulose, calcium hydroxide, calcium chloride and water, used in mixture which is packed into sachets for absorbing oxygen/carbon dioxide emitting from/into the headspace surrounding packed food. All substances of this formulation have been evaluated and approved for use as additives in plastic food contact materials or as food additives. No migration of calcium, iron and sodium ions was detected. No volatile organic compounds other than carbon dioxide were detected at the limit of detection of 0.5 μg/l. The CEF Panel concluded that the use of the substances sodium erythorbate, sodium carbonate, sodium bicarbonate, iron sulfate, activated carbon, cellulose, calcium hydroxide, calcium chloride and water does not raise a safety concern when used in oxygen absorber/carbon dioxide emitter systems, in sachets that prevent the physical release of their contents into the food. The sachets are to be placed in the headspace of the packaging and as such may come into occasional contact with the food, e.g. during handling. The sachet should not come into direct contact with liquid foods or foods that have and external aqueous liquid phase on the surface (liquid or exudates.

  8. IAEA activities in the field of research reactors safety

    IAEA activities in the field of research reactor safety are included in the programme of the Division of Nuclear Installations Safety. Following the objectives of the Division, the results of the IAEA missions and the recommendations from International Advisory Groups, the IAEA has conducted in recent years a certain number of activities aiming to enhance the safety of research reactors. The following activities will be presented: (a) the new Requirements for the Safety of Research Reactors, main features and differences with previous standards (SS-35-S1 and SS-35-S2) and the grading approach for implementation; (b) new documents being developed (safety guides, safety reports and TECDOC's); (c) activities related to the Incident Reporting System for Research Reactor (IRSRR); (d) the new features implemented for the INSARR missions; (e) the Code of Conduct on the Safety of Research Reactors adopted by the Board of Governors on 8 March 2004, following the General Conference Resolution GC(45)/RES/10; and (f) the survey on the safety of research reactors published on the IAEA website on February 2003 and the results obtained. (author)

  9. System safety assessment by maintenance indicator

    The Maintenance Indicator was applied to evaluate the safety of nuclear power plants. A method was proposed to evaluate the reliability for 'a function' required for the system safety from the viewpoint of maintenance. (author)

  10. Progress report: 1996 Radiation Safety Systems Division

    The activities of Radiation Safety Systems Division include (i) development of specialised monitoring systems and radiation safety information network, (ii) radiation hazards control at the nuclear fuel cycle facilities, the radioisotope programmes at Bhabha Atomic Research Centre (BARC) and for the accelerators programme at BARC and Centre for Advanced Technology (CAT), Indore. The systems on which development and upgradation work was carried out during the year included aerial gamma spectrometer, automated environment monitor using railway network, radioisotope package monitor and air monitors for tritium and alpha active aerosols. Other R and D efforts at the division included assessment of risk for radiation exposures and evaluation of ICRP 60 recommendations in the Indian context, shielding evaluation and dosimetry for the new upcoming accelerator facilities and solid state nuclear track detector techniques for neutron measurements. The expertise of the divisional members was provided for 36 safety committees of BARC and Atomic Energy Regulatory Board (AERB). Twenty three publications were brought out during the year 1996. (author)

  11. FOOD SAFETY CONTROL SYSTEM IN CHINA

    Liu Wei-jun; Wei Yi-min; Han Jun; Luo Dan; Pan Jia-rong

    2007-01-01

    Most countries have expended much effort to develop food safety control systems to ensure safe food supplies within their borders. China, as one of the world's largest food producers and consumers,pays a lot of attention to food safety issues. In recent years, China has taken actions and implemented a series of plans in respect to food safety. Food safety control systems including regulatory, supervisory,and science and technology systems, have begun to be established in China. Using, as a base, an analysis of the current Chinese food safety control system as measured against international standards, this paper discusses the need for China to standardize its food safety control system. We then suggest some policies and measures to improve the Chinese food safety control system.

  12. Safety Trigger Conditions for Critical Autonomous Systems

    Mekki-Mokhtar, Amina; Blanquart, Jean-Paul; Guiochet, Jérémie; Powell, David; Roy, Matthieu

    2012-01-01

    International audience A systematic process for eliciting safety trigger conditions is presented. Starting from a risk analysis of the monitored system, critical transitions to catastrophic system states are identified and handled in order to specify safety margins on them. The conditions for existence of such safety margins are given and an alternative solution is proposed if no safety margin can be defined. The proposed process is illustrated on a robotic rollator.

  13. Advancement on safety management system of nuclear power for safety and non-anxiety of society

    Advancement on safety management system is investigated to improve safety and non-anxiety of society for nuclear power, from the standpoint of human machine system research. First, the recent progress of R and D works of human machine interface technologies since 1980 s are reviewed and then the necessity of introducing a new approach to promote technical risk communication activity to foster safety culture in nuclear industries. Finally, a new concept of Offsite Operation and Maintenance Support Center (OMSC) is proposed as the core facility to assemble human resources and their expertise in all organizations of nuclear power, for enhancing safety and non-anxiety of society for nuclear power. (author)

  14. System Design and the Safety Basis

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

  15. Intermediate probabilistic safety assessment approach for safety critical digital systems

    Even though the conventional probabilistic safety assessment methods are immature for applying to microprocessor-based digital systems, practical needs force to apply it. In the Korea, UCN 5 and 6 units are being constructed and Korean Next Generation Reactor is being designed using the digital instrumentation and control equipment for the safety related functions. Korean regulatory body requires probabilistic safety assessment. This paper analyzes the difficulties on the assessment of digital systems and suggests an intermediate framework for evaluating their safety using fault tree models. The framework deals with several important characteristics of digital systems including software modules and fault-tolerant features. We expect that the analysis result will provide valuable design feedback. (authors)

  16. Intermediate probabilistic safety assessment approach for safety critical digital systems

    Taeyong, Sung; Hyun Gook, Kang [Korea Atomic Energy Research Inst., Integrated Safety Assessment Team, Taejon (Korea, Republic of)

    2001-07-01

    Even though the conventional probabilistic safety assessment methods are immature for applying to microprocessor-based digital systems, practical needs force to apply it. In the Korea, UCN 5 and 6 units are being constructed and Korean Next Generation Reactor is being designed using the digital instrumentation and control equipment for the safety related functions. Korean regulatory body requires probabilistic safety assessment. This paper analyzes the difficulties on the assessment of digital systems and suggests an intermediate framework for evaluating their safety using fault tree models. The framework deals with several important characteristics of digital systems including software modules and fault-tolerant features. We expect that the analysis result will provide valuable design feedback. (authors)

  17. Activities performed within the program of nuclear safety research on structural and cladding materials for innovative reactor system able to transmute nuclear waste

    The transmutation of nuclear waste to reduce the burden on a geological repository is a relevant topic within the Program of Nuclear Safety Research of the Research Centre Karlsruhe. Several studies have confirmed that a high efficiency of transmutation of actinides is reached in fast neutron spectrum reactor system. Therefore, an important effort is dedicated to the study of transmutation strategies with different fast reactors and their associated technologies. Moreover, in international contexts as Generation IV International Forum (GIF) and Sustainable Nuclear Energy Technology Platform (SNETP), fast reactors are considered in the frame of sustainable development of nuclear energy and reduction of waste. The systems that are currently under investigation, in the frame of the different fuel cycle scenarios, are liquid metal cooled and gas cooled fast reactors as well as Accelerator Driven Sub-critical Transmutation devices (ADS). These innovative reactor systems, call for structural and clad materials, which are able to perform in a safe manner under the envisaged operational and postulated transient conditions. In this context the European Commission supports the FP7 project GETMAT, with the objective to contribute to the development and selection of reference structure materials for core components and primary systems of fast neutron reactors. Several institutes of the Research Centre Karlsruhe are involved in this project with activities in the area of 9Cr ODS steel development and mechanical characterisation; optimisation and ranking of weld and joining techniques as Electron Beam, TIG and Diffusion Bonding; assessment of materials behaviour in corrosive environment and in neutron and neutron/proton irradiation field; and development of corrosion protection barriers for cladding and primary system components and their characterisation. The objective of this contribution is to describe the context in which the GETMAT activities are embedded in the Program

  18. Digital control systems for nuclear criticality safety

    Nuclear fuel cycle facilities, like much of the nuclear industry, are increasingly relying on digital instrumentation and control (DI and C) systems such as programmable logic controllers (PLCs) to maintain system variables for both production and safety purposes. Fuel cycle manufacturing processes are increasingly automated and relying on active engineered controls. Compliance with the double contingency principle requires that DI and C trains credited for criticality safety are independent. The additional requirements imposed as part of performing an Integrated Safety Analysis (ISA) in accordance with Title 10 of the Code of Federal Regulations (10 CFR) Part 70, Subpart H, mean that such DI and C systems must meet more stringent requirements than would otherwise be required to meet industry standards. This paper discusses the current status of the U.S. Nuclear Regulatory Commission's (NRC's) Digital I and C Working Group, and the requirements that would be imposed on such systems are a result of having to comply with the double contingency principle and the performance requirements of 10 CFR 70.61. Existing applicable NRC Interim Staff Guidance is summarized, and several case studies from ISA technical reviews are presented. (authors)

  19. Safety design requirements for safety systems and components of JSFR

    Safety design requirements for JSFR were summarized taking the development targets of FaCT project and design feature of JSFR into account. The related safety principle and requirements for Monju, CRBRP, PRISM, SPX, LWRs, IAEA standards, goals of GIF and basic principle of INPRO etc. were also taken into account so that the safety design requirements can be a next-generation global-standard. The development targets for safety and reliability are set based on that of FaCT. Namely, ensuring safety and reliability equal to future LWR and related fuel cycle facilities. In order to achieve these targets, the defence-in-depth philosophy is used as the basic safety design principle. General features of the safety design requirements are 1) Achievement of higher reliability, 2) Achievement of higher inspectability and maintainability, 3) Introduction of passive safety features, 4) Reduction of operator action needs, 5) Design consideration against Beyond Design Basis Events, 6) In Vessel Retention of degraded core materials, 7) Prevention and mitigation against sodium chemical reactions, 8) Design against external events. Current specific requirements for the each system and component are summarized taking the basic design concept of JSFR into account, which is an advanced loop type large output power plant with mixed oxide fuelled core. (author)

  20. 30 CFR 285.811 - When must I follow my Safety Management System?

    2010-07-01

    ... 30 Mineral Resources 2 2010-07-01 2010-07-01 false When must I follow my Safety Management System..., COPs and GAPs Safety Management Systems § 285.811 When must I follow my Safety Management System? Your Safety Management System must be fully functional when you begin activities described in your...

  1. Convoy Active Safety Technologies Warfighter Experiment I

    Schoenherr, Edward; Theisen, Bernard L.; Animashaun, Asisat; Davis, James, Jr.; Day, Christopher

    2008-04-01

    The operational ability to project and sustain forces in distant, anti-access and area denial environments poses new challenges for combatant commanders. One of the new challenges is the ability to conduct sustainment operations at operationally feasible times and places on the battlefield. Combatant commanders require a sustainment system that is agile, versatile, and survivable throughout the range of military operations and across the spectrum of conflict. A key component of conducting responsive, operationally feasible sustainment operations is the ability to conduct sustainment convoys. Sustainment convoys are critical to providing combatant commanders the right support, at the right time and place, and in the right quantities, across the full range of military operations. The ability to conduct sustainment convoys in a variety of hostile environments require force protection measures that address the enemy threat and protect the Soldier. One cost effective, technically feasible method of increasing the force protection for sustainment convoys is the use of robotic follower technology and autonomous navigation. The Convoy Active Safety Technologies (CAST) system is a driver assist, convoy autopilot technology aimed to address these issues. Warfigher Experiment I, held at A.P. Hill, VA in the fall of 2007, tested the utility of this vehicle following technology not only in measures of system integrity and performance vs. manual driving, but also the physiological effects on the operators themselves. This paper will detail the Warfigher Experiment's methodology, analysis, results and conclusions.

  2. Probabilistic safety criteria at the safety function/system level

    A Technical Committee Meeting was held in Vienna, Austria, from 26-30 January 1987. The objectives of the meeting were: to review the national developments of PSC at the level of safety functions/systems including future trends; to analyse basic principles, assumptions, and objectives; to compare numerical values and the rationale for choosing them; to compile the experience with use of such PSC; to analyse the role of uncertainties in particular regarding procedures for showing compliance. The general objective of establishing PSC at the level of safety functions/systems is to provide a pragmatic tool to evaluate plant safety which is placing emphasis on the prevention principle. Such criteria could thus lead to a better understanding of the importance to safety of the various functions which have to be performed to ensure the safety of the plant, and the engineering means of performing these functions. They would reflect the state-of-the-art in modern PSAs and could contribute to a balance in system design. This report, prepared by the participants of the meeting, reviews the current status and future trends in the field and should assist Member States in developing their national approaches. The draft of this document was also submitted to INSAG to be considered in its work to prepare a document on safety principles for nuclear power plants. Five papers presented at the meeting are also included in this publication. A separate abstract was prepared for each of these papers. Refs, figs and tabs

  3. A philosophy for space nuclear systems safety

    The unique requirements and contraints of space nuclear systems require careful consideration in the development of a safety policy. The Nuclear Safety Policy Working Group (NSPWG) for the Space Exploration Initiative has proposed a hierarchical approach with safety policy at the top of the hierarchy. This policy allows safety requirements to be tailored to specific applications while still providing reassurance to regulators and the general public that the necessary measures have been taken to assure safe application of space nuclear systems. The safety policy used by the NSPWG is recommended for all space nuclear programs and missions

  4. Obtaining Food Safety by Applying HACCP System

    ION CRIVEANU; NATALIŢA MARIA SPERDEA; RADU CATALIN CRIVEANU

    2012-01-01

    In order to increase the confidence of the trading partners and consumers in the products which are sold on the market, enterprises producing food are required to implement the food safety system HACCP,a particularly useful system because the manufacturer is not able to fully control finished products . SR EN ISO 22000:2005 establishes requirements for a food safety management system where an organization in the food chain needs to proove its ability to control food safety hazards in order to...

  5. Safety Verification for Probabilistic Hybrid Systems

    Zhang, Lijun; She, Zhikun; Ratschan, Stefan;

    2010-01-01

    The interplay of random phenomena and continuous real-time control deserves increased attention for instance in wireless sensing and control applications. Safety verification for such systems thus needs to consider probabilistic variations of systems with hybrid dynamics. In safety verification of...... hybrid systems and develop a general abstraction technique for verifying probabilistic safety problems. This gives rise to the first mechanisable technique that can, in practice, formally verify safety properties of non-trivial continuous-time stochastic hybrid systems-without resorting to point...... number of case studies, tackled using a prototypical implementation....

  6. Automation for System Safety Analysis

    Malin, Jane T.; Fleming, Land; Throop, David; Thronesbery, Carroll; Flores, Joshua; Bennett, Ted; Wennberg, Paul

    2009-01-01

    This presentation describes work to integrate a set of tools to support early model-based analysis of failures and hazards due to system-software interactions. The tools perform and assist analysts in the following tasks: 1) extract model parts from text for architecture and safety/hazard models; 2) combine the parts with library information to develop the models for visualization and analysis; 3) perform graph analysis and simulation to identify and evaluate possible paths from hazard sources to vulnerable entities and functions, in nominal and anomalous system-software configurations and scenarios; and 4) identify resulting candidate scenarios for software integration testing. There has been significant technical progress in model extraction from Orion program text sources, architecture model derivation (components and connections) and documentation of extraction sources. Models have been derived from Internal Interface Requirements Documents (IIRDs) and FMEA documents. Linguistic text processing is used to extract model parts and relationships, and the Aerospace Ontology also aids automated model development from the extracted information. Visualizations of these models assist analysts in requirements overview and in checking consistency and completeness.

  7. Report of safety of the characterizing system of radioactive waste

    Report of safety of the system of radioactive waste of the ININ: Installation, participant personnel, selection of the place, description of the installation, equipment. Proposed activities: operations with radioactive material, calibration in energy, calibration in efficiency, types of waste. Maintenance: handling of radioactive waste, physical safety. Organization: radiological protection, armor-plating, personal dosemeter, risks and emergency plan, environmental impact, medical exams. (Author)

  8. Fasten seat belts: Do car safety systems cause positive externalities?

    Michael Berlemann; Andreas Matthes

    2011-01-01

    Although traffic safety belongs to the quite intensively regulated sectors, there has been little discussion about the adequacy of the arguments underlying these regulations. We argue that passive and active car safety systems might cause positive externalities for other traffic participants and present empirical evidence in favour of this hypothesis.

  9. Qualification of safety-critical software for digital reactor safety system in nuclear power plants

    This paper describes the software qualification activities for the safety-critical software of the digital reactor safety system in nuclear power plants. The main activities of the software qualification processes are the preparation of software planning documentations, verification and validation (V and V) of the software requirements specifications (SRS), software design specifications (SDS) and codes, and the testing of the integrated software and integrated system. Moreover, the software safety analysis and software configuration management are involved in the software qualification processes. The V and V procedure for SRS and SDS contains a technical evaluation, licensing suitability evaluation, inspection and traceability analysis, formal verification, software safety analysis, and an evaluation of the software configuration management. The V and V processes for the code are a traceability analysis, source code inspection, test case and test procedure generation. Testing is the major V and V activity of the software integration and system integration phases. The software safety analysis employs a hazard operability method and software fault tree analysis. The software configuration management in each software life cycle is performed by the use of a nuclear software configuration management tool. Through these activities, we can achieve the functionality, performance, reliability, and safety that are the major V and V objectives of the safety-critical software in nuclear power plants. (author)

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

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

    2011-01-01

    unrtainties represents a method of probabilistic thinking wherein the analyst and decision makers recognize possible outcomes other than the outcome perceived to be "most likely." Without this type of analysis, it is not possible to determine the worth of an analysis product as a basis for making decisions related to safety and mission success. In line with these considerations the handbook does not take a hazard-analysis-centric approach to system safety. Hazard analysis remains a useful tool to facilitate brainstorming but does not substitute for a more holistic approach geared to a comprehensive identification and understanding of individual risk issues and their contributions to aggregate safety risks. The handbook strives to emphasize the importance of identifying the most critical scenarios that contribute to the risk of not meeting the agreed-upon safety objectives and requirements using all appropriate tools (including but not limited to hazard analysis). Thereafter, emphasis shifts to identifying the risk drivers that cause these scenarios to be critical and ensuring that there are controls directed toward preventing or mitigating the risk drivers. To address these and other areas, the handbook advocates a proactive, analytic-deliberative, risk-informed approach to system safety, enabling the integration of system safety activities with systems engineering and risk management processes. It emphasizes how one can systematically provide the necessary evidence to substantiate the claim that a system is safe to within an acceptable risk tolerance, and that safety has been achieved in a cost-effective manner. The methodology discussed in this handbook is part of a systems engineering process and is intended to be integral to the system safety practices being conducted by the NASA safety and mission assurance and systems engineering organizations. The handbook posits that to conclude that a system is adequately safe, it is necessary to consider a set of safety claims that

  11. Airline Safety Management: The development of a proactive safety mechanism model for the evolution of safety management system

    Hsu, Yueh-Ling

    2004-01-01

    The systemic origins of many accidents have led to heightened interest in the way in which organisations identify and manage risks within the airline industry. The activities which are thought to represent the term "organisational accident", "safety culture" and "proactive approach" are documented and seek to explain the fact that airlines differ in their willingness and ability to conduct safety management. However, an important but yet relatively undefined task in the airline...

  12. Communication and Networking Techniques for Traffic Safety Systems

    Chisalita, Ioan

    2006-01-01

    Accident statistics indicate that every year a significant number of casualties and extensive property losses occur due to traffic accidents. Consequently, efforts are directed towards developing passive and active safety systems that help reduce the severity of crashes, or prevent vehicles from colliding with one another. To develop these systems, technologies such as sensor systems, computer vision and vehicular communication have been proposed. Safety vehicular communication is defined as ...

  13. Ergonomics in the context of system safety

    In a complex industrial environment, ergonomics must be combined with management science and systems analysis to produce a program which can create effective change and improve safety performance. We give an overview of such an approach, namely System Safety, so that its ergonomic content may be seen

  14. 76 FR 14592 - Safety Management System; Withdrawal

    2011-03-17

    ..., and 145 RIN 2120-AJ15 Safety Management System; Withdrawal AGENCY: Federal Aviation Administration... (``product/ service providers'') to develop a Safety Management System (SMS). The FAA is withdrawing the... proposed rulemaking (ANPRM) published on July 23, 2009 (74 FR 36414) is withdrawn as of March 17, 2011....

  15. Recommendations for the LHC safety alarm system

    Laeger, H

    1999-01-01

    A working group was set up to define the LHC safety alarm system, also known as Alarm-of-Level-3-System (AL3S). The mandate asked for recommendations to be elaborated on four items: the overall concept of the AL3S for machine and experiments, the transmission and display of safety alarms, the AL3S during civil engineering construction, and the transition from the present LEP to the final LHC safety alarm system. The members of the working group represented a wide range of interest and experience including the CERN Fire Brigade, safety officers from experiments and machines, and specialists for safety and control systems. The recommendations highlight the need for a clear definition of responsibilities and procedures, well-engineered homogeneous systems across CERN, and they point to several important issues outside the mandate of the working group. These recommendations were presented, discussed and accepted by several CERN and LHC committees.

  16. Computer system reliability safety and usability

    Dhillon, BS

    2013-01-01

    Computer systems have become an important element of the world economy, with billions of dollars spent each year on development, manufacture, operation, and maintenance. Combining coverage of computer system reliability, safety, usability, and other related topics into a single volume, Computer System Reliability: Safety and Usability eliminates the need to consult many different and diverse sources in the hunt for the information required to design better computer systems.After presenting introductory aspects of computer system reliability such as safety, usability-related facts and figures,

  17. Risk communication activities toward nuclear safety in Tokai: your safety is our safety

    As several decades have passed since the construction of nuclear power plants began, residents have become gradually less interested in nuclear safety. The Tokai criticality accident in 1909, however, had roused residents in Tokai-Mura to realize that they live with nuclear technology risks. To prepare a field of risk communication, the Tokai-Mura C3 project began as a pilot research project supported by NISA. Alter the project ended, we are continuing risk. communication activities as a non-profit organisation. The most important activity of C3 project is the citizen's inspection programme for nuclear related facilities. This programme was decided by participants who voluntarily applied to the project. The concept of the citizen's inspection programme is 'not the usual facility tours'. Participants are involved from the planning stage and continue to communicate with workers of the inspected nuclear facility. Since 2003, we have conducted six programmes for five nuclear related organisations. Participants evaluated that radiation protection measures were near good but there were some problems concerning the worker's safety and safety culture, and proposed a mixture of advice based on personal experience. Some advice was accepted and it did improve the facility's safety measures. Other suggestions were not agreed upon by nuclear organisations. The reason lies in the difference of concept between the nuclear expert's 'safety' and the citizen's 'safety'. Residents do not worry about radiation only, but also about the facility's safety as a whole including the worker's safety. They say, 'If the workers are not safe, you also are unable to protect us'. Although the disagreement remained, the participants and the nuclear industry learned much about each other. Participating citizens received a substantial amount of knowledge about the nuclear industry and its safety measures, and feel the credibility and openness of the nuclear industry. On the other hand, the nuclear

  18. Safety design requirements for safety systems and components of JSFR

    As a part of the conceptual design for Japan sodium-cooled fast reactor (JSFR), safety design requirements of JSFR is now being established in collaboration with JAEA, JAPC and MFBR. The basic safety approach is based on the development targets of a fast reactor cycle technology development (FaCT) project, i.e., the deterministic design approach based on the defense-in-depth philosophy, in which prevention and mitigation against BDBEs are considered as well as against DBEs, is supported by the probabilistic evaluations. In order to embody a safety design, a higher level safety principle was broken down into a set of design requirements for each safety related system, structure and component (SSC). This paper will present an output of the safety requirements for safety related SSCs of JSFR. In the course of this study, related safety principle and requirements for Monju, CRBRP, PRISM, SPX, LWRs, IAEA standards, development targets of FaCT project, goals of GIF and basic principle of INPRO etc. were taken into account to develop a next-generation global-standard safety requirements. It is stressed that preventive and mitigative measures against BDBEs shall be considered from early design stage. The attached figure shows outline of the safety requirements. The systems and components to be studied are divided: (1)core and fuel, (2) reactor vessel and its internal structures, (3) primary coolant system, (4) intermediate coolant system, (5) decay heat removal system, (6) reactor shutdown and reactivity control systems, (7)safety protection system, instrumentation and control systems, (8) electric power system, (9) fuel handling system, (10) steam and power conversion systems, (11) containment system and reactor building, (12) auxiliary systems. These requirements can also be categorized into some levels. Although the lower level expresses design requirements specific for JSFR, the higher level can be commonly applied to sodium cooled fast reactors. This paper will

  19. Safety Stock versus Safety Time in MRP Controlled Production Systems

    J. A. Buzacott; Shanthikumar, J. G.

    1994-01-01

    The two management set parameters which determine the performance of a material requirements planning (MRP) system are the lead time and the safety stock. The appropriate values of these parameters are influenced by the accuracy of forecasts over the lead time, the variability of processing time and the degree of congestion, together with the costs of inventory and shortages. These influences are explored using stochastic models of a single stage manufacturing system for which work release is...

  20. OBTAINING FOOD SAFETY BY APPLYING HACCP SYSTEM

    ION CRIVEANU

    2012-01-01

    Full Text Available In order to increase the confidence of the trading partners and consumers in the products which are sold on the market, enterprises producing food are required to implement the food safety system HACCP,a particularly useful system because the manufacturer is not able to fully control finished products . SR EN ISO 22000:2005 establishes requirements for a food safety management system where an organization in the food chain needs to proove its ability to control food safety hazards in order to ensure that food is safe at the time of human consumption. This paper presents the main steps which ensure food safety using the HACCP system, and SR EN ISO 20000:2005 requirements for food safety.

  1. Synthesized safety analysis of fusion system

    General Methodology of Safety Analysis and Evaluation for Fusion Energy System (GEMSAFE) was applied to the International Thermonuclear Experimental Reactor (ITER) interim design in the Engineering Design Activities (EDA) stage to identify the candidates of the Design Basis Events (DBEs) stage. These DBEs were compared with those of the ITER design in the Conceptual Design Activities (EDA). As a result, 18 candidates of DBEs were selected for EDA interim design in comparison with 25 DBE candidates for the CDA design. The DBE candidates related to the fuel area were categorized in higher event categories than those of the CDA design due to the increase of the mobile tritium-contained in some components. It is important to reduce the inventory of the tritium absorbed in the dust in the vacuum area as well as in the CDA design. Measures were recommended to reduce the mobile tritium dissolved in the coolant in the single loop due to the increase of this estimated inventory. (author)

  2. System safety management: A new discipline

    Pope, W. C.

    1971-01-01

    The systems theory is discussed in relation to safety management. It is suggested that systems safety management, as a new discipline, holds great promise for reducing operating errors, conserving labor resources, avoiding operating costs due to mistakes, and for improving managerial techniques. It is pointed out that managerial failures or system breakdowns are the basic reasons for human errors and condition defects. In this respect, a recommendation is made that safety engineers stop visualizing the problem only with the individual (supervisor or employee) and see the problem from the systems point of view.

  3. Adoption of digital safety protection system in Japan

    The application of micro-processor-based digital controllers has been widely propagated among various industries in recent years. While in the nuclear power plant industry, the application of them has also been expanding gradually starting from non-safety related systems, taking advantage of their reliability and maintainability over the conventional analog devices. Based on the careful study of the feasibility of digital controllers to the safety protection system, the Tokyo Electric Power Company proposed on May 1989 the adoption of digital controllers to the safety protection system in the Application for Permission of Establishment of Kashiwazaki-Kariwa units 6 and 7 (ABWR-1350Mwe each). MITI, Ministry of International Trade and Industry, the Japanese regulatory body for electric power generating facilities, had approved this application after careful review. This paper describes a series of supporting activities leading to the MITI's approval of the digital safety protection system and the MITI's licensing activities. (author)

  4. Software reliability and safety in nuclear reactor protection systems

    Planning the development, use and regulation of computer systems in nuclear reactor protection systems in such a way as to enhance reliability and safety is a complex issue. This report is one of a series of reports from the Computer Safety and Reliability Group, Lawrence Livermore that investigates different aspects of computer software in reactor National Laboratory, that investigates different aspects of computer software in reactor protection systems. There are two central themes in the report, First, software considerations cannot be fully understood in isolation from computer hardware and application considerations. Second, the process of engineering reliability and safety into a computer system requires activities to be carried out throughout the software life cycle. The report discusses the many activities that can be carried out during the software life cycle to improve the safety and reliability of the resulting product. The viewpoint is primarily that of the assessor, or auditor

  5. Software reliability and safety in nuclear reactor protection systems

    Lawrence, J.D. [Lawrence Livermore National Lab., CA (United States)

    1993-11-01

    Planning the development, use and regulation of computer systems in nuclear reactor protection systems in such a way as to enhance reliability and safety is a complex issue. This report is one of a series of reports from the Computer Safety and Reliability Group, Lawrence Livermore that investigates different aspects of computer software in reactor National Laboratory, that investigates different aspects of computer software in reactor protection systems. There are two central themes in the report, First, software considerations cannot be fully understood in isolation from computer hardware and application considerations. Second, the process of engineering reliability and safety into a computer system requires activities to be carried out throughout the software life cycle. The report discusses the many activities that can be carried out during the software life cycle to improve the safety and reliability of the resulting product. The viewpoint is primarily that of the assessor, or auditor.

  6. Safety features of subcritical fluid fueled systems

    Bell, C.R. [Los Alamos National Lab., NM (United States). Technology and Safety Assessment Div.

    1994-09-01

    Accelerator-driven transmutation technology has been under study at Los Alamos for several years for application to nuclear waste treatment, tritium production, energy generation, and recently, to the disposition of excess weapons plutonium. Studies and evaluations performed to date at Los Alamos have led to a current focus on a fluid-fuel, fission system operating in a neutron source-supported subcritical mode, using molten salt reactor technology and accelerator-driven proton-neutron spallation. In this paper, the safety features and characteristics of such systems are explored from the perspective of the fundamental nuclear safety objectives that any reactor-type system should address. This exploration is qualitative in nature and uses current vintage solid-fueled reactors as a baseline for comparison. Based on the safety perspectives presented, such systems should be capable of meeting the fundamental nuclear safety objectives. In addition, they should be able to provide the safety robustness desired for advanced reactors. However, the manner in which safety objectives and robustness are achieved in very different from that associated with conventional reactors. Also, there are a number of safety design and operational challenges that will have to be addressed for the safety potential of such systems to be credible.

  7. Wireless information and safety system for mines

    L.K. Bandyopadhyay; S.K. Chaulya; P.K. Mishra; A. Choure; B.M. Baveja [Central Institute of Mining and Fuel Research (CIMFR), Dhanbad (India)

    2009-02-15

    This study presents a wireless information and safety system for mines developed by CIMFR, Dhanbad. The system consists of hardware devices and application software. Hardware module is ZigBee-compliant active radio frequency identification (RFID) devices transceivers, which can be programmed to act as an end device (tag), router or coordinator that enables them to form an IEEE 802.15.4-based mesh network. It uses a unified wireless mesh-networking infrastructure to locate, trace and manage mobile assets and people as well as monitor different environmental conditions using sensors. Another core module is wireless sensor network (WSN) software, which is developed for tracking of underground miners and moveable equipment by wireless sensor networking in mines. Software is especially designed for tracking of miners and vehicles, route tracking in opencast mines, preventing fatal accidents and vehicle collisions, environmental monitoring, observing miners' unsafe practice, sending alert message, and preparing computerized miners' duty hours record.

  8. LOFT integral test system final safety analysis report

    Safety analyses are presented for the following LOFT Reactor systems: engineering safety features; support buildings and facilities; instrumentation and controls; electrical systems; and auxiliary systems. (JWR)

  9. Integrating system safety into the basic systems engineering process

    Griswold, J. W.

    1971-01-01

    The basic elements of a systems engineering process are given along with a detailed description of what the safety system requires from the systems engineering process. Also discussed is the safety that the system provides to other subfunctions of systems engineering.

  10. IAEA activities in nuclear safety: future perspectives. Spanish Nuclear Safety Council, Madrid, 28 May 1998

    The document represents the conference given by the Director General of the IAEA at the Spanish Nuclear Safety Council in Madrid, on 28 May 1998, on Agency's activities in nuclear safety. The following aspects are emphasized: Agency's role in creating a legally binding nuclear safety regime, non-binding safety standards, services provided by the Agency to assist its Member States in the Application of safety standards, Agency's nuclear safety strategy, and future perspective concerning safety aspects related to radioactive wastes, residues of past nuclear activities, and security of radiological sources

  11. Safety Verification for Probabilistic Hybrid Systems

    Zhang, Lijun; She, Zhikun; Ratschan, Stefan;

    2012-01-01

    The interplay of random phenomena and continuous dynamics deserves increased attention, especially in the context of wireless sensing and control applications. Safety verification for such systems thus needs to consider probabilistic variants of systems with hybrid dynamics. In safety verification...... probabilistic hybrid systems and develop a general abstraction technique for verifying probabilistic safety problems. This gives rise to the first mechanisable technique that can, in practice, formally verify safety properties of non-trivial continuous-time stochastic hybrid systems. Moreover, being based on...... abstractions computed by tools for the analysis of non-probabilistic hybrid systems, improvements in effectivity of such tools directly carry over to improvements in effectivity of the technique we describe. We demonstrate the applicability of our approach on a number of case studies, tackled using a...

  12. Aviation Safety Reporting System: Process and Procedures

    Connell, Linda J.

    1997-01-01

    The Aviation Safety Reporting System (ASRS) was established in 1976 under an agreement between the Federal Aviation Administration (FAA) and the National Aeronautics and Space Administration (NASA). This cooperative safety program invites pilots, air traffic controllers, flight attendants, maintenance personnel, and others to voluntarily report to NASA any aviation incident or safety hazard. The FAA provides most of the program funding. NASA administers the program, sets its policies in consultation with the FAA and aviation community, and receives the reports submitted to the program. The FAA offers those who use the ASRS program two important reporting guarantees: confidentiality and limited immunity. Reports sent to ASRS are held in strict confidence. More than 350,000 reports have been submitted since the program's beginning without a single reporter's identity being revealed. ASRS removes all personal names and other potentially identifying information before entering reports into its database. This system is a very successful, proof-of-concept for gathering safety data in order to provide timely information about safety issues. The ASRS information is crucial to aviation safety efforts both nationally and internationally. It can be utilized as the first step in safety by providing the direction and content to informed policies, procedures, and research, especially human factors. The ASRS process and procedures will be presented as one model of safety reporting feedback systems.

  13. Safety aspect of digital reactor protection system in Japan

    It was early in 1980's that the digital controllers were first applied to nuclear power plant in japan. After that, their application area had been expanding gradually, reaching to the overall integrated digital system including the safety system in Kashiwazaki-Kariwa units 6 and 7. The software for computer-based systems has been produced using the graphical language ''POL'' in Japanese nuclear power plants. It is the fundamental principle that the reliability of the software should be assured through the properly managed quality assurance. The POL-based system is fitted to this principle. In applying POL-based systems to safety system, the MITI, Ministry of International Trade and Industry, identified the licensing issues as the regulatory body, while the utilities had developed the digital technology feasible to the safety application. Through the activities, a specific industrial design guide for the software important to safety was established and the adequacy of the technology was certified through the demonstration tests of the integrated system. In the safety examination of the digital reactor protection system of K-6/7, the application of POL were approved. The POL-based systems in nuclear power plants were successful design and production process of the POL-based systems. This paper describes the activities in licensing and maintaining the computer-based systems by the utilities and manufacturers as well as the MITI. (author)

  14. Proactive Management of Aviation System Safety Risk

    National Aeronautics and Space Administration — Aviation safety systems have undergone dramatic changes over the past fifty years. If you take a look at the early technology in this area, you'll see that there...

  15. International Atomic Energy Agency Activities on Education and Training in Radiation, Transport and Waste Safety: Strategic Approach for a Sustainable System

    The statutory safety functions of the international Atomic Energy Agency (IAEA) include the establishment of and provision for the application of safety standards for protection of health, life and property against ionizing radiation. The safety standards are based on the presumption that a national infrastructure is in place enabling the government to discharge its responsibilities for protection and safety. Education and training is an essential element of the infrastructure. The IAEA education and training activities follows the the resolutions of its general conferences and reflects the latest IAEA standards and guidance. several general conference resolutions have emphasized the importance of education and training (e.g. GC (XXXV)/RES/552 in 1991,GC (XXXVI)/ RES/584 in 1992, GC (43)/RES/13 in 1999 and more recently GC (44)/RES/13 in 2000). In response to GC (44) /RES/13, the IAEA prepared a strategic approach to education and training in radiation and waste safety (strategy on education and training) aiming at establishing, by 2010 sustainable education and training programmes in member states. This strategy was endorsed by the general conference resolution GC(45)/RES/10C that, inter alia, urged the secretariat to implement the strategy on education and training, and to continue to strengthen, subject to available resources, its current effort in this area, and in particular to assist Member States national, regional and collaborating centres in conducting such education and training activities in the relevant official languages of the IAEA. The General Conference resolutions GC(46)RES/9C in 2002 and GC(47)RES/7 in 2003 urged the Agency to continue its efforts to implement the Strategy. The purpose of this paper is to present the newly established Strategic Approach to Education and Training in Radiation, Transport and Waste Safety and its implementation

  16. ''Piloni'' - Safety Management System at Soreq

    'Piloni' is a computer program developed at the Safety Division of NRC Soreq. It is designed to update, manage and save all the data related to the safety of the employees, devices, laboratories, facilities and the environment on a single unified system. The system is currently being used and tested at the Safety Division. It had been written in Access 2002 but has been tested and modified to work on workstations in which Access 2003 is installed. The program is built modularly so that additions, updates and extensions can be carried out conveniently

  17. CLASSIFICATION OF THE MGR HEALTH SAFETY SYSTEM

    The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) health safety system structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333P, ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998)

  18. Database management systems for process safety

    Several elements of the process safety management regulation (PSM) require tracking and documentation of actions; process hazard analyses, management of change, process safety information, operating procedures, training, contractor safety programs, pre-startup safety reviews, incident investigations, emergency planning, and compliance audits. These elements can result in hundreds of actions annually that require actions. This tracking and documentation commonly is a failing identified in compliance audits, and is difficult to manage through action lists, spreadsheets, or other tools that are comfortably manipulated by plant personnel. This paper discusses the recent implementation of a database management system at a chemical plant and chronicles the improvements accomplished through the introduction of a customized system. The system as implemented modeled the normal plant workflows, and provided simple, recognizable user interfaces for ease of use

  19. A management system integrating radiation protection and safety supporting safety culture in the hospital

    Quality assurance has been identified as an important part of radiation protection and safety for a considerable time period. A rational expansion and improvement of quality assurance is to integrate radiation protection and safety in a management system. The aim of this study was to explore factors influencing the implementing strategy when introducing a management system including radiation protection and safety in hospitals and to outline benefits of such a system. The main experience from developing a management system is that it is possible to create a vast number of common policies and routines for the whole hospital, resulting in a cost-efficient system. One of the key benefits is the involvement of management at all levels, including the hospital director. Furthermore, a transparent system will involve staff throughout the organisation as well. A management system supports a common view on what should be done, who should do it and how the activities are reviewed. An integrated management system for radiation protection and safety includes key elements supporting a safety culture. (authors)

  20. System for controlling child safety seat environment

    Dabney, Richard W. (Inventor); Elrod, Susan V. (Inventor)

    2008-01-01

    A system is provided to control the environment experienced by a child in a child safety seat. Each of a plurality of thermoelectric elements is individually controllable to be one of heated and cooled relative to an ambient temperature. A first portion of the thermoelectric elements are positioned on the child safety seat such that a child sitting therein is positioned thereover. A ventilator coupled to the child safety seat moves air past a second portion of the thermoelectric elements and filters the air moved therepast. One or more jets coupled to the ventilator receive the filtered air. Each jet is coupled to the child safety seat and can be positioned to direct the heated/cooled filtered air to the vicinity of the head of the child sitting in the child safety seat.

  1. Diagnosis operational safety of a transport system

    Maciej WOROPAY

    2009-01-01

    Full Text Available The transport systems are sociotechnical systems in which the direct realization of the tasks is dealt with by an executive subsystem consisting of the elementary subsystems of a human – a technical object (an operator – a means of transport type realizing the tasks within the system environment. In respect of a human located within a transport system the most significant criterion in the evaluation of transport being realized is their safety.The safety level of the task realization is influenced by the risks resulting from the interaction of the forcing factors, affecting an elementary executive subsystem.These factors may be divided into [8]:-working;-external;-antropotechnical.Due to the complexity of the systems being analysed in the paper, it has been attempted to evaluate the influence of the forcing factors on the safety of this system operation.

  2. Safety and interlock system for Tristan

    This report describes alarm and interlock system of TRISTAN, concentrating on personnel safety. The basis of TRISTAN machine-control system (TMS) is an N-to-N computer network and KEK NODAL which offers high software productivity. TMC achieves high flexibility of operation both for normal operation and for the fast commissioning. However, to assure the safety of personnel and the TRISTAN machine operation, the safety system has to continue functioning during TMC failure as well. A distributed safety and interlock system (DSIS) is used for diversification of risks in TRISTAN system. DSIS is functionally subdivided along local system lines and has a hierarchical structure of 12 programmable sequence controllers (PSCs). Optical fiber links connect the PSCs at subsystem level and a PSC at the supervisory level of TRISTAN central control room (TCCR). The subsystem PSCs provide the interlock functions between their local devices. The local PSCs interact with the central system through a limited number of summarized signals. The central PSC provides the interlock functions between the subsystems and interacts with an operator's panel. Personnel safety is based on a system of electrical interlock keys, emergency push-buttons around the tunnel, at the entrance gates or in the control room

  3. Safety of emerging nuclear energy systems

    The first stage of world nuclear power development based on light water fission reactors has demonstrated not only rather high rate but at the same time too optimistic attitude to safety problems. Large accidents at Three Mile Island and Chernobyl essentially affects the concept of NP development. As a result the safety and social acceptance of NP became of absolute priority among other problems. That's why emerging nuclear power systems should be first of all estimated from this point of view. In the paper some quantitative criteria of safety derived from estimations of social risk and economic-ecological damage from hypothetical accidents are formulated. On the base of these criteria we define two stages of possible way to meet safety demands: first--development of high safety fission reactors and second--that of asymptotic high safety ENEs. The limits of tolorated expenses for safety are regarded. The basis physical factors determining hazards of NES accidents are considered. This permits to classify the ways of safety demands fulfillment due to physical principals used

  4. Classification of Aeronautics System Health and Safety Documents

    National Aeronautics and Space Administration — Most complex aerospace systems have many text reports on safety, maintenance, and associated issues. The Aviation Safety Reporting System (ASRS) spans several...

  5. K West integrated water treatment system subproject safety analysis document

    This Accident Analysis evaluates unmitigated accident scenarios, and identifies Safety Significant and Safety Class structures, systems, and components for the K West Integrated Water Treatment System

  6. K West integrated water treatment system subproject safety analysis document

    SEMMENS, L.S.

    1999-02-24

    This Accident Analysis evaluates unmitigated accident scenarios, and identifies Safety Significant and Safety Class structures, systems, and components for the K West Integrated Water Treatment System.

  7. SNS Accelerator Facility Target Safety and Non-Safety Control Systems

    The SNS is a proton accelerator facility that generates neutrons for scientific researchers by spallation of neutrons from a mercury target. The SNS became operational on April 28, 2006 with first beam on target at approximately 200 watts. The SNS accelerator, target, and conventional facilities controls are integrated by standardized hardware and software throughout the facility and were designed and fabricated to SNS conventions to ensure compatibility of systems with Experimental Physics Integrated Control System (EPICS). ControlLogix PLCs interface to instruments and actuators, and EPICS performs the high-level integration of the PLCs such that all operator control can be accomplished from the Central Control room using EPICS graphical screens that pass process variables to and from the PLCs. Three active safety systems were designed to industry standards ISA S84.01 and IEEE 603 to meet the desired reliability for these safety systems. The safety systems protect facility workers and the environment from mercury vapor, mercury radiation, and proton beam radiation. The facility operators operated many of the systems prior to beam on target and developed the operating procedures. The safety and non-safety control systems were tested extensively prior to beam on target. This testing was crucial to identify wiring and software errors and failed components, the result of which was few problems during operation with beam on target. The SNS has continued beam on target since April to increase beam power, check out the scientific instruments, and continue testing the operation of facility subsystems

  8. System Safety in an IT Service Organization

    Parsons, Mike; Scutt, Simon

    Within Logica UK, over 30 IT service projects are considered safetyrelated. These include operational IT services for airports, railway infrastructure asset management, nationwide radiation monitoring and hospital medical records services. A recent internal audit examined the processes and documents used to manage system safety on these services and made a series of recommendations for improvement. This paper looks at the changes and the challenges to introducing them, especially where the service is provided by multiple units supporting both safety and non-safety related services from multiple locations around the world. The recommendations include improvements to service agreements, improved process definitions, routine safety assessment of changes, enhanced call logging, improved staff competency and training, and increased safety awareness. Progress is reported as of today, together with a road map for implementation of the improvements to the service safety management system. A proposal for service assurance levels (SALs) is discussed as a way forward to cover the wide variety of services and associated safety risks.

  9. Current status of safety design and safety analysis for China ITER helium coolant ceramic breeder test blanket system long

    Helium Coolant Ceramic Breeder (HCCB) Test Blanket System (TBS) designed by China are planned to be tested in ITER to validate key technologies, including demonstration of nuclear safety, for future fusion reactor breeding blankets. Furthermore, in order to be operated in ITER, a nuclear facility (INB) recognized by French nuclear safety authority, safety design and safety analysis of the TBS are mandatory for the licensing procedures. This paper summarizes the status at current design phase with following main elements: The main radiological source terms in the system are tritium and activation products. Nuclear and tritium analysis are performed to identify their inventories and distributions in system. Multiple confinement barriers are considered to be the most essential safety feature. French regulation for pressure equipment and nuclear equipment (ESP/ESPN regulations) will be followed to ensure the system integrities. ALARA principle is kept in mind during the whole safety design phases. Protective actions including choice of advanced materials, improvement of shielding, optimization of operation and maintenance activities, usage of remote handling operations, zoning and access control have been considered. Passive safety is emphasized in the system design, only minimal active safety functions including call for fusion plasma shutdown and isolation of TBM from ex-vessel ancillary systems. High reliability and redundancies are required for components related to these functions. Several accidents have been identified and analyzed. Consider the limited inventories in the system and the intrinsic safety of fusion device, positive conclusions have been obtained. (author)

  10. Hybrid SIT for Passive Safety System

    The injection pressure of the current SIT is about 4 MPa. Therefore, the SIT is not available during a high pressure SBLOCA or Station Black Out (SBO) accident because the RCS pressure is higher than that of the SIT. In addition, the AC-powered High Pressure Safety Injection (HPSI) System driven by an emergency diesel generator is not available during a SBO accident. However, as the RCS mass inventory is continuously decreased by releasing steam through the pressurizer safety valves after reactor trip, a high pressure safety injection is needed to mitigate the accident

  11. Hybrid SIT for Passive Safety System

    Kwon, Taesoon; Park, Choonkyung [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2013-05-15

    The injection pressure of the current SIT is about 4 MPa. Therefore, the SIT is not available during a high pressure SBLOCA or Station Black Out (SBO) accident because the RCS pressure is higher than that of the SIT. In addition, the AC-powered High Pressure Safety Injection (HPSI) System driven by an emergency diesel generator is not available during a SBO accident. However, as the RCS mass inventory is continuously decreased by releasing steam through the pressurizer safety valves after reactor trip, a high pressure safety injection is needed to mitigate the accident.

  12. Safety approach in the EU test blanket systems design

    Highlights: ► European Union (EU) Test Blanket Systems (TBS) safety objectives. ► EU TBS strategy. ► EU TBS project environment and status, risks and mitigations. ► EU TBS safety approach and its implementation. - Abstract: This paper reveals the safety strategy and approach developed and followed in the design of the two EU TBS describing its objectives, components and implementation. Addressing the safety in the early stage of the conceptual design of nuclear facilities is a well recognized international practice and industrial project-level requirement for the successful completion of the licensing process within expected project cost and schedule. The impact of the early development of the safety approach, its implementation and monitoring in the design of nuclear device like the TBS is not limited to the safety assessment and licensing activities only. Safety approach plays indispensible role in reducing the overall project risk. It infiltrates the entire design process through the unavoidable interfaces between the design features and its safety level. In reality the entire process of the TBS development, design, technological demonstration and implementation is affected by the project team safety culture.

  13. Risk based management of safety systems' availability

    The paper presents the results of Task 14 of the OECD/NEA Committee on the Safety of Nuclear Installations (CSNI) Principal Working Group 5. Following completion of work on 'PSA Application to Technical Specifications', Task 14 was initiated at the Autumn 1992 meeting of the Principal Working Group, and was completed at the end of 1994. The agreed objective of the task was to review the possibilities for using probabilistic safety analysis (PSA) based insights in the real time management of safety system reliability. The practicality of on-line risk based monitoring of safety systems' availability status has been demonstrated by seven years of experience at each of four nuclear power reactors in the United Kingdom. Within this experience many thousands of status changes have been monitored and evaluated. 4 refs, 3 figs

  14. Research reactor management. Safety improvement activities in HANARO

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

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

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

  16. Review of nuclear regulatory activities associated with safety culture and the management of safety in the United Kingdom

    This paper describes some of the key regulatory activities which have taken place in the United Kingdom in recent years in the areas of safety culture and management of safety. It explains how the UK's nuclear licensing regime, regulated and enforced by the Nuclear Installations Inspectorate, (NII), provides the framework for a viable safety management system and identifies a management of safety model which a NII Task Force has developed. It finally identifies further work which is being undertaken by the NII. (author). 4 refs, 2 figs

  17. Safety assessment of high consequence robotics system

    This paper outlines the use of a failure modes and effects analysis for the safety assessment of a robotic system being developed at Sandia National Laboratories. The robotic system, the weigh and leak check system, is to replace a manual process for weight and leakage of nuclear materials at the DOE Pantex facility. Failure modes and effects analyses were completed for the robotics process to ensure that safety goals for the systems have been met. Due to the flexible nature of the robot configuration, traditional failure modes and effects analysis (FMEA) were not applicable. In addition, the primary focus of safety assessments of robotics systems has been the protection of personnel in the immediate area. In this application, the safety analysis must account for the sensitivities of the payload as well as traditional issues. A unique variation on the classical FMEA was developed that permits an organized and quite effective tool to be used to assure that safety was adequately considered during the development of the robotic system. The fundamental aspects of the approach are outlined in the paper

  18. Safety effects of navigation systems.

    2009-01-01

    Increasing numbers of drivers are using navigation systems in their cars. The advantages to the user are obvious: you can get to your destination via the fastest and shortest route. This reduces stress and exposure to other traffic. However, there are also some (unintended) negative effects. For example, using the system while driving can distract your attention from other traffic. The system sometimes directs traffic through small centres of habitation or along unsuitable roads. Moreover, ti...

  19. SAFETY ANALYSIS OF THE DEMONSTRATION BULK VITRIFICATION SYSTEM

    The U.S. Department of Energy (DOE) and CH2M HILL, Hanford Group, Inc. (CH2M HILL) [also referred to as the Tank Farm Contractor (TFC)] are evaluating the Demonstration Bulk Vitrification System (DBVS) as a supplemental treatment technology for low-activity waste (LAW) at the Hanford Site. As a new facility at Hanford, the safety analysis for the DBVS is being subjected to new and evolving DOE requirements. Hazard categorization for the facility is being closely examined since this determines whether performance category (PC)-2 or PC-3 requirements are to be applied for natural phenomena hazards, as well as differing requirements under Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 2004-2, Active Confinement Systems. Questions have also arisen regarding application of DOE-STD-3009-94, Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses, or DOE-STD-1189-2008, Integration of Safety into the Design Process, format and content, as well as full implementation of DOE-STD-1186-2004, Specific Administrative Controls and naming conventions and content requirements for the interim safety analysis documents under DOE O 413.3A, Program and Project Management for the Acquisition of Capital Assets (e.g., Preliminary Documented Safety Analysis or Preliminary Safety Design Report). Another challenge is the integration of the programmatic chapters of the safety document with those of the Hanford tank farms, since the tank farms Safety Management Programs (SMP) are relied upon for the DBVS facility. All of these issues and their resolutions, as well as the level of scrutiny to which internal and external regulators have held this project's safety analysis, will be discussed in this paper

  20. Safety Problems of Small Water Supply Systems

    Tchórzewska-Cieślak Barbara

    2016-07-01

    Full Text Available The paper presents issues related to risks associated with the operation of small water supply systems on the background of water consumer safety assessment made on the basis of risk analysis. Definition of water consumer safety loss as a risk associated with the water consumption of poor quality or water lack was proposed. For this purpose, a three-parameter matrix is implemented with the parameters of the probability of a representative accident scenario, the losses of the water consumers and their protection. Risk management, together with the implementation of protective barriers of small water supply system against threats is a fundamental condition for the continued operation of the system.

  1. Building a safety case for a small sized product line of Fuel Level Display Systems

    Gallucci, Antonio

    2013-01-01

    ISO 26262 is an international standard valid for the automotive domain. It regulates all the activities to perform for developing safety critical systems in such domain. To be compliant with ISO 26262, all the required activities have to be performed and all the required work products have to be provided. Furthermore, in addition to develop a system in a safe way, following the safety standard guidelines, the achieved safety has also to be demonstrated. This is done through a safety case, a s...

  2. Integrated safety management system verification: Volume 2

    Christensen, R.F.

    1998-08-10

    Department of Energy (DOE) Policy (P) 450.4, Safety Management System Policy, commits to institutionalization of an Integrated Safety Management System (ISMS) throughout the DOE complex. The DOE Acquisition Regulations (DEAR, 48 CFR 970) requires contractors to manage and perform work in accordance with a documented Integrated Safety Management System (ISMS). Guidance and expectations have been provided to PNNL by incorporation into the operating contract (Contract DE-ACM-76FL0 1830) and by letter. The contract requires that the contractor submit a description of their ISMS for approval by DOE. PNNL submitted their proposed Safety Management System Description for approval on November 25,1997. RL tentatively approved acceptance of the description pursuant to a favorable recommendation from this review. The Integrated Safety Management System Verification is a review of the adequacy of the ISMS description in fulfilling the requirements of the DEAR and the DOE Policy. The purpose of this review is to provide the Richland Operations Office Manager with a recommendation for approval of the ISMS description of the Pacific Northwest Laboratory based upon compliance with the requirements of 49 CFR 970.5204(-2 and -78); and to verify the extent and maturity of ISMS implementation within the Laboratory. Further the review will provide a model for other DOE laboratories managed by the Office of Assistant Secretary for Energy Research.

  3. Constructing control safety systems that utilize a durable logic principle

    Full text of publication follows: Our report discusses the basic principles of producing control safety systems that utilize hardware complexes designed and developed by the Research and Production Corporation (RPC) 'Radiy', Ukraine. The safety systems produced by the company are based on a principle of 'tough' logic. Our presentation describes: - functions that are performed by CSS in nuclear power stations; - principles that are realized in the equipment of hardware complexes for control safety systems; - methods for addressing sub-system components; - integration of all components into one system. We will discuss how this system performs simultaneous functions. In addition we describe the realization of fundamental safety principles. Our presentation contains data that illustrates how our unique hardware design meets the national and international standards of radiation safety in the following cases: - one time system failures; - stand by redundancy; - multiple system failures. We provide examples of how our control safety system hardware functions as a part of power generation units in nuclear power stations as follows: - Technology protection and lockout: this controls the parameters of the nuclear reactor, monitors its status for deviations and initiates the appropriate actions; - Manual remote control: the choice of manual override of the command line options that are displayed on the block control panel; - Automatic control: automatic maintenance of nuclear reactor technological parameters in normal operational and emergency modes. Our hardware system performs these functions without utilizing software. The Program Technological Complexes (PTC) for Control Safety Systems (CSS) include several standard functions such as alarm transmission, activity databases, automatic diagnostics and many others. Special attention in our presentation is given to the issues of PTC CSS reliability in all types of emergencies. (authors)

  4. Upgrade of accelerator radiation safety system for SPring-8

    The accelerator safety interlock system to protect persons from the radiation damages has been operated in SPring-8. The accelerator safety interlock system is monitoring the condition of safety equipment. If the condition is unsafe, the system stops the electron beam. The accelerator safety interlock system currently running is based on the operation mode control. Since the operation mode based system is quite complex, the system has some problems. Therefore, we are planning to construct new accelerator safety interlock system. We'll report the situation of current accelerator safety interlock system and the conceptual design of new accelerator safety interlock system. (author)

  5. Expert systems and nuclear safety

    The US Nuclear Regulatory Commission (NRC) and the Electric Power Research Institute have initiated a broad-based exploration of means to evaluate the potential applications of expert systems in the nuclear industry. This exploratory effort will assess the use of expert systems to augment the diagnostic and decision-making capabilities of personnel with the goal of enhancing productivity, reliability, and performance. The initial research effort is the development and documentation of guidelines for verifying and validating (V and V) expert systems. An initial application of expert systems in the nuclear industry is to aid operations and maintenance personnel in decision-making tasks. The scope of the decision aiding covers all types of cognitive behavior consisting of skill, rule, and knowledge-based behavior. For example, procedure trackers were designed and tested to support rule-based behavior. Further, these systems automate many of the tedious, error-prone human monitoring tasks, thereby reducing the potential for human error. The paper version of the procedure contains the knowledge base and the rules and thus serves as the basis of the design verification of the procedure tracker. Person-in-the-loop tests serve as the basis for the validation of a procedure tracker. When conducting validation tests, it is important to ascertain that the human retains the locus of control in the use of the expert system

  6. Systems-theoretic Safety Assessment of Robotic Telesurgical Systems

    Alemzadeh, Homa; Chen, Daniel; Lewis, Andrew; Kalbarczyk, Zbigniew; Raman, Jaishankar; Leveson, Nancy; Iyer, Ravishankar K.

    2015-01-01

    Robotic telesurgical systems are one of the most complex medical cyber-physical systems on the market, and have been used in over 1.75 million procedures during the last decade. Despite significant improvements in design of robotic surgical systems through the years, there have been ongoing occurrences of safety incidents during procedures that negatively impact patients. This paper presents an approach for systems-theoretic safety assessment of robotic telesurgical systems using software-imp...

  7. The passive safety systems of the Swr 1000

    In recent years, a new boiling water reactor (BWR) plant called the SWR 1000 has been developed by Siemens on behalf of Germany's electric utilities. This new plant design concept incorporates the wide range of operating experience gained with German BWRs. The main objective behind developing the SWR 1000 was to design a plant with a rated electric output of approximately 1000 MW which would not only have a lower capital cost and lower power generating costs but would also provide a much higher level of nuclear safety compared to plants currently in operation. This safety-related goal has been met through, for example, the use of passive safety equipment. Passive systems make a significant contribution towards increasing the over-all level of plant safety due to the way in which they operate. They function solely accord-ing to basic laws of nature, such as gravity, and perform their designated functions with-out any need for electric power or other sources of external energy, or signals from instrumentation and control (I and C) equipment. The passive safety systems have been designed such that design basis accidents can be controlled using just these systems alone. However, the design concept of the SWR 1000 is nevertheless still based on the provision of active safety systems in addition to passive systems. (author)

  8. From Safe Systems to Patient Safety

    Aarts, J.; Nøhr, C.

    2010-01-01

    safety. The editors want to thank Marianne Sørensen, Aalborg University for keeping track of all the contributions and ensuring they found their way to the final proceedings. We also want to thank all the reviewers for their excellent work in providing constructive feedback to the authors. This valuable...... third conference with the theme: The ability to design, implement and evaluate safe, useable and effective systems within complex health care organizations. The theme for this conference was "Designing and Implementing Health IT: from safe systems to patient safety". The contributions have reflected on...... and implementation of safe systems and thus contribute to the agenda of patient safety? The contributions demonstrate how the health informatics community has contributed to the performance of significant research and to translating research findings to develop health care delivery and improve patient...

  9. Recent advances in systems safety and security

    Stamatescu, Grigore

    2016-01-01

    This book represents a timely overview of advances in systems safety and security, based on selected, revised and extended contributions from the 2nd and 3rd editions of the International Workshop on Systems Safety and Security – IWSSS, held in 2014 and 2015, respectively, in Bucharest, Romania. It includes 14 chapters, co-authored by 34 researchers from 7 countries. The book provides an useful reference from both theoretical and applied perspectives in what concerns recent progress in this area of critical interest. Contributions, broadly grouped by core topic, address challenges related to information theoretic methods for assuring systems safety and security, cloud-based solutions, image processing approaches, distributed sensor networks and legal or risk analysis viewpoints. These are mostly accompanied by associated case studies providing additional practical value and underlying the broad relevance and impact of the field.

  10. LOCA analysis of SCWR-M with passive safety system

    Liu, X.J., E-mail: xiaojingliu@sjtu.edu.cn [School of Nuclear Science and Engineering, Shanghai Jiao Tong University, 800 Dong Chuan Road, Shanghai 200240 (China); Fu, S.W. [Navy University of Engineering, Wuhan, Hubei (China); Xu, Z.H. [Shanghai Nuclear Engineering Research and Design Institute, Shanghai (China); Yang, Y.H. [School of Nuclear Science and Engineering, Shanghai Jiao Tong University, 800 Dong Chuan Road, Shanghai 200240 (China); Cheng, X. [Institute of Fusion and Nuclear Technology, Karlsruhe Institute of Technology (KIT), Kaiserstr. 12, 76131 Karlsruhe (Germany)

    2013-06-15

    Highlights: • Application of the ATHLET-SC code to the trans-critical analysis for SCWR. • Development of a passive safety system for SCWR-M. • Analysis of hot/cold leg LOCA behaviour with different break size. • Introduction of some mitigation measures for SCWR-M -- Abstract: A new SCWR conceptual design (mixed spectrum supercritical water cooled reactor: SCWR-M) is proposed by Shanghai Jiao Tong University (SJTU). R and D activities covering core design, safety system design and code development of SCWR-M are launched at SJTU. Safety system design and analysis is one of the key tasks during the development of SCWR-M. Considering the current advanced reactor design, a new passive safety system for SCWR-M including isolation cooling system (ICS), accumulator injection system (ACC), gravity driven cooling system (GDCS) and automatic depressurization system (ADS) is proposed. Based on the modified and preliminarily assessed system code ATHLET-SC, loss of coolant accident (LOCA) analysis for hot and cold leg is performed in this paper. Three different break sizes are analyzed to clarify the hot and cold LOCA characteristics of the SCWR-M. The influence of the break location and break size on the safety performance of SCWR-M is also concluded. Several measures to induce the core coolant flow and to mitigate core heating up are also discussed. The results achieved so far demonstrate the feasibility of the proposed passive safety system to keep the SCWR-M core at safety condition during loss of coolant accident.

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

    The criticality accident at the JCO plant prompted the Government to enact a law for nuclear emergency preparedness. The nuclear industry established NSnet to facilitate opportunities for peer review among its members. This paper describes the activities by NSnet and TEPCO's Kashiwazaki-Kariwa nuclear power station (NPS) for a better safety culture. Created as a voluntary organization by the nuclear industry in 1999, NSnet has 35 members and is assisted by CRIEPI and NUPEC for its activities relevant to human factors. Given the fact that nuclear facility operators not belonging to WANO had no institutional system available for exchange of experiences and good practices for better safety among themselves, NSnet's activities focus on peer review by member organizations and onsite seminars. Starting April 2000 with visits to three fuel fabricators, NSnet intends to have 23 peer-review visits in 2 yr (Ref. 1). The six-member review team stays on-site for 4 days, during which time they review-using guidelines available from WANO and IAEA-OSART-six areas: organization/management, emergency preparedness, education/training, operation/ maintenance, protection against occupational radiation exposure, and prevention of accidents. A series of on-site seminars is held at members' nuclear facilities, to which NSnet dispatches experts for lectures. NSnet plans to hold such seminars twice per month. Other activities include information-sharing through a newsletter, a Web site (www. nsnet.gr.jp), and others. Although considerable differences exist in the design and the practices in operation/maintenance between power reactors and JCO, utilities can extract lessons from the accident that will be worth consideration for their own facilities in the areas of safety culture, education and training, and interface between design and operation. This thinking prompted the Nuclear Safety Promotion Center at Kashiwazaki-Kariwa NPS, to which the author belonged at that time, to launch the

  12. Scientific Opinion on the safety assessment of the active substances iron powder, activated carbon, calcined kaolin, sodium chloride, polyacrylic acid, sodium salt, crosslinked and calcium chloride, for use as active system in food contact materials

    EFSA Panel on Food Contact Materials, Enzymes, Flavourings and Processing Aids (CEF

    2014-05-01

    Full Text Available This scientific opinion of the EFSA Panel on Food Contact Materials, Enzymes, Flavourings and Processing Aids deals with the safety assessment of the active substances iron powder, activated carbon, calcined kaolin, sodium chloride, polyacrylic acid, sodium salt, crosslinked and calcium chloride, used in mixture which is packed into labels, for absorbing oxygen from the headspace surrounding packed food. All substances of this formulation have been evaluated and approved for use as additives in plastic food contact materials or as food supplements. Migration of substances from the labels and formation and release of volatile constituents are not expected under the intended conditions of use. The CEF Panel concluded that the use of substances iron powder, activated carbon, calcined kaolin, sodium chloride, polyacrylic acid, sodium salt, crosslinked and calcium chloride does not raise a safety concern when used in oxygen absorbers in labels, which prevent the physical release of their content into the food. When placed in the headspace of the packaging or when used in direct contact with foods, the labels should not intentionally or unintentionally come into direct contact with liquid foods or foods that have an external aqueous phase on the surface such as sliced fruits.

  13. Mine Safety Detection System (MSDS)

    Ballard, B.; Degnan, T.; Kipp, M.; Johnson, J; Miller, D.; Minto, M.

    2012-01-01

    Systems Engineering Project Report Approved for public release, distribution unlimited The search, detection, identification and assessment components of the U.S. Navys organic modular in-stride Mine Countermeasure (MCM) Concept of Operations (CONOPS) have been evaluated for their effectiveness as part of a hypothetical exercise in response to the existence of sea mines placed in the sea lanes of the Strait of Hormuz. The current MCM CONOPS has been shown to be capable of supporting the...

  14. Addressing the fundamental issues in reliability evaluation of passive safety of AP1000 for a comparison with active safety of PWR

    Passive safety systems adopted in advanced Pressurized Water Reactor (PWR), such as AP1000 and EPR, should attain higher reliability than the existing active safety systems of the conventional PWR. The objective of this study is to discuss the fundamental issues relating to the reliability evaluation of AP1000 passive safety systems for a comparison with the active safety systems of conventional PWR, based on several aspects. First, comparisons between conventional PWR and AP1000 are made from the both aspects of safety design and cost reduction. The main differences between these PWR plants exist in the configurations of safety systems: AP1000 employs the passive safety system while reducing the number of active systems. Second, the safety of AP1000 is discussed from the aspect of severe accident prevention in the event of large break loss of coolant accidents (LOCA). Third, detailed fundamental issues on reliability evaluation of AP1000 passive safety systems are discussed qualitatively by using single loop models of safety systems of both PWRs plants. Lastly, methodology to conduct quantitative estimation of dynamic reliability for AP1000 passive safety systems in LOCA condition is discussed, in order to evaluate the reliability of AP1000 in future by a success-path-based reliability analysis method (i.e., GO-FLOW). (author)

  15. Development of the Digital Reactor Safety System

    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

  16. Safety analyse of cryptography protocol used within safety-related control systems in industry

    Franeková, Mária; Fedor KÁLLAY; Kurytnik, Igor Piotr

    2008-01-01

    In the paper the possibilities of solution safety communication within area of safety-related control industry system are summarised with using cryptography techniques. Requirements to safety are based on generic standard for functional safety of Electrical/Electronic/Programmable Electronic (E/E/PE) systems IEC 61508 and standards, which define safety and security profiles in industrial network used in measurement and control systems. In mainly part of paper the model of safe...

  17. Current activities on safety improvement at Ukrainian NPPs

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

  18. Software qualification for digital safety system in KNICS project

    In order to achieve technical self-reliance in the area of nuclear instrumentation and control, the Korea Nuclear Instrumentation and Control System (KNICS) project had been running for seven years from 2001. The safety-grade Programmable Logic Controller (PLC) and the digital safety system were developed by KNICS project. All the software of the PLC and digital safety system were developed and verified following the software development life cycle Verification and Validation (V and V) procedure. The main activities of the V and V process are preparation of software planning documentations, verification of the Software Requirement Specification (SRS), Software Design Specification (SDS) and codes, and a testing of the software components, the integrated software, and the integrated system. In addition, a software safety analysis and a software configuration management are included in the activities. For the software safety analysis at the SRS and SDS phases, the software Hazard Operability (HAZOP) was performed and then the software fault tree analysis was applied. The software fault tree analysis was applied to a part of software module with some critical defects identified by the software HAZOP in SDS phase. The software configuration management was performed using the in-house tool developed in the KNICS project. (author)

  19. An approach for assessing ALWR passive safety system reliability

    Many of the advanced light water reactor (ALWR) concepts proposed for the next generation of nuclear power plants rely on passive rather than active systems to perform safety functions. Despite the reduced redundancy of the passive systems as compared to active systems in current plants, the assertion is that the overall safety of the plant is enhanced due to the much higher expected reliability of the passive systems. In order to investigate this assertion, a study is being conducted at Sandia National Laboratories to evaluate the reliability of ALWR passive safety features in the context of probabilistic risk assessment (PRA). The purpose of this paper is to provide a brief overview of the approach to this study. The quantification of passive system reliability is not as straightforward as for active systems, due to the lack of operating experience, and to the greater uncertainty in the governing physical phenomena. Thus, the adequacy of current methods for evaluating system reliability must be assessed, and alternatives proposed if necessary. For this study, the Westinghouse Advanced Passive 600 MWe reactor (AP600) was chosen as the advanced reactor for analysis, because of the availability of AP600 design information. This study compares the reliability of AP600 emergency cooling system with that of corresponding systems in a current generation reactor

  20. Safety and security system of radioactive sources in Poland

    Poland has national System of Safety and Security of Radioactive Sources that fulfil International Basic Safety Standards for Protection against Ionising Radiation and for the Safety of Radiation Sources. It includes all main principles of protection against exposure to ionising radiation and for the safety and security of radioactive sources, of the Code of Conduct. All activities related to the exposure to ionising radiation are under control of the President of the National Atomic Energy Agency (NAEA) according to the Polish Atomic Law and Executive Regulations. The radioactive sources in Poland are under a sustainable supervision. The President of NAEA, as the national regulatory authority based on a legal system originating from the Atomic Law, is competent in and responsible for nuclear safety and nuclear security as well as for radiological protection of workers and of public in general. That means that the NAEA licences and controls (from the point of view of nuclear safety and radiation protection) all activities involving each source of ionising radiation (other than excepted source), registers all the nuclear materials and controls their physical protection. NAEA keeps registers of sealed radioactive sources and individual radiation doses of workers. NAEA also supervises (within its competence) all activities undertaken in case of radiation emergency. There are implementing procedures for strengthening controls of exports, imports and other transfers of radioactive sources, national safety and security cultures, particularly through the training of workers and the provision of appropriate information. Keeping records of all activities concerning nuclear materials and sealed radioactive sources has been applied in Poland since 1957. At present, NAEA has effective access to information collected in its own electronic databases, which histories go back to 1986. (author)

  1. Maintenance of radiation safety information system

    Choi, Ho Sun [Korea Institute of Nuclear Safety, Taejon (Korea, Republic of); Park, Moon Il; Chung, Chong Kyu; Lim, Bock Soo; Kim, Hyung Uk; Chang, Kwang Il; Nam, Kwan Hyun; Cho, Hye Ryan [AD center incubation LAB, Taejon (Korea, Republic of)

    2001-12-15

    The objectives of radiation safety information system maintenance are to maintain the requirement of users, change of job process and upgrade of the system performance stably and effectively while system maintenance. We conduct the code of conduct recommended by IAEA, management of radioisotope inventory database systematically using analysis for the state of inventory database integrated in this system. This system and database will be support the regulatory guidance, rule making and information to the MOST, KINS, other regulatory related organization and general public optimizationally.

  2. Safety Aspects of Big Cryogenic Systems Design

    Chorowski, M.; Fydrych, J.; Poliński, J.

    2010-04-01

    Superconductivity and helium cryogenics are key technologies in the construction of large scientific instruments, like accelerators, fusion reactors or free electron lasers. Such cryogenic systems may contain more than hundred tons of helium, mostly in cold and high-density phases. In spite of the high reliability of the systems, accidental loss of the insulation vacuum, pipe rupture or rapid energy dissipation in the cold helium can not be overlooked. To avoid the danger of over-design pressure rise in the cryostats, they need to be equipped with a helium relief system. Such a system is comprised of safety valves, bursting disks and optionally cold or warm quench lines, collectors and storage tanks. Proper design of the helium safety relief system requires a good understanding of worst case scenarios. Such scenarios will be discussed, taking into account different possible failures of the cryogenic system. In any case it is necessary to estimate heat transfer through degraded vacuum superinsulation and mass flow through the valves and safety disks. Even if the design of the helium relief system does not foresee direct helium venting into the environment, an occasional emergency helium spill may happen. Helium propagation in the atmosphere and the origins of oxygen-deficiency hazards will be discussed.

  3. Nuclear safety, control and monitoring systems

    The review of basic systems supporting safety of technological processes, which were developed and implemented at the Mayak site, is given. The purpose of the self-sustaining chain reaction emergency warning system is to register any anomalously high level of instantaneous γ-radiation, provide sound and light alarm signals, estimate the γ-radiation absorbed dose rate. The purpose of the automated radiation monitoring system is to provide radiation safety of process personnel by continuous remote monitoring of the radiological situation and control of the alarm devices and operating mechanisms. The automated radiation monitoring system provides continuous monitoring γ-radiation exposure dose rate; collection and processing of data from measurement units; prompt notification to regional and federal executive authorities about any accidents and provision of informational support of decision-making. The neutron detection system is used to measure the frequency of impulses that characterise the flux of neutrons emitted by the plutonium solution in the process vessels, prepare and transfer information to the central process control system at its automated workplace locations. The goals of the system for automatic monitoring of nuclear shipments are to provide integrated online monitoring for nuclear, radiation, environmental and fire safety, branch power supply, radiation and meteorological monitoring of the sanitary protection zones and observation zones, as well as transmission of operative data to the Rosatom's Crisis Response Centre

  4. Annual activity report of Ignalina NPP Safety Analysis Group for 1996 year

    The main results of Ignalina NPP Safety Analysis Group (ISAG) investigations for 1996 are presented. ISAG is concentrating its research activities into four areas: the neutrons dynamics modelling, simulation of transient processes during loss of coolant accident, the reactor cooling systems modelling and the probabilistic safety assessment of accident confinement system. Ignalina Safety Analysis Report was prepared on the basis of these results. 37 refs., 9 tabs., 96 figs

  5. Operational reliability of standby safety systems

    Grant, G.M.; Atwood, C.L.; Gentillon, C.D. [Idaho National Engineering Lab., Idaho Falls, ID (United States)] [and others

    1995-04-01

    The Idaho National Engineering Laboratory (INEL) is evaluating the operational reliability of several risk-significant standby safety systems based on the operating experience at US commercial nuclear power plants from 1987 through 1993. The reliability assessed is the probability that the system will perform its Probabilistic Risk Assessment (PRA) defined safety function. The quantitative estimates of system reliability are expected to be useful in risk-based regulation. This paper is an overview of the analysis methods and the results of the high pressure coolant injection (HPCI) system reliability study. Key characteristics include (1) descriptions of the data collection and analysis methods, (2) the statistical methods employed to estimate operational unreliability, (3) a description of how the operational unreliability estimates were compared with typical PRA results, both overall and for each dominant failure mode, and (4) a summary of results of the study.

  6. Formal verification of safety protocol in train control system

    Zhang, Yan; TANG, TAO; Li, Keping; Mera Sanchez de Pedro, Jose Manuel; Zhu, Li; Zhao, Lin; Xu, Tianhua

    2011-01-01

    In order to satisfy the safety-critical requirements, the train control system (TCS) often employs a layered safety communication protocol to provide reliable services. However, both description and verification of the safety protocols may be formidable due to the system complexity. In this paper, interface automata (IA) are used to describe the safety service interface behaviors of safety communication protocol. A formal verification method is proposed to describe the safety communication pr...

  7. Assessment of the Safety management system in railway sectors

    El-Koursi, Em; DUQUENNE, N

    2006-01-01

    The result of this work is done within the European project untitled SAMNET Safety Management and interoperability thematic Network for railways system launched by the Commission to investigate and to propose the approaches to specify and to implement the requirements identified in the Safety Directives. In particular, issues concerning policies on Safety Management System, Common Safety Indicators, Common Safety Targets and Common Safety Methods are addressed by this project. The project sta...

  8. Romania: ALFRED Demonstrator – Safety Rods System

    The main goal of the ALFRED project is to play the role of a demonstrator for the European concept of a LFR, able to prove the safety and reliability in all operating conditions through the use of some simple engineering solutions while reducing to the largest possible extent the uncertainties related to all development stages: design, construction and operation. The ALFRED core has been designed taking into account in a comprehensive approach the main goals to be achieved, the safety performances required as well as the main technological constraints that should be fulfilled. In this context and taking into account the topic of the meeting, the presentation is focused on the safety rod system that has been successfully adapted from the CDT-MYRRHA project

  9. Periodic safety review of the experimental fast reactor JOYO. Review of the activity for safety

    Periodic safety review (Review of the activity for safety) which consisted of 'Comprehensive evaluation of operation experience' and Incorporation of the latest technical knowledge' was carried out up to January 2005. 1. Comprehensive evaluation of operation experience. It was confirmed that the effectual activities for safety through the operation of JOYO were carried out in terms of (1) Operation management, (2) Maintenance management, (3) Fuel management, (4) Radiation management, (5) Radioactive waste management, (6) Emergency planning and (7) Feedback of incidents and failures. 2. Reflection of the latest technical knowledge. It was confirmed that the latest technical knowledge including regulation and guide line established by Nuclear Safety Commission of Japan until March 31st. 2003 were properly reflected in impressing the safety of the reactor. As a result, it was evaluated that the activity for safety was carried out effectually, and no additional measure was identified continual safe operation of the reactor. (author)

  10. A Methodological Framework for Software Safety in Safety Critical Computer Systems

    P. V. Srinivas Acharyulu; P. Seetharamaiah

    2012-01-01

    Software safety must deal with the principles of safety management, safety engineering and software engineering for developing safety-critical computer systems, with the target of making the system safe, risk-free and fail-safe in addition to provide a clarified differentaition for assessing and evaluating the risk, with the principles of software risk management. Problem statement: Prevailing software quality models, standards were not subsisting in adequately addressing the software safety ...

  11. A Methodological Framework for Software Safety in Safety Critical Computer Systems

    P. V. Srinivas Acharyulu

    2012-01-01

    Full Text Available Software safety must deal with the principles of safety management, safety engineering and software engineering for developing safety-critical computer systems, with the target of making the system safe, risk-free and fail-safe in addition to provide a clarified differentaition for assessing and evaluating the risk, with the principles of software risk management. Problem statement: Prevailing software quality models, standards were not subsisting in adequately addressing the software safety issues for real-time safety-critical embedded systems. At present no standard framework does exist addressing the safety management and safety engineering priniciples for the development of software safety in safety-critical computer systems. Approach: In this study we propose a methodological framework involving safety management practices, safety engineering practices and software development life cycle phases for the development of software safety. In this framework we make use of the safety management practices such as planning, defining priniciples, fixing responsibilities, creteria and targets, risk assessment, design for safety, formulating safety requirements and integrating skills and techniques to address safety issues early with a vision for assurance and so on. In this framework we have also analysed integration of applicability of generic industrial heirarchy and software development heirarchy, with derived cyclical review involving safety professionals generating a nodal point for software safety. Results: This framework is applied to safety-critical software based laboratory prototype Railroad Crossing Control System (RCCS with a limited complexity. The results have shown that all critical operations were safe and risk free. Conclusion: The development of software based on the proposed framework for RCCS have shown a clarified and improved safety-critical operations of the overall system peformance.

  12. Does the concept of safety culture help or hinder systems thinking in safety?

    Reiman, Teemu; Rollenhagen, Carl

    2014-07-01

    The concept of safety culture has become established in safety management applications in all major safety-critical domains. The idea that safety culture somehow represents a "systemic view" on safety is seldom explicitly spoken out, but nevertheless seem to linger behind many safety culture discourses. However, in this paper we argue that the "new" contribution to safety management from safety culture never really became integrated with classical engineering principles and concepts. This integration would have been necessary for the development of a more genuine systems-oriented view on safety; e.g. a conception of safety in which human, technological, organisational and cultural factors are understood as mutually interacting elements. Without of this integration, researchers and the users of the various tools and methods associated with safety culture have sometimes fostered a belief that "safety culture" in fact represents such a systemic view about safety. This belief is, however, not backed up by theoretical or empirical evidence. It is true that safety culture, at least in some sense, represents a holistic term-a totality of factors that include human, organisational and technological aspects. However, the departure for such safety culture models is still human and organisational factors rather than technology (or safety) itself. The aim of this paper is to critically review the various uses of the concept of safety culture as representing a systemic view on safety. The article will take a look at the concepts of culture and safety culture based on previous studies, and outlines in more detail the theoretical challenges in safety culture as a systems concept. The paper also presents recommendations on how to make safety culture more systemic. PMID:24275532

  13. Development of a Highway Safety Management System for Indiana: Phase 1

    Farooq, Omar; Sinha, Kumares C.; Nagle, John; James, Dwayne Stanley; Jiang, Yi

    1994-01-01

    This report presents the work plan for the development of a highway safety management system for Indiana. It identifies major activities and responsibilities for the development and implementation of a formal, statewide, interactive safety decision-making process. The safety management system of Indiana is perceived as a continuous process of considering all opportunities to improve highway safety in all phases of highway planning, design, construction, maintenance and operation. The primary ...

  14. SAFETY

    Niels Dupont

    2013-01-01

    CERN Safety rules and Radiation Protection at CMS The CERN Safety rules are defined by the Occupational Health & Safety and Environmental Protection Unit (HSE Unit), CERN’s institutional authority and central Safety organ attached to the Director General. In particular the Radiation Protection group (DGS-RP1) ensures that personnel on the CERN sites and the public are protected from potentially harmful effects of ionising radiation linked to CERN activities. The RP Group fulfils its mandate in collaboration with the CERN departments owning or operating sources of ionising radiation and having the responsibility for Radiation Safety of these sources. The specific responsibilities concerning "Radiation Safety" and "Radiation Protection" are delegated as follows: Radiation Safety is the responsibility of every CERN Department owning radiation sources or using radiation sources put at its disposition. These Departments are in charge of implementing the requi...

  15. Safety implications of using programmable digital computers in nuclear safety and control systems

    This papers describes the activities being conducted at the Idaho National Engineering Laboratory associated with the use of stored-program computers for protection and control systems. This project has recently been initiated and a preliminary report will be available. The use of computers in plant control and protection (and more generally in system important to safety) represents a major departure from the systems which have been used in the past. The design, development, and audit methods used for these systems are significantly different, thus requiring different skills and different perspectives

  16. Unavailability analysis of redundant safety systems

    Analytical equations have been obtained for the unavailabilities of redundant standby safety systems with components tested periodically. Test and repair contributions, hardware failures, human testing and repair errors as well as failures due to true demands have been taken into account. Equations have been derived for m-out-of-n systems (1 less than or equal to m less than or equal to n less than or equal to 4) with uniformly staggered, consecutive and random testing schemes. The equations have been used in a computer code, ICARUS, and applied to practical safety systems. The results are useful for optimizing the redundancy and testing and they illustrate the importance of human/testing errors and falures associated with true demands

  17. ACP Facility Safety Surveillance System Installation

    The Advanced spent fuel Conditioning Process is under development for effective management of spent fuel by converting UO2 into U-metal. For demonstration of this process, α-γ type new hotcell was built in the IMEF basement. All facilities which treat radioactive materials must manage CCTV system which is under control of Health Physics department. Three main points (including hotcell rear door area) have each camera, but operators who are in charge of facility management need to check the safety of the facility immediately through the network in his office. This needs introduce additional network cameras installation and this new surveillance system is expected to update the whole safety control ability with existing system

  18. Reactor safety: the Nova computer system

    After instances of maloperation, the causes of defects, the effectiveness of the measures taken to control the situation, and possibilities to avoid future recurrences need to be investigated above all before the plant is restarted. The most important aspect in all these efforts is to check the sequence in time, and the completeness, of the control measures initiated automatically. For this verification, a computer system is used instead of time-consuming manual analytical techniques, which produces the necessary information almost in real time. The results are available within minutes after completion of the measures initiated automatically. As all short-term safety functions are initiated by automatic systems, their consistent and comprehensive verification results in a clearly higher level of safety. The report covers the development of the computer system, and its implementation, in the Gundremmingen nuclear power station. Similar plans are being pursued in Biblis and Muelheim-Kaerlich. (orig.)

  19. Industrial Personal Computer based Display for Nuclear Safety System

    The safety display of nuclear system has been classified as important to safety (SIL:Safety Integrity Level 3). These days the regulatory agencies are imposing more strict safety requirements for digital safety display system. To satisfy these requirements, it is necessary to develop a safety-critical (SIL 4) grade safety display system. This paper proposes industrial personal computer based safety display system with safety grade operating system and safety grade display methods. The description consists of three parts, the background, the safety requirements and the proposed safety display system design. The hardware platform is designed using commercially available off-the-shelf processor board with back plane bus. The operating system is customized for nuclear safety display application. The display unit is designed adopting two improvement features, i.e., one is to provide two separate processors for main computer and display device using serial communication, and the other is to use Digital Visual Interface between main computer and display device. In this case the main computer uses minimized graphic functions for safety display. The display design is at the conceptual phase, and there are several open areas to be concreted for a solid system. The main purpose of this paper is to describe and suggest a methodology to develop a safety-critical display system and the descriptions are focused on the safety requirement point of view

  20. Spallation Neutron Source Accelerator Facility Target Safety and Non-safety Control Systems

    The Spallation Neutron Source (SNS) is a proton accelerator facility that generates neutrons for scientific researchers by spallation of neutrons from a mercury target. The SNS became operational on April 28, 2006, with first beam on target at approximately 200 W. The SNS accelerator, target, and conventional facilities controls are integrated by standardized hardware and software throughout the facility and were designed and fabricated to SNS conventions to ensure compatibility of systems with Experimental Physics Integrated Control System (EPICS). ControlLogix Programmable Logic Controllers (PLCs) interface to instruments and actuators, and EPICS performs the high-level integration of the PLCs such that all operator control can be accomplished from the Central Control room using EPICS graphical screens that pass process variables to and from the PLCs. Three active safety systems were designed to industry standards ISA S84.01 and IEEE 603 to meet the desired reliability for these safety systems. The safety systems protect facility workers and the environment from mercury vapor, mercury radiation, and proton beam radiation. The facility operators operated many of the systems prior to beam on target and developed the operating procedures. The safety and non-safety control systems were tested extensively prior to beam on target. This testing was crucial to identify wiring and software errors and failed components, the result of which was few problems during operation with beam on target. The SNS has continued beam on target since April to increase beam power, check out the scientific instruments, and continue testing the operation of facility subsystems

  1. Activities on safety for the cross-cutting issue of research reactors in the IAEA

    IAEA activities in the field of research reactor safety are included in the programme of the Division of Nuclear Installations Safety and implemented by the Engineering Safety Section through its Research Reactor Safety Unit. Following the objectives of the Division, the results of the IAEA missions and the recommendations from International Advisory Groups, the IAEA has conducted in recent years a certain number of activities aiming to enhance the safety of research reactors. The following activities are discussed in this paper: (a) the new Requirements for the Safety of Research Reactors, main features and differences with previous standards (SS-35-S1 and SS-35-S2) and the grading approach for implementation; (b) new documents being developed (safety guides, safety reports and TECDOCs); (c) activities related to the Incident Reporting System for Research Reactor (IRSRR); (d) the new features implemented for the (Integrated Safety Assessment of Research Reactors) INSARR missions; (e) the Code of Conduct on the Safety of Research Reactors developed, following the General Conference Resolution GC(45)/RES/10; and (f) the survey on the safety of research reactors conducted in the year 2002 and the results obtained. (author)

  2. Guidelines for implementation of RCM on safety systems

    Reliability Centered Maintenance (RCM) methodology was originally developed by the commercial airlines industry in the early 1960s for identifying applicable and effective preventive maintenance tasks and as currently used in nuclear power industry. Effective maintenance of the systems at a nuclear power plant (NPP) is essential for its safe and reliable operation. Reliability Centered Maintenance at NPP is the program to assure that plant systems remain within an original design criteria and are not adversely affected during the plant life time. The aim of this report is to provide the guidelines to implement the RCM approach on NPP safety systems. Safety systems are usually standby and therefore, we need to periodically detect and repair failures that may have occurred since the previous activation or inspection the equipment. The RCM guidelines are intended to help identify the failure modes and related root causes and then decide the maintenance policies to achieve the high level of safety and reliability. The RCM is intended to improve or maintain high levels of system reliability and plant availability. Since the reliability of plant systems will be improved, the plant safety correspondingly will be increased. Another goal of RCM is to optimize the maintenance and surveillance tasks such that the overall level of resources required to accomplish essential tasks is kept to minimum. RCM also strives to eliminate unnecessary corrective maintenance and to select yet most cost-effective approach to maintenance, testing and inspection for system components. 9 refs. (Author) .new

  3. Modelling of safety fieldbus system via SW tool SHARPE

    Maria Franekova; Jan Rofar

    2008-01-01

    Paper deals with the modelling of the safety-related Fieldbus communication system, which has to guaranty Safety Integrity Level (SIL) according to standard IEC 61508. There are methods of safety analysis for the closed safety Fieldbus transmission system summarized. The mainly part the modeling SW tool SHARPE describes. The realized models are based on Fault Tree Analysis (FTA) and Markov analysis.

  4. Safety Cultures in Water-Based Outdoor Activities in Denmark

    Andkjær, Søren; Arvidsen, Jan

    2015-01-01

    water-based outdoor activities: small boat fishing, sea kayaking, and kite surfing. The theoretical framework used was cultural analysis and the methodological approach was mixed methods using case studies with survey and qualitative interviews. The study indicates that safety is a complex matter and......In this paper, we report on the study Safe in Nature (Tryg i naturen) in which the aim was to analyze and discuss risk and safety related to outdoor recreation in the coastal regions of Denmark. A cultural perspective is applied to risk management and the safety cultures related to three selected...... that safety culture can be understood as the sum and interaction among six categories. The safety culture is closely related to the activity and differs widely among activities. We suggest a broad perspective be taken on risk management wherein risk and safety can be managed at different levels. Small...

  5. Indus-2 beamline personal safety interlocks system

    Indus-2 is a 2.5 GeV, 300 mA synchrotron radiation source and is currently operating at 2 GeV and 100 mA in the round the clock shift. Two sources of ionizing radiation at Indus-2 can pose a hazard if not properly dealt with are, Bremsstrahlung radiation and synchrotron radiation. The former is mostly generated from collision of electrons with gas molecules and consists of very high energy radiation. A hutch is a structure that houses the beamline and other experimental equipment /apparatus, which is designed to prevent personnel access to areas where there is a potential for the synchrotron beam to generate high levels of ionizing radiation. Hutches are designed to reduce the direct and scattered beam dose rates to acceptably low levels outside. Personal Safety Interlock System (PSIS) is introduced to protect people from accidental exposure to high radiation when the beamlines are in use. PSIS ensures that (1) synchrotron radiation can be allowed to enter an experimental hutch only when no one is present in the hutch and all the doors of the hutch are properly closed; (2) in case of a person entering a hutch during operation, the radiation is stopped by closing the safety shutter and (3) when radiation level in the occupied area near the beamline exceeds the permissible level, it is brought down by closing the safety shutter. The PSIS system is linked with main front-end control system of each beamline. PSIS system consist of relay modules, timers, search and scram buttons, status display panels, door limit switches with latching mechanism and audio-visual alarms. This paper describes, in detail, the design and interlock scheme of a fail-safe and reliable Personal Safety Interlock System implemented at Indus-2 beamlines. (author)

  6. Research on Food Safety Guarantee System Based on AHP

    Pei Tang; Shanhong Zhu

    2015-01-01

    All kinds of food safety accidents occurred frequently in recent years, the main reason is that food safety system construction failed to synchronize with the internet, this study sets up food safety technical standard system based on the AHP evaluation model, learns lessons from food safety related bulletin, revises for the food industry standard, innovates from technology and regulatory reform, so as to promote international food safety system construction.

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

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

  8. Monitoring System For Improving Radiation Safety Management

    Medi SMARTS (Medical Survey Mapping Automatic Radiation Tracing System), a gamma radiation monitoring system, was installed in a nuclear medicine department. In this paper the evaluation of the system's ability to improve radiation safety management is presented. The system is based on a state of the art software that continuously collects on line radiation measurements for display, analysis and logging. Radiation is measured by GM tubes; the signal is transferred to a data processing unit and then via an RS-485 communication line to a computer. The system automatically identifies the detector type and its calibration factor, thus providing compatibility, maintainability and versatility when changing detectors. Radiation levels are displayed on the nuclear medicine department map at six locations. The system has been operating continuously for more than one year, documenting abnormal events caused by routine operation or failure incidents. In cases where abnormal working conditions were encountered, an alarm message was sent automatically to the supervisor via his tele-pager. An interesting issue observed during the system evaluation, was the inability to distinguish between high radiation levels caused by proper routine operation and those caused by safety failure incidents. The solution included examination of two parameters, radiation levels as well as their duration period. A careful analysis of the historical data, applying the appropriated combined parameters determined for each location, verified that such a system can identify abnormal events, provide alarms to warn in case of incidents and improve standard operating procedures

  9. An approach for assessing ALWR passive safety system reliability

    Many advanced light water reactor designs incorporate passive rather than active safety features for front-line accident response. A method for evaluating the reliability of these passive systems in the context of probabilistic risk assessment has been developed at Sandia National Laboratories. This method addresses both the component (e.g. valve) failure aspect of passive system failure, and uncertainties in system success criteria arising from uncertainties in the system's underlying physical processes. These processes provide the system's driving force; examples are natural circulation and gravity-induced injection. This paper describes the method, and provides some preliminary results of application of the approach to the Westinghouse AP600 design

  10. Theoretical study on safety assessment indexes system of coal mines

    SHI Shi-liang(施式亮); LI Run-qiu(李润求); XIE Jian-xiang(谢建湘)

    2003-01-01

    The safety status of the coal mines is closely correlated with the operating status and its changes of the whole working system in the coal mines, and the safety system is the sub-system of the whole production system. In this paper, based on the analysis of the complicacy of the safety sub-system and its affecting factors, the theory basis of the indexes system of the safety assessment was studied, including the establishing principles of the indexes system , the structure of the indexes system, the determining methods of the assessment indexes. The complete indexes system was established for the safety assessment of the coal mines in the paper.

  11. Safety characteristics of decay heat removal systems

    Safety features of the decay heat removal systems including power sunply and final heat sink are described. A rather high reliability and an utmost degree of independence from energy supply are goals to be attained in the design of the European Fast Reactor (EFR) decay heat removal scheme. Natural circulation is an ambitious design goal for EFR. All the considerations are performed within the frame of risk minimization

  12. Occupational Safety and Health Management System (OSHMS)

    Safe work environment has always been one of the major concerns at workplace. For this, Occupational Safety and Health Act 1994 has been promulgated for all workplaces to ensure the Safety, Health and Welfare of its employees and any person at workplaces. Malaysian Nuclear Agency therefore has started the initiative to review and improve the current Occupational Safety and Health Management System (OSHMS) by going for OHSAS 18001:2007 and MS 1722 standards certification. This would also help in our preparation to bid as the TSO (Technical Support Organization) for the NPP (Nuclear Power Plant) when it is established. With a developed and well maintained OSHMS, it helps to create a safe working condition and thus enhancing the productivity, quality and good morale. Ultimately, this will lead to a greater organization profit. However, successful OSHMS requires full commitment and support from all level of the organization to work hand in hand in implementing the safety and health policy. Therefore it is essential for all to acknowledge the progress of the implementation and be part of it. (author)

  13. Nuclear safety activities in the SR of Slovenia in 1986

    Currently Yugoslavia has one 632 MWe nuclear power plant (NPP) of PWR design, located at Krsko in the Socialist Republic (SR) of Slovenia. Krsko NPP, which is a two-loop plant, started power operation in 1981. In general, reactor safety activities in the SR of Slovenia are mostly related to upgrading the safety of our Krsko NPP and to developing capabilities for use in future units. This report presents the nuclear safety related legislation and organization of the corresponding regulatory body, and the activities related to nuclear safety of the participating organizations in the SR of Slovenia in 1986. (author)

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

    Hill, Janice; Victor, Daniel

    2008-01-01

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

  15. Risk and Safety Working Group: perspectives,accomplishments and activities

    The Generation IV Technology Road-map identifies 3 specific safety goals: 1) Generation IV nuclear energy systems will excel in safety and reliability; 2) Generation IV nuclear energy systems will have a very low likelihood and degree of reactor core damage; and 3) Generation IV nuclear energy systems will eliminate the need for offsite emergency response. This paper describes an integrated safety philosophy for Generation IV nuclear systems. The following postulates should underlie such a safety philosophy: -) Opportunities exist to further improve on nuclear power's already excellent safety record in most countries; -) Safety improvements should simultaneously be based on several elements which will require specific research efforts; -) The principle of 'defense in depth' has served the nuclear power industry well, and must be preserved in the design of Generation IV systems; -) The Generation IV design process should be driven by a 'risk-informed' approach. The methodology is tentatively called the Integrated Safety Assessment Methodology (ISAM). Although the ISAM is essentially a Probabilistic Safety Assessment (PSA) based methodology for Generation IV systems, the strength of the ISAM is that it offers tools that are tailored to answering specific types of questions at various stages of design development, and that the elements of the methodology complement and support one another in a way that contributes to a much more complete understanding of the range of safety issues. (A.C.)

  16. The Management System for Nuclear Installations Safety Guide

    This Safety Guide is applicable throughout the lifetime of a nuclear installation, including any subsequent period of institutional control, until there is no significant residual radiation hazard. For a nuclear installation, the lifetime includes site evaluation, design, construction, commissioning, operation and decommissioning. These stages in the lifetime of a nuclear installation may overlap. This Safety Guide may be applied to nuclear installations in the following ways: (a)To support the development, implementation, assessment and improvement of the management system of those organizations responsible for research, site evaluation, design, construction, commissioning, operation and decommissioning of a nuclear installation; (b)As an aid in the assessment by the regulatory body of the adequacy of the management system of a nuclear installation; (c)To assist an organization in specifying to a supplier, via contractual documentation, any specific element that should be included within the supplier's management system for the supply of products. This Safety Guide follows the structure of the Safety Requirements publication on The Management System for Facilities and Activities, whereby: (a)Section 2 provides recommendations on implementing the management system, including recommendations relating to safety culture, grading and documentation. (b)Section 3 provides recommendations on the responsibilities of senior management for the development and implementation of an effective management system. (c)Section 4 provides recommendations on resource management, including guidance on human resources, infrastructure and the working environment. (d)Section 5 provides recommendations on how the processes of the installation can be specified and developed, including recommendations on some generic processes of the management system. (e)Section 6 provides recommendations on the measurement, assessment and improvement of the management system of a nuclear installation. (f

  17. High-performance work systems and occupational safety.

    Zacharatos, Anthea; Barling, Julian; Iverson, Roderick D

    2005-01-01

    Two studies were conducted investigating the relationship between high-performance work systems (HPWS) and occupational safety. In Study 1, data were obtained from company human resource and safety directors across 138 organizations. LISREL VIII results showed that an HPWS was positively related to occupational safety at the organizational level. Study 2 used data from 189 front-line employees in 2 organizations. Trust in management and perceived safety climate were found to mediate the relationship between an HPWS and safety performance measured in terms of personal-safety orientation (i.e., safety knowledge, safety motivation, safety compliance, and safety initiative) and safety incidents (i.e., injuries requiring first aid and near misses). These 2 studies provide confirmation of the important role organizational factors play in ensuring worker safety. PMID:15641891

  18. Security-Informed Safety Case Approach to Analysing MILS Systems

    Netkachova, K.; Müller, K.; Paulitsch, M; Bloomfield, R. E.

    2015-01-01

    Safety cases are the development foundation for safety-critical systems and are often quite complex to understand depending on the size of the system and operational conditions. The recent advent of security aspects complicates the issues further. This paper describes an approach to analysing safety and security in a structured way and creating security-informed safety cases that provide justification of safety taking into particular consideration the impact of security. The paper includes an...

  19. ESSAA: Embedded system safety analysis assistant

    Wallace, Peter; Holzer, Joseph; Guarro, Sergio; Hyatt, Larry

    1987-01-01

    The Embedded System Safety Analysis Assistant (ESSAA) is a knowledge-based tool that can assist in identifying disaster scenarios. Imbedded software issues hazardous control commands to the surrounding hardware. ESSAA is intended to work from outputs to inputs, as a complement to simulation and verification methods. Rather than treating the software in isolation, it examines the context in which the software is to be deployed. Given a specified disasterous outcome, ESSAA works from a qualitative, abstract model of the complete system to infer sets of environmental conditions and/or failures that could cause a disasterous outcome. The scenarios can then be examined in depth for plausibility using existing techniques.

  20. A safety related control system for NPPs

    After an introduction into safety terms a short description of diverse system design is given. Diversity principle will be analyzed critically especially due to non-planable waiting times, the necessary grade of diversification, real-time behaviour. A conventional PID-controller is presented running in parallel with a modem fuzzy controller. Nevertheless, just the fuzzy controller offers a great challenge because of its inherent diverse design approach. Up to now there is deeper know-how available for V and V procedures for conventional as well as fuzzy controller. An example for such a system design will be presented together with V and V aspects. (author)

  1. Safety Analysis of Stochastic Dynamical Systems

    Sloth, Christoffer; Wisniewski, Rafael

    2015-01-01

    This paper presents a method for verifying the safety of a stochastic system. In particular, we show how to compute the largest set of initial conditions such that a given stochastic system is safe with probability p. To compute the set of initial conditions we rely on the moment method that via...... Haviland's theorem allows an infinite dimensional optimization problem on measures to be formulated as a polynomial optimization problem. Subsequently, the moment sequence is truncated (relaxed) to obtain a finite dimensional polynomial optimization problem. Finally, we provide an illustrative example that...

  2. A review of the nuclear safety activities in Italy

    A review of research programs carried out in Italy in the field of nuclear reactor safety was done in 1986, in the frame of the activities of the Commission of the European Communities, the International Energy Agency and the Nuclear Energy Agency of the Organization for Economic Cooperation and Development. The report contains information on these programs, as well as information on the organization of safety research in Italy and the evolution of safety research programs

  3. Safety systems of heavy water reactors and small power reactors

    After introductional descriptions of heavy water reactors and natural circulation boiling water reactors the safety philosophy and safety systems like ECCS, residual heat removal, protection systems etc., are described. (RW)

  4. Total Quality Management and the System Safety Secretary

    Elliott, Suzan E.

    1993-01-01

    The system safety secretary is a valuable member of the system safety team. As downsizing occurs to meet economic constraints, the Total Quality Management (TQM) approach is frequently adopted as a formula for success and, in some cases, for survival.

  5. Safety system in a heavy water detritiation plant

    In the heavy water circuits of the CANDU reactor, tritium is generated through the following reactions: - neutron activation; - 235 U, 233 U and 239 Pu fission in rods; - 3 He decay. The equilibrium value, of about 30-50 Ci/kg, depends by the heavy water quantity which is used in common in primary circuit and moderator, at an increase rate by 4Ci/kg/year. As the tritium inventory in a CANDU reactor can be larger than 6 x 106 Ci (tritium oxide in heavy water circuits), it results that a detritiation plant is a necessity. Solving these problems means that a heavy water detritiation plant must built and linked to the moderator circuits of the CANDU type reactor. This plant can be assimilated as a nuclear facility, involving special regulation and safety systems, complying with the nuclear laws of Romania and international safety regulations, including IAEA Vienna specifications. Like any nuclear facility, a special safety system is provided, with special hardware and software that supervises the technological process and safety equipment. Conventional systems use a large number of equipment, very expensive, while the reliability and accuracy are basic demands. On the other hand, the systems become more complex solving demands like redundancy, failure of safety or diversity. Like a result, operation and maintenance become more complicated and more expensive. Solution for these problems is to develop a reliable and flexible on-line diagnosis system, comprising two computers and a small number of discrete equipment. Creating a safety display and analysis system that provides an overview of the plant safety status and prevents serious safety degradation, ensures an easy maintenance and operation. The system is flexible, easy to use and the improvements needed by any technological process experiment could be done in short time and at low costs. Such a system can replace a dedicated hardware and software for industrial processes, regarding especially the experimental

  6. Coupled seismic analysis of nuclear safety systems

    Seismic responses of structural systems obtained on the basis of coupled analysis (selected equipment modelled along with the civil structures) results in lower responses and economical designs when compared with uncoupled analysis. For Nuclear Safety Related Structures, from considerations of limiting problem size for analysis and also to reduce modelling efforts, it is necessary to select which equipment needs to be modelled with its supports so as to adequately obtain the response of the structural system with interaction of such equipment. Coupled analysis of a primary structure and secondary system is necessary when the effects of interaction between them are significant. This paper attempts to study the structural response of Reactor Building structures of PHWR as well as PFBR to arrive at specific conclusions with respect to effect of coupling of secondary systems. The paper presents an approach followed to evolve a rational basis for inclusion or non-inclusion of such equipment in the coupled model of the primary system. (author)

  7. Safety testing for LHC access system

    Valentini, F; Ninin, P; Scibile, S

    2008-01-01

    In the domain of Safety Real-Time Systems the problem of testing represents always a big effort in terms of time, costs and efficiency to guarantee an adequate coverage degree. Exhaustive tests may, in fact, not be practicable for large and distributed systems. This paper describes the testing process followed during the validation of the CERN's LHC Access System [1], responsible for monitoring and preventing physical risks for the personnel accessing the underground areas. In the paper we also present a novel strategy for the testing problem, intended to drastically reduce the time for the test patterns generation and execution. In particular, we propose a methodology for blackbox testing that relies on the application of Model Checking techniques. Model Checking is a formal method from computer science, commonly adopted to prove correctness of system’s models through an automatic system’s state space exploration against some property formulas.

  8. System analysis for plant operation and safety

    In parallel with the established reactor support program utilizing design basis system analysis for licensing applications, NUSCO has a broad program underway utilizing best estimate system analysis in support of safe operation of its nuclear units. The latter analysis application requires the use of codes such as RETRAN, which have proven prediction capabilities under a wide range of physical conditions. The program utilizing best estimate system analysis, to varying degrees, in support of plant operation and safety includes the following areas of application: 1) Operator training. Specific application of system analysis in this support area include: best estimate analysis of FSAR transients, best estimate verification of plant specific simulators, and lessons learned through PRA best estimate analysis. 2) Operator guidance. Specific applications in this support area include: development, verification, and safety evaluations of emergency operator guidelines, and analysis of ambiguous scenarios to determine available fail-safe decisions and reversible actions. 3) Operator performance verification. Specific applications in this support area include: verification analysis of operational transients, and verifications of adequacy of system performance/operator actions. 4) Deterministic analyses for PRA support. 5) Verification and support of startup procedures

  9. Safety management systems. Audit tools and reliability of auditing

    Kuusisto, A. [VTT Automation, Espoo (Finland). Safety Engineering

    2000-12-01

    Safety auditing is a systematic method to evaluate a company's safety management system. This work concentrates on evaluating the reliability of some safety audit tools. Firstly, the factors affecting reliability in auditing are clarified. Secondly, the inter-observer reliability of one of the audit tools is tested. This was done using an audit method, known as the D and S method, in six industrial companies in the USA, and in three companies in Finland. Finally, a new improved audit method called MISHA was developed, and its reliability was tested in two industrial companies. The results of the work show that safety audit tools do not ensure reliable and valid audit results. The auditor's expertise in the field of health and safety is particularly important when the company's compliance with the legal requirements is evaluated. A reasonably high reliability in the use of the D and S can be achieved when the auditor is familiar with the audit tool, the national legislation, and the company's culture. The MISHA method gives more reliable results than D and S when the auditor is not trained. On the other hand, it seems that the D and S is more reliable when the auditor is a trained expert. Some differences were found between the companies in the USA and in Finland. The organization and administration of safety activities was at a somewhat higher level among the companies in the USA. Industrial hazard control, as well as the control of fire hazards and industrial hygiene were at a high level in all companies in both countries. Most dispersion occurred in supervision, participation, motivation, and training activities. Finally, accident investigation and analysis were significantly better arranged among the companies in the USA. The results are in line with the findings of the literature survey on national differences in safety management procedures. (orig.)

  10. 78 FR 29392 - Embedded Digital Devices in Safety-Related Systems, Systems Important to Safety, and Items Relied...

    2013-05-20

    ... COMMISSION Embedded Digital Devices in Safety-Related Systems, Systems Important to Safety, and Items Relied... Regulatory Issue Summary (RIS) 2013-XX, ``Embedded Digital Devices in Safety-Related Systems, Systems... basic components with embedded digital devices. DATES: Submit comments by July 19, 2013....

  11. Development of Network Protocol for the Integrated Safety System

    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

  12. Development of Network Protocol for the Integrated Safety System

    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.

  13. Safety program considerations for space nuclear reactor systems

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

  14. Safety program considerations for space nuclear reactor systems

    Cropp, L.O.

    1984-08-01

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

  15. Improved safety approach for general safety designs of the next generation sodium-cooled fast reactor systems

    For the future sodium-cooled fast reactor [SFR], safety approach should realize higher safety level than that of current generation reactor systems, by enhancing prevention and mitigation features of severe accidents with built-in measures in the safety designs. In this study, general safety approaches are developed for the next generation SFR based on the fundamental safety characteristics of the SFR system by comparing those of LWR system and with incorporating lessons learned from the TEPCO's Fukushima Daiichi nuclear power plants accidents. The fundamental characteristics of the SFR system are summarized into five key points: 1) reactivity related to reactor core configuration, 2) coolant pressure under operation, 3) coolant sub-cool margin to boiling, 4) ultimate heat sink, and 5) physical and chemical properties of sodium coolant. These points are considered to derive general safety approach related to fundamental function, i.e. reactor shutdown, decay heat removal, and containment, for the future SFR system. The key is to apply passive safety mechanism for prevention/mitigation of severe accident in design extension condition (DEC) with balancing active safety systems - passive mechanism should be built-in design for reactor shutdown and decay heat removal especially for DEC in order to enhance diversity to the engineered safety systems utilized for design basis accident (DBA). From the viewpoint of containment integrity, SFR system has favorable feature due to its low coolant pressure (almost atmospheric) under operation, whereas the potentials of pressure/temperature increases via sodium leak and of significant mechanical energy release by re-criticality in the course of the core disruptive accident (CDA) should be eliminated by the safety designs for both prevention and mitigation of the severe accidents. (author)

  16. Safety Analysis for Power Reactor Protection System

    The main function of a Reactor Protection System (RPS) is to safely shutdown the reactor and prevents the release of radioactive materials. The purpose of this paper is to present a technique and its application for used in the analysis of safety system of the Nuclear Power Plant (NPP). A more advanced technique has been presented to accurately study such problems as the plant availability assessments and Technical Specifications evaluations that are becoming increasingly important. The paper provides the Markov model for the Reactor Protection System of the NPP and presents results of model evaluations for two testing policies in technical specifications. The quantification of the Markov model provides the probability values that the system will occupy each of the possible states as a function of time.

  17. Configuration and Data Management Process and the System Safety Professional

    Shivers, Charles Herbert; Parker, Nelson C. (Technical Monitor)

    2001-01-01

    This article presents a discussion of the configuration management (CM) and the Data Management (DM) functions and provides a perspective of the importance of configuration and data management processes to the success of system safety activities. The article addresses the basic requirements of configuration and data management generally based on NASA configuration and data management policies and practices, although the concepts are likely to represent processes of any public or private organization's well-designed configuration and data management program.

  18. Design and Realization of the Safety Production Scheduling System

    Qiang Fan

    2013-01-01

    Full Text Available In this study, we have a research of the design and realization of the Safety Production Scheduling System. Urged by the government departments as well as safety supervising institutions, many coal enterprises are embarking on designing and constructing an information system platform for safety production and scheduling. How to establish a systematic, comprehensive, standardized and scientific management platform for the safety production and scheduling has become a hot issue in the coal industry, which is also an important move to integrate various safety management measures in order to prevent major safety accidents and keep up with the international industry status. Taking a successful, large-scale safety production and scheduling system for example, this study elaborates on its overall design and construction. When the system is completed, it will play an important role in strengthening safety production of the coal mines, preventing accidents as well as increasing the overall safety level of the coal industry.

  19. An Approach to Modeling Software Safety in Safety-Critical Systems

    Ben S. Medikonda; Seetha R. Panchumarthy

    2009-01-01

    Software for safety-critical systems has to deal with the hazards identified by safety analysis in order to make the system safe, risk-free and fail-safe. Software safety is a composite of many factors. Problem statement: Existing software quality models like McCalls and Boehms and ISO 9126 were inadequate in addressing the software safety issues of real time safety-critical embedded systems. At present there does not exist any standard framework that comprehensively addresses the Factors, Cr...

  20. Safety Culture Improvement Activities of YGN 3 and 4

    In nuclear power industry all over the world, we can never overemphasize the importance of nuclear safety. After the Chernobyl accident occurred in 1986, Korean nuclear energy industry had made every effort to enhance nuclear safety culture further. And, as a result of the efforts, Korean government declared the five principles for the nuclear energy safety regulation, which were included in the Nuclear Energy Safety Policy Statement published in 1994. In 2001, through the announcement of Nuclear Safety Charter for the peaceful use of nuclear energy, the Ministry of Science and Technology proclaimed at home and abroad that the protection of citizens and environment by securing nuclear safety should be the highest priority in nuclear energy industry. Occupying almost 40% share of domestic electricity generation, Korea Hydro and Nuclear Power Co. decided 'Safety Top Priority Management' as president's management policy, and clearly presented the safety goal to the personnel. By this, the management can effectively place stress on securing safety, which is our highest priority and the only way to win public confidence toward nuclear energy industry. This is prepared to shortly introduce the activities for improving safety culture in Yonggwang Nuclear Power unit 3 and 4 (YGN 3 and 4)

  1. Safety drain system for fluid reservoir

    England, John Dwight (Inventor); Kelley, Anthony R. (Inventor); Cronise, Raymond J. (Inventor)

    2012-01-01

    A safety drain system includes a plurality of drain sections, each of which defines distinct fluid flow paths. At least a portion of the fluid flow paths commence at a side of the drain section that is in fluid communication with a reservoir's fluid. Each fluid flow path at the side communicating with the reservoir's fluid defines an opening having a smallest dimension not to exceed approximately one centimeter. The drain sections are distributed over at least one surface of the reservoir. A manifold is coupled to the drain sections.

  2. Safety-Critical Java for Embedded Systems

    Rios Rivas, Juan Ricardo

    for Java aims at providing a reduced set of the Java programming language that can be used for systems that need to be certified at the highest levels of criticality. Safety-critical Java (SCJ) restricts how a developer can structure an application by providing a specific programming model...... and by restricting the set of methods and libraries that can be used. Furthermore, its memory model do not use a garbage-collected heap but scoped memories. In this thesis we examine the use of the SCJ specification through an implementation in a time-predictable, FPGA-based Java processor. The specification is now...

  3. New trends in safety systems design optimization

    Design and maintenance-strategy optimization of safety systems for potentially hazardous facilities have become a first-order social demand in the last decade. Not only because the nocive effects of contamination and industrial spillages on the environment are less tolerated, but also because the great amount of materials dangerous to human beings that are manipulated in the cities, or at their outskirts, turn some spots of our cities into very dangerous zones for their inhabitants. As a result, in the last decade safety system modeling methods have been developed, especially the so-called Fault Tree Analysis, in order to allow the introduction of new design alternatives as well as different maintenance strategies. The increasing complexity of the resulting optimization problems has led to the application of global optimization evolutive methods, especially genetic algorithms, in a single-objective environment as well as in a multiobjective one. Despite recent progress in this subject, there persist important limitations still not solved that limit the applicability in multiple real problems, and therefore current methodologies are not part yet of the tool set used by most engineering design groups. Among them, the computational cost of fault tree quantitative evaluation, and the loss of efficiency of the genetic algorithms due to the different nature of the variables to optimize. In this paper, a review of relevant contributions in safety system design, from a conceptual point of view as well as from an algorithmic one, is presented. Emphasizing the advantages and drawbacks of the use of genetic algorithms. Non-solved problems will be analyzed and described using current methodologies and the most recent contributions to solving such problems will be presented, including the usage of the new global optimization evolutive method, known as flexible evolution, which shows excellent properties for design optimization. The role that Monte Carlo simulation methods may

  4. Inspirations from Dupont Safety Management System

    Ma Yong

    2009-01-01

    @@ Dupont,with its 200 years of safety management experience,tells us:all safety accidents can be prevented. Dupont has a history of more than 200 years,the concept of "safety is priority"has never changed.Dupont is just another word for safety.

  5. Activities of nuclear safety culture in foreign organizations such as IAEA, etc

    Safety of nuclear facilities is guaranteed with the safety of instrument and equipment and of human, organization, management and system. In the guarantee, especially the encouragement and the growth of nuclear safety culture which is the basis of the safety of the latter are very important. In recent years, severe accidents and transients due to organizational issues have increased. Then, international organizations, regulatory organizations of each country and nuclear enterprises promote positively the developments of self-assessment methods of safety culture and safety management systems. The activities in the international organizations of IAEA and OECD/NEA and in the foreign regulatory organizations of US NRC and UK NII are described. (K. Kato)

  6. Advocating System Safety Concept in Preventing Airline Accidents

    Lu, Chien-tsung; Wetmore, Michael; Smith, John

    2005-01-01

    System safety was conceptualized by the aerospace industry in the late 1940s in the United States (U.S.). Traditionally, users of system safety applied analysis to identify operational hazards and subsequently provide countermeasures before or after an accident. Unfortunately, very few aviation safety researches from the airlines had utilized it to promote aviation safety. To enrich this knowledge and contribute interest from academia, this paper adopted the inductive techniques of system saf...

  7. The WIPP transportation system: Dedicated to safety

    When developing a transportation system to transport transuranic (TRU) waste from ten widely-dispersed generator sites, the Department of Energy (DOE) recognized and addressed many challenges. Shipments of waste to the Waste Isolation Pilot Plant (WIPP) were to cover a twenty-five year period and utilize routes covering over twelve thousand miles in twenty-three states. Enhancing public safety by maximizing the payload, thus reducing the number of shipments, was the primary objective. To preclude the requirement for overweight permits, the DOE started with a total shipment weight limit of 80,000 pounds and developed an integrated transportation system consisting of a Type ''B'' package to transport the material, a lightweight tractor and trailer, stringent driver requirements, and a shipment tracking system referred to as ''TRANSCOM''

  8. IAEA activity related to safety of nuclear desalination

    The nuclear plants for desalination to be built in the future will have to meet the standards of safety required for the best nuclear power plants currently in operation or being designed. The current safety approach, based on the achievement of the fundamental safety functions and defence in depth strategy, has been shown to be a sound foundation for the safety and protection of public health, and gives the plant the capability of dealing with a large variety of sequences, even beyond the design basis. The Department of Nuclear Safety of the IAEA is involved in many activities, the most important of which are to establish safety standards, and to provide various safety services and technical knowledge in many Technical Co-operation assistance projects. The department is also involved in other safety areas, notably in the field of future reactors. The IAEA is carrying out a project on the safety of new generation reactors, including those used for desalination, with the objective of fostering an exchange of information on safety approaches, promoting harmonization among Member States and contributing towards the development and revision of safety standards and guidelines for nuclear power plant design. The safety, regulatory and environmental concerns in nuclear powered desalination are those related directly to nuclear power plants, with due consideration given to the coupling process. The protection of product water against radioactive contamination must be ensured. An effective infrastructure, including appropriate training, a legal framework and regulatory regime, is a prerequisite to considering use of nuclear power for desalination plants, also in those countries with limited industrial infrastructures and little experience in nuclear technology or safety. (author)

  9. Hybrid reliability model for nuclear reactor safety system

    The dependability of critical safety systems needs to be quantitatively determined in order to verify their effectiveness, e.g. with regard to regulatory requirements. Since modular redundant safety systems are not required for normal operation, their reliability is strongly dependent on periodic inspection. Several modeling methods for the quantitative assessment of dependability are described in the literature, with a broad variation in complexity and modeling power. Static modeling techniques such as fault tree analysis (FTA) or reliability block diagrams (RBD) are not capable of capturing redundancy and repair or test activities. Dynamic state space based models such as continuous time Markov chains (CTMC) are more powerful but often result in very large, intractable models. Moreover, exponentially distributed state residence times are not a correct representation of actual residence times associated with repair activities or periodic inspection. In this study, a hybrid model combines a system level RBD with a CTMC to describe the dynamics. The effects of periodic testing are modeled by redistributing state probabilities at deterministic test times. Applying the method to the primary safety shutdown system of the BR2(Belgian Reactor 2)—nuclear research reactor, resulted in a quantitative as well as a qualitative assessment of its reliability.

  10. Optimal logic structure of safety monitoring systems

    This paper introduces an optimal logic structure of a safety monitoring system to minimize the expected total loss incurred upon fail-dangerous (FD) failures or fail-safe (FS) failures. This paper is divided into three parts. The first part considers the safety monitoring system composed of several channels. Each channel has identical sensors to monitor a plant state variable, e.g., temperature of pressure. When a state variable becomes abnormal, the corresponding channel issues a channel alarm for protective action. The problem is to design an optimal, coherent structure for each channel when the channels are logically connected according to an accident occurence mechanism. For the one-channel system, the optimal channel structure is proven to be k*-out-of-n: G, and k* can be calculated analytically. For the multi-channel system, the optimal channel structure is a k-out-of-n: G, and the problem is formulated as a non-linear integer programming (NLIP) which can be solved by the extended Lawler and Bell's method. The second part generalizes the first part to cover more general optimization of the logic structure without assuming ad-hoc channel connections. The optimal, Boolean structure can be determined by a switching function. The monotone property enables one to employ a systematic search method for a simple expression of the optimal structure. A probabilistic logic structure is discussed and proven to be reduced to a deterministic one. The last part disccusses an optimal shut-down logic for the overall protective system, which is composed of the driving, judging, and sensing sections. Each section may fail in two ways: FD or FS. The optimal shut-down logic, as before, is determined by a switching function. For the system with reliable judging and driving sections, the optimal shut-down logic can be determined based on the reliability information of the sensing section. (author)

  11. Safety Oversight of Decommissioning Activities at DOE Nuclear Sites

    The Defense Nuclear Facilities Safety Board (Board) is an independent federal agency established by Congress in 1988 to provide nuclear safety oversight of activities at U.S. Department of Energy (DOE) defense nuclear facilities. The activities under the Board's jurisdiction include the design, construction, startup, operation, and decommissioning of defense nuclear facilities at DOE sites. This paper reviews the Board's safety oversight of decommissioning activities at DOE sites, identifies the safety problems observed, and discusses Board initiatives to improve the safety of decommissioning activities at DOE sites. The decommissioning of former defense nuclear facilities has reduced the risk of radioactive material contamination and exposure to the public and site workers. In general, efforts to perform decommissioning work at DOE defense nuclear sites have been successful, and contractors performing decommissioning work have a good safety record. Decommissioning activities have recently been completed at sites identified for closure, including the Rocky Flats Environmental Technology Site, the Fernald Closure Project, and the Miamisburg Closure Project (the Mound site). The Rocky Flats and Fernald sites, which produced plutonium parts and uranium materials for defense needs (respectively), have been turned into wildlife refuges. The Mound site, which performed R and D activities on nuclear materials, has been converted into an industrial and technology park called the Mound Advanced Technology Center. The DOE Office of Legacy Management is responsible for the long term stewardship of these former EM sites. The Board has reviewed many decommissioning activities, and noted that there are valuable lessons learned that can benefit both DOE and the contractor. As part of its ongoing safety oversight responsibilities, the Board and its staff will continue to review the safety of DOE and contractor decommissioning activities at DOE defense nuclear sites

  12. Appraisal of Fire Safety Management Systems at Educational Buildings

    Nadzim N.

    2014-01-01

    Full Text Available Educational buildings are one type of government asset that should be protected, and they play an important role as temporary communal meeting places for children, teachers and communities. In terms of management, schools need to emphasize fire safety for their buildings. It is well known that fires are not only a threat to the building’s occupants, but also to the property and the school environment. A study on fire safety management has been carried out on schools that have recently experienced fires in Penang. From the study, it was found that the school buildings require further enhancement in terms of both active and passive fire protection systems. For instance, adequate fire extinguishers should be provided to the school and the management should inspect and maintain fire protection devices regularly. The most effective methods to increase the level of awareness on fire safety are by organizing related programs on the management of fire safety involving all staff, teachers and students, educational talks on the dangers of fire and important actions to take in the event of an emergency, and, lastly, to appoint particular staff to join the management safety team in schools.

  13. Remote mobile communication in safety support system

    Safety Support System (SSS) is a computerized operator support system for nuclear power plants, which is now under development. The concept of SSS covers 1) earlier detection of failure symptom and prediction of its influence to the plant operation, 2) improved transparency and robustness of plant control systems, 3) advanced human-machine interface and communication. The authors have been working on the third concept and proposed a remote mobile communication system called Plant Communication System (PCS). PCS aims to realize convenient communication between main control room and other areas such as plant local areas and site offices, using Personal Handyphone System (PHS) and wireless LAN (Local Area Network). PCS can transmit not only data but also graphic displays and dynamic video displays between the main control room and plant local areas. MPEG4 (Moving Picture Experts Group 4) technology is utilized in video data compression and decompression. The authors have developed the special multiplexing unit that connects PHS Cell Stations (CSs) and exiting coaxial cables. Voice recognition and announcement capability is also realized in the system, which enables verbal retrieval of information in the computer systems in the main control room from local areas. (author)

  14. Review of regulatory activities associated with safety culture and management of safety at UK nuclear installations

    The management of health and safety and the culture of the people who participate in the process have been fundamental to the development of the United Kingdom's nuclear power programme. In the early years of development, the organizations and systems set up in companies which designed, manufactured, constructed and operated nuclear power stations were based upon the best practices needed to ensure, not only the operability of the plant, but also the safety of the workers at the power stations and the public. Over the years the nuclear industry in the UK has changed as has the regulatory body responsible for licensing. The economic environment within which the nuclear electricity generators operate has caused them to review their business and organizational structures. The UK nuclear industry has developed its approach to health and safety management and it is generally recognized that commercially successful companies have excellent health and safety records. This paper discusses the importance of effective health and safety management to the maintenance of high safety standards and the delivery of business goals. It also discusses the model that has been developed to help assess safety management in the changing UK nuclear industry. Finally, it comments upon regulatory developments in management of safety and safety culture. (author)

  15. CEC activities in the field of LMFBR safety

    The aim of the ECC is to reach a common LMFBR Safety strategy in Europe. To this end the Commission promotes collaboration between the different fast reactor projects in the Community through working groups and collaborative arrangements and contributes with a research activity executed in its Joint Research Centre Ispra. A short description is given of the activity in the working groups and of the Ispra programme on LMFBR Safety. This programme covers: LMFBR thermohydraulics, fuel coolant interactions, dynamic structure loading and response, safety related material properties and whole core accident code development

  16. Study on application of safety checklist in preventive maintenance activities

    The paper describes the principles and the characteristics of safety checklist as a risk evaluation method. Examples of application of safety checklists to preventive maintenance activities such as criteria comparison and checkup items in place in nuclear power plants are illustrated in details with issues appeared in the checklist establishment. Checklist has a good application in the RCM analysis or in the actual preventive maintenance program for Chashma Nuclear Power Plant indicated by concrete instances. In the light of safety checklist which is used to sustain preventive maintenance as a simple and applicable risk analysis approach, we can get deep knowledge of risks of nuclear power plant to perfect preventive maintenance activities. (authors)

  17. Recent development in safety regulation of nuclear fuel cycle activities

    Through the effort of deliberation and legislation over five years, Japanese government structure was reformed this January, with the aim of realizing simple, efficient and transparent administration. Under the reform, the Agency for Nuclear and Industrial Safety (ANIS) was founded in the Ministry of Economy, Trade and Industry (METI) to be responsible for safety regulation of energy-related nuclear activities, including nuclear fuel cycle activities, and industrial activities, including explosives, high-pressure gasses and mining. As one of the lessons learned from the JCO criticality accident of September 1999, it was pointed out that government's inspection function was not enough for fuel fabrication facilities. Accordingly, new statutory regulatory activities were introduced, namely, inspection of observance of safety rules and procedures for all kinds of nuclear operators and periodic inspection of fuel fabrication facilities. In addition, in order to cope with insufficient safety education and training of workers in nuclear facilities, licensees of nuclear facilities are required by law to specify safety education and training for their workers. ANIS is committed to enforce these new regulatory activities effectively and efficiently. In addition, it is going to be prepared for, in its capacity of safety regulatory authority, future development of Japanese fuel cycle activities, including commissioning of JNFL Rokkasho reprocessing plant and possible application for licenses for JNFL MOX fabrication plant and for spent fuel interim storage facilities. (author)

  18. Recent development in safety regulation of nuclear fuel cycle activities

    Through the effort of deliberation and legislation over five years, Japanese government structure was reformed this January, with the aim of realizing simple, efficient and transparent administration. Under the reform, the Agency for Nuclear and Industrial Safety (ANIS) was founded in the Ministry of Economy, Trade and Industry (METI) to be responsible for safety regulation of energy-related nuclear activities, including nuclear fuel cycle activities, and industrial activities, including explosives, high-pressure gasses and mining. As one of the lessons learned from the JCO criticality accident of September 1999, it was pointed out that the government's inspection function was not enough for fuel fabrication facilities. Accordingly, new statutory regulatory activities were introduced, namely, inspection of observance of safety rules and procedures for all kinds of nuclear operators and periodic inspection of fuel fabrication facilities. In addition, in order to cope with insufficient safety education and training of workers in nuclear facilities, licensees of nuclear facilities are required by law to specify safety education and training for their workers. ANIS is committed to enforce these new regulatory activities effectively and efficiently. In addition, it is going to be prepared, in its capacity as safety regulatory authority, for future development of Japanese fuel cycle activities, including commissioning of JNFL Rokkasho reprocessing plant and possible application for licenses for JNFL MOX fabrication plant and for spent fuel interim storage facilities. (author)

  19. Reliability of thermal-hydraulic passive safety systems

    The scholar will be informed of reliability concepts applied to passive system adopted for nuclear reactors. Namely, for classical components and systems the failure concept is associated with malfunction of breaking of hardware. In the case of passive systems the failure is associated with phenomena. A method for studying the reliability of passive systems is discussed and is applied. The paper deals with the description of the REPAS (Reliability Evaluation of Passive Safety System) methodology developed by University of Pisa (UNIPI) and with results from its application. The general objective of the REPAS methodology is to characterize the performance of a passive system in order to increase the confidence toward its operation and to compare the performances of active and passive systems and the performances of different passive systems

  20. Workplace activities to promote small attempts for safety. Toward development of safety culture in a nuclear power plant

    Activities that could possibly grow into learning activities for developing safety culture were explored by intensive fieldwork in a nuclear power plant depending on Engestroem's activity theory. As a first step to achieve this goal, workers' small attempts that might contribute to nurturing a safety culture were investigated. Eight kinds of activity were observed and interpreted as having the possibility to facilitate small recognition and small practice, i.e., activities including (1) workgroup as community, (2) other workgroups and other departments as community, (3) meeting drawing remarks as mediating artifacts, (4) study session and Off-the-Job-Training as mediating artifact, (5) award as mediating artifact, (6) extended leave as mediating artifact, (7) check sheet as mediating artifact, and (8) skill-transfer system as mediating artifact. (author)

  1. Addressing firefighter safety around solar PV systems

    Harris, B. [Sustainable Energy Technologies, Calgary, AB (Canada)

    2010-11-15

    The article discussed new considerations for installing photovoltaic (PV) systems that address the needs of fire service personnel. The presence of a PV system presents a multitude of dangers for firefighters, including electrical shock, the inhalation of toxic gases from being unable to cut a hole through the roof, falling debris and flying glass, and dead loading on a compromised structure and tripping on conduits. Mapping systems should be modified so that buildings with PV systems are identified for first responders, including firefighters who should learn that solar modules present an electrical hazard during the day but not at night; covering PV modules with foam or salvage covers may not shut the system down to a safe level; it takes a few moments for the power in PV modules to reduce to zero; and PV modules or conduit should never be cut, broke, chopped, or walked upon. The California Department of Forestry and Fire Protection recommends creating pathways and allowing easier access to the roof by setting the modules back from roof edges, creating a structurally sound pathway for firefighters to walk on and space to cut ventilation holes. However, the setback rule makes the economics of solar installation less viable for residential applications. The technological innovations aimed at addressing system safety all focus on limiting firefighter contact with live electrical components to within the extra-low-voltage (ELV) band. Some of the inverters on the market that support ELV system architecture were described. 1 fig.

  2. Probabilistic safety assessment activities at Ignalina NPP

    The Barselina Project was initiated in the summer 1991. The project was a multilateral co-operation between Lithuania, Russia and Sweden up until phase 3, and phase 4 has been performed as a bilateral between Lithuania and Sweden. The long-range objective is to establish common perspectives and unified bases for assessment of severe accident risks and needs for remedial measures for the RBMK reactors. During phase 3, from 1993 to 1994, a full scope Probabilistic Safety Analysis (PSA) model of the Ignalina Nuclear Power Plant unit 2 was developed to identify possible safety improvement of risk importance. The probabilistic methodology was applied on a plant specific basis for a channel type reactor of RBMK design. During phase 4, from 1994 to 1996, the PSA was further developed, taking into account plant changes, improved modelling methods and extended plant information concerning dependencies (area events, dynamic effects, electrical and signal dependencies). The model reflected the plant status before the outage 1996. During phase 4+, 1998 to 1999 the PSA model was upgraded taking into account the newest plant modifications. The new PSA model of CPS/AZRT was developed. Modelling was based on the Single Failure Analysis

  3. Application of integrated safety management in decommissioning activities: ensuring the safety of workers throughout the changing environment of decommissioning

    The United States Department of Energy (DOE), Office of Environmental Management (EM) has successfully decommissioned several legacy facilities that were used in the development and manufacture of nuclear weapons. The DOE experience includes laboratories, raw material manufacturing, foundry, separation, reactor, reprocessing canyon, waste storage and repackaging facilities. Some of these facilities date back to the original Manhattan Project in the 1940s. Inventories include a range of isotopes and hazardous chemicals. The physical condition of the facilities and their safety systems also range in age and integrity. As each facility transitions through the decommissioning lifecycle the hazard profile and the available controls change with the facility. One of the most effective means the DOE has found to reliably manage the changing hazards is a strong system of safety management programs (SMPs) that address hazards in an integrated fashion. Statistics demonstrate that the most significant hazards to the worker during decommissioning activities result from industrial accidents. It is imperative that a foundation of strong safety management systems must identify hazards and coordinate between program areas to establish the most appropriate protective measure for the worker. This paper walks through examples to illustrate lessons learned through its decommissioning experience, including coordinating between programs such as electrical safety and radiological protection when both hazards are substantial in a given work evolution. The DOE has institutionalized its Integrated Safety Management System (ISMS) and routinely evaluates its contractors to ensure effective implementation. ISMS establishes the foundation for safe, efficient decommissioning of nuclear facilities. (author)

  4. Development of a system for safety indicators

    This R and D effort was carried out to support the introduction of safety performance indicators (SPIs) for the SKI inspections. The main goal was to compile and evaluate indicators currently in use by the Swedish utilities, and those proposed by the SKI. The main parts of the work performed were: - a compilation of safety performance indicators used by the utilities and those proposed by the SKI; - an assessment of selected important attributes for each SPI; - a description of the data collection processes; - an evaluation of how the currently used SPIs cover the various focus areas of the SKI yearly safety performance assessments for the plants; - a proposal of which SPIs to use for the 2002 assessments; - participation in reference group meetings. The utilities have used SPIs since the early 1990s. SPIs are regularly calculated and presented at plants and at corporate offices, and the SPIs are today an integrated part of the management systems. The selection of SPIs is based both on the WANO SPIs and on SPIs defined by the users themselves. The compilation shows that the utilities currently use well over 20 SPIs for follow-up of safety at the plants, including all of the 8 WANO SPIs. A SKI pilot project has proposed a number of SPIs for internal use. The basis is the reporting requirements according to regulations in SKIFS 1998:1, with its barrier- and defence-in-depth principles. A first implementation is planned for the 2002 safety assessments of plant performance. The SKI has in the report proposed use of 9 groups of SPIs. Several are identical or similar to those used by the utilities. An analysis of the data extracted from the SKI LER database STAGBAS implies some quality assurance problems i.e. data are not easily re-created. The data base itself though should be well fit for the application. Users within the Vattenfall group perform various aggregations of the SPIs, while others so far have only presented indicator data for the individual SPIs. Several of

  5. Accelerator driven systems from the radiological safety point of view

    P K Sarkar; Maitreyee Nandy

    2007-02-01

    In the proposed accelerator driven systems (ADS) the possible use of several milliamperes of protons of about 1 GeV incident on high mass targets like the molten lead–bismuth eutectic is anticipated to pose radiological problems that have so far not been encountered by the radiation protection community. Spallation reaction products like high energy gammas, neutrons, muons, pions and several radiotoxic nuclides including Po-210 complicate the situation. In the present paper, we discuss radiation safety measures like bulk shielding, containment of radiation leakage through ducts and penetration and induced activity in the structure to protect radiation workers as well as estimation of sky-shine, soil and ground water activation, release of toxic gases to the environment to protect public as per the stipulations of the regulatory authorities. We recommend the application of the probabilistic safety analysis technique by assessing the probability and criticality of different hazard-initiating events using HAZOP and FMECA.

  6. Safety assessment for facilities and activities. General safety requirements. Pt. 4

    The Safety Fundamentals publication, Fundamental Safety Principles, establishes principles for ensuring the protection of workers, the public and the environment, now and in the future, from harmful effects of ionizing radiation. The objective of this Safety Requirements publication is to establish the generally applicable requirements to be fulfilled in safety assessment for facilities and activities, with special attention paid to defence in depth, quantitative analyses and the application of a graded approach to the ranges of facilities and of activities that are addressed. The publication also addresses the independent verification of the safety assessment that needs to be carried out by the originators and users of the safety assessment. This publication is intended to provide a consistent and coherent basis for safety assessment across all facilities and activities, which will facilitate the transfer of good practices between organizations conducting safety assessments and will assist in enhancing the confidence of all interested parties that an adequate level of safety has been achieved for facilities and activities. The requirements, which are derived from the Fundamental Safety Principles, relate to any human activity that may cause people to be exposed to radiation risks arising from facilities and activities, as follows: Facilities includes: (a) Nuclear power plants; (b) Other reactors (such as research reactors and critical assemblies); (c) Enrichment facilities and fuel fabrication facilities; (d) Conversion facilities used to generate UF6; (e) Storage and reprocessing plants for irradiated fuel; (f) Facilities for radioactive waste management where radioactive waste is treated, conditioned, stored or disposed of; (g) Any other places where radioactive materials are produced, processed, used, handled or stored; (h) Irradiation facilities for medical, industrial, research and other purposes, and any places where radiation generators are installed; (i

  7. Safety Assessment for Facilities and Activities. General Safety Requirements. Pt. 4

    The Safety Fundamentals publication, Fundamental Safety Principles, establishes principles for ensuring the protection of workers, the public and the environment, now and in the future, from harmful effects of ionizing radiation.? read more The objective of this Safety Requirements publication is to establish the generally applicable requirements to be fulfilled in safety assessment for facilities and activities, with special attention paid to defence in depth, quantitative analyses and the application of a graded approach to the ranges of facilities and of activities that are addressed. The publication also addresses the independent verification of the safety assessment that needs to be carried out by the originators and users of the safety assessment. This publication is intended to provide a consistent and coherent basis for safety assessment across all facilities and activities, which will facilitate the transfer of good practices between organizations conducting safety assessments and will assist in enhancing the confidence of all interested parties that an adequate level of safety has been achieved for facilities and activities. The requirements, which are derived from the Fundamental Safety Principles, relate to any human activity that may cause people to be exposed to radiation risks arising from facilities and activities, as follows: Facilities includes: (a) Nuclear power plants; (b) Other reactors (such as research reactors and critical assemblies); (c) Enrichment facilities and fuel fabrication facilities; (d) Conversion facilities used to generate UF6; (e) Storage and reprocessing plants for irradiated fuel; (f) Facilities for radioactive waste management where radioactive waste is treated, conditioned, stored or disposed of; (g) Any other places where radioactive materials are produced, processed, used, handled or stored; (h) Irradiation facilities for medical, industrial, research and other purposes, and any places where radiation generators are

  8. System Interface for an Integrated Intelligent Safety System (ISS for Vehicle Applications

    Mahammad A. Hannan

    2010-01-01

    Full Text Available This paper deals with the interface-relevant activity of a vehicle integrated intelligent safety system (ISS that includes an airbag deployment decision system (ADDS and a tire pressure monitoring system (TPMS. A program is developed in LabWindows/CVI, using C for prototype implementation. The prototype is primarily concerned with the interconnection between hardware objects such as a load cell, web camera, accelerometer, TPM tire module and receiver module, DAQ card, CPU card and a touch screen. Several safety subsystems, including image processing, weight sensing and crash detection systems, are integrated, and their outputs are combined to yield intelligent decisions regarding airbag deployment. The integrated safety system also monitors tire pressure and temperature. Testing and experimentation with this ISS suggests that the system is unique, robust, intelligent, and appropriate for in-vehicle applications.

  9. Licensing process for safety-critical software-based systems

    Haapanen, P. [VTT Automation, Espoo (Finland); Korhonen, J. [VTT Electronics, Espoo (Finland); Pulkkinen, U. [VTT Automation, Espoo (Finland)

    2000-12-01

    System vendors nowadays propose software-based technology even for the most critical safety functions in nuclear power plants. Due to the nature of software faults and the way they cause system failures new methods are needed for the safety and reliability evaluation of these systems. In the research project 'Programmable automation systems in nuclear power plants (OHA)', financed together by the Radiation and Nuclear Safety Authority (STUK), the Ministry of Trade and Industry (KTM) and the Technical Research Centre of Finland (VTT), various safety assessment methods and tools for software based systems are developed and evaluated. As a part of the OHA-work a reference model for the licensing process for software-based safety automation systems is defined. The licensing process is defined as the set of interrelated activities whose purpose is to produce and assess evidence concerning the safety and reliability of the system/application to be licensed and to make the decision about the granting the construction and operation permissions based on this evidence. The parties of the licensing process are the authority, the licensee (the utility company), system vendors and their subcontractors and possible external independent assessors. The responsibility about the production of the evidence in first place lies at the licensee who in most cases rests heavily on the vendor expertise. The evaluation and gauging of the evidence is carried out by the authority (possibly using external experts), who also can acquire additional evidence by using their own (independent) methods and tools. Central issue in the licensing process is to combine the quality evidence about the system development process with the information acquired through tests, analyses and operational experience. The purpose of the licensing process described in this report is to act as a reference model both for the authority and the licensee when planning the licensing of individual applications

  10. Licensing process for safety-critical software-based systems

    System vendors nowadays propose software-based technology even for the most critical safety functions in nuclear power plants. Due to the nature of software faults and the way they cause system failures new methods are needed for the safety and reliability evaluation of these systems. In the research project 'Programmable automation systems in nuclear power plants (OHA)', financed together by the Radiation and Nuclear Safety Authority (STUK), the Ministry of Trade and Industry (KTM) and the Technical Research Centre of Finland (VTT), various safety assessment methods and tools for software based systems are developed and evaluated. As a part of the OHA-work a reference model for the licensing process for software-based safety automation systems is defined. The licensing process is defined as the set of interrelated activities whose purpose is to produce and assess evidence concerning the safety and reliability of the system/application to be licensed and to make the decision about the granting the construction and operation permissions based on this evidence. The parties of the licensing process are the authority, the licensee (the utility company), system vendors and their subcontractors and possible external independent assessors. The responsibility about the production of the evidence in first place lies at the licensee who in most cases rests heavily on the vendor expertise. The evaluation and gauging of the evidence is carried out by the authority (possibly using external experts), who also can acquire additional evidence by using their own (independent) methods and tools. Central issue in the licensing process is to combine the quality evidence about the system development process with the information acquired through tests, analyses and operational experience. The purpose of the licensing process described in this report is to act as a reference model both for the authority and the licensee when planning the licensing of individual applications. Many of the

  11. Instrumentation and Control Systems and Software Important to Safety for Research Reactors. Specific Safety Guide

    This Safety Guide provides recommendations and guidance on instrumentation and control systems and software important to safety for research reactors, including instrumentation and control system architecture and associated components, from sensors to actuators, operator interfaces and auxiliary equipment. It also provides recommendations on computer based systems and software, including software requirements and design, verification and validation, integration, and operation. This publication also addresses safety classification, design, implementation, qualification and operation of instrumentation as well as control systems. The recommendations and guidance apply to both the design and configuration management of instrumentation and control systems for new research reactors and the modernization of the instrumentation and control systems to existing research reactor facilities. In addition this Safety Guide provides recommendations and guidance on human factors engineering and human machine interfaces, and for computer based systems and software for use in instrumentation and control systems important to safety

  12. Identifying behaviour patterns of construction safety using system archetypes.

    Guo, Brian H W; Yiu, Tak Wing; González, Vicente A

    2015-07-01

    Construction safety management involves complex issues (e.g., different trades, multi-organizational project structure, constantly changing work environment, and transient workforce). Systems thinking is widely considered as an effective approach to understanding and managing the complexity. This paper aims to better understand dynamic complexity of construction safety management by exploring archetypes of construction safety. To achieve this, this paper adopted the ground theory method (GTM) and 22 interviews were conducted with participants in various positions (government safety inspector, client, health and safety manager, safety consultant, safety auditor, and safety researcher). Eight archetypes were emerged from the collected data: (1) safety regulations, (2) incentive programs, (3) procurement and safety, (4) safety management in small businesses (5) production and safety, (6) workers' conflicting goals, (7) blame on workers, and (8) reactive and proactive learning. These archetypes capture the interactions between a wide range of factors within various hierarchical levels and subsystems. As a free-standing tool, they advance the understanding of dynamic complexity of construction safety management and provide systemic insights into dealing with the complexity. They also can facilitate system dynamics modelling of construction safety process. PMID:25909389

  13. Stakeholder Safety in Information Systems Research

    R.H. Barbour

    2006-11-01

    Full Text Available Information Communication Technology (ICT researchers adapt and use tools from reference and cognate disciplines. This application of existing tools outside the context of their development has implications beyond the immediate problem context. ICT researchers have access to a wide variety of data sources including newer ones, such as the Internet, that may bring unexpected outcomes. ICT research can impact on researchers, their institutions and the researched in unexpected ways. People so affected are the stakeholders in ICT research activities. Reputations, welfare and property may be put at risk by unplanned events described in this paper. Legal aspects of ICT research are broadly identified and linked to the tort of negligence. The Social Research Association’s Code for researcher safety is described and its application extended to include the Internet as a potential data source. A common set of underlying ethical principles is identified suggesting that the ICT researcher can refine particular research protocols for specific social contexts.

  14. Safety evaluation by living probabilistic safety assessment. Procedures and applications for planning of operational activities and analysis of operating experience

    Living Probabilistic Safety Assessment (PSA) is a daily safety management system and it is based on a plant-specific PSA and supporting information systems. In the living use of PSA, plant status knowledge is used to represent actual plant safety status in monitoring or follow-up perspective. The PSA model must be able to express the risk at a given time and plant configuration. The process, to update the PSA model to represent the current or planned configuration and to use the model to evaluate and direct the changes in the configuration, is called living PSA programme. The main purposes to develop and increase the usefulness of living PSA are: Long term safety planning: To continue the risk assessment process started with the basic PSA by extending and improving the basic models and data to provide a general risk evaluation tool for analyzing the safety effects of changes in plant design and procedures. Risk planning of operational activities: To support the operational management by providing means for searching optimal operational maintenance and testing strategies from the safety point of view. The results provide support for risk decision making in the short term or in a planning mode. The operational limits and conditions given by technical specifications can be analyzed by evaluating the risk effects of alternative requirements in order to balance the requirements with respect to operational flexibility and plant economy. Risk analysis of operating experience: To provide a general risk evaluation tool for analyzing the safety effects of incidents and plant status changes. The analyses are used to: identify possible high risk situations, rank the occurred events from safety point of view, and get feedback from operational events for the identification of risk contributors. This report describes the methods, models and applications required to continue the process towards a living use of PSA. 19 tabs, 20 figs

  15. System Study: High-Pressure Safety Injection 1998–2013

    Schroeder, John Alton [Idaho National Lab. (INL), Idaho Falls, ID (United States). Risk Assessment and Management Services Dept.

    2015-02-01

    This report presents an unreliability evaluation of the high-pressure safety injection system (HPSI) at 69 U.S. commercial nuclear power plants. Demand, run hours, and failure data from fiscal year 1998 through 2013 for selected components were obtained from the Institute of Nuclear Power Operations (INPO) Consolidated Events Database (ICES). The unreliability results are trended for the most recent 10-year period while yearly estimates for system unreliability are provided for the entire active period. No statistically significant increasing or decreasing trends were identified in the HPSI results.

  16. Manual on maintenance of systems and components important to safety

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

  17. System Study: High-Pressure Safety Injection 1998-2014

    Schroeder, John Alton [Idaho National Lab. (INL), Idaho Falls, ID (United States). Risk Assessment and Management Services Dept.

    2015-12-01

    This report presents an unreliability evaluation of the high-pressure safety injection system (HPSI) at 69 U.S. commercial nuclear power plants. Demand, run hours, and failure data from fiscal year 1998 through 2014 for selected components were obtained from the Institute of Nuclear Power Operations (INPO) Consolidated Events Database (ICES). The unreliability results are trended for the most recent 10 year period, while yearly estimates for system unreliability are provided for the entire active period. No statistically significant increasing or decreasing trends were identified in the HPSI results.

  18. System Study: High-Pressure Safety Injection 1998–2012

    T. E. Wierman

    2013-10-01

    This report presents an unreliability evaluation of the high-pressure safety injection system (HPSI) at 69 U.S. commercial nuclear power plants. Demand, run hours, and failure data from fiscal year 1998 through 2012 for selected components were obtained from the Equipment Performance and Information Exchange (EPIX). The unreliability results are trended for the most recent 10 year period while yearly estimates for system unreliability are provided for the entire active period. No statistically significant increasing or decreasing trends were identified in the HPSI results.

  19. Safety system challenges in US commercial power reactors

    United States operating experience, especially the events at Three Mile Island Unit 2 in 1979, Salem Unit 1 in 1983, and Davis-Besse in 1985, has demonstrated that human errors should be expected, that multiple failures can occur, and that the frequency of challenge to safety systems is becoming an important consideration in the probability of a serious transient. To reduce challenges to plant safety, emphasis is shifting from just the mitigation of transients to attention to plant operating systems, the operator, and the routine activities of technicians. Since that date, over 300 reactor years of experience have been accumulated. The United States Nuclear Regulatory Commission (USNRC) has analysed that experience and this paper presents the safety system challenge information for that period (approximately three years). This experience and the root causes for the various challenges are discussed along with the efforts of the NRC and the US operating industry to reduce the frequency. Nuclear steam supply system (NSSS) vendors, utilities, and the Institute of Nuclear Power Operations of the US industry have formulated various programmes to reduce operational transients. Some of the highlights of these programmes are discussed. In addition to reducing the challenge frequency for the matured US plants, both the NRC and the utilities are engaged in programmes to improve substantially the learning curve in the first few years of plant operation. The NRC recently completed an evaluation of the causes for this behaviour. Selected results of this work are discussed. Invariably, these analyses of the US operating experience lead to an identification of the unreliability of some balance-of-plant systems. These balance-of-plant systems in some plants had little redundancy. NRC regulation strategy has not previously focused on this equipment since it was not directly considered to be safety related. Moreover, US plants vary in design, with little or no attention to

  20. Evaluation of CANDU safety-system calibration accuracy through monitoring

    CANDU operators are increasingly being required to demonstrate that estimated accuracies of the transmitters used to measure process variables in CANDU special safety systems are being achieved in operation. At present, this is done by recalibrating all transmitters periodically, typically every one to three years. Functional checks are performed more frequently. These include panel checks (i.e., visual monitoring and cross-comparison of redundant process measurements) and safety-system process-trip tests (i.e., valving-in test pressures to activate the alarm units). These functional tests provide assurance that transmitters and related circuits are working, but they are not always sufficiently sensitive to evaluate calibration accuracy. Continuous computerized monitoring of safety-system signals is being investigated as one approach to verifying safety-system calibration accuracy and transmitter functionality. Eventually, if successful, it may enable a reduction in the frequency of process trip testing (a labour-intensive, error-prone operation), or even the elimination of process trip tests and their associated hardware altogether. Using both Shutdown System (SDS) 1 and SDS2, it is possible to obtain at least three, and more often six, independent, redundant measurements of each of many process variables. If signals from the reactor regulating, containment and emergency coolant injection (ECI) systems are also used, then it is possible to obtain up to 13 independent, redundant measurements of many process variables. Assuming these measurements are truly independent, and that there are no common mode errors, calibration accuracy can be verified by intercomparing the nominally identical readings. A CANDU Owners Group (COG) R and D project was set up to evaluate this monitoring concept. This project has progressed through several phases: (1) data acquisition, (2) data analysis and algorithm development, and (3) on-line calibration analysis and operational experience

  1. Safety Justification of Software Systems. Software Based Safety Systems. Regulatory Inspection Handbook

    The introduction of new software based technology in the safety systems in nuclear power plants also makes it necessary to develop new strategies for regulatory review and assessment of these new systems that is more focused on reviewing the processes at the different phases in design phases during the system life cycle. It is a general requirement that the licensee shall perform different kinds of reviews. From a regulatory point of view it is more cost effective to assess that the design activities at the suppliers and the review activities within the development project are performed with good quality. But the change from more technical reviews over to the development process oriented approach also cause problems. When reviewing development and quality aspects there are no 'hard facts' that can be judged against some specified criteria, the issues are more 'soft' and are more to build up structure of arguments and evidences that the requirements are met. The regulatory review strategy must therefore change to follow the development process over the whole life cycle from concept phase until installation and operation. Even if we know what factors that is of interest we need some guidance on how to interpret and judge the information.For that purpose SKl started research activities in this area at the end of the 1990s. In the first phase, in co-operation with Gustav Dahll at the Halden project, a life cycle model was selected. For the different phases a qualitative influence net was constructed of the type that is used in Bayesian Believe Network together with a discussion on different issues involved. In the second phase of the research work, in co-operation with Norman Wainwright, a former NII inspector, information from a selection of the most important sources as guidelines, IAEA and EC reports etc, was mapped into the influence net structure (the total list on used sources are in the report). The result is presented in the form of questions (Q) and a

  2. Safety Justification of Software Systems. Software Based Safety Systems. Regulatory Inspection Handbook

    Dahll, Gustav (OECD Halden Project, Halden (NO)); Liwaang, Bo (Swedish Nuclear Power Inspectorate, Stockholm (Sweden)); Wainwright, Norman (Wainwright Safety Advice (GB))

    2006-07-01

    The introduction of new software based technology in the safety systems in nuclear power plants also makes it necessary to develop new strategies for regulatory review and assessment of these new systems that is more focused on reviewing the processes at the different phases in design phases during the system life cycle. It is a general requirement that the licensee shall perform different kinds of reviews. From a regulatory point of view it is more cost effective to assess that the design activities at the suppliers and the review activities within the development project are performed with good quality. But the change from more technical reviews over to the development process oriented approach also cause problems. When reviewing development and quality aspects there are no 'hard facts' that can be judged against some specified criteria, the issues are more 'soft' and are more to build up structure of arguments and evidences that the requirements are met. The regulatory review strategy must therefore change to follow the development process over the whole life cycle from concept phase until installation and operation. Even if we know what factors that is of interest we need some guidance on how to interpret and judge the information.For that purpose SKl started research activities in this area at the end of the 1990s. In the first phase, in co-operation with Gustav Dahll at the Halden project, a life cycle model was selected. For the different phases a qualitative influence net was constructed of the type that is used in Bayesian Believe Network together with a discussion on different issues involved. In the second phase of the research work, in co-operation with Norman Wainwright, a former NII inspector, information from a selection of the most important sources as guidelines, IAEA and EC reports etc, was mapped into the influence net structure (the total list on used sources are in the report). The result is presented in the form of

  3. Basic Requirements for Cables of Systems Important to NPP Safety

    In view of the need for equipment upgrades at Ukrainian nuclear power plants, the replacement of cables, as an integral part of any system, becomes important. There is no document in Ukraine that combines requirements for cables of systems important to nuclear safety. The paper systematizes the technical requirements of national regulatory documents on nuclear and radiation safety in relation to cable products. The most important requirements for selecting cables are fire safety, resistance to high temperatures, humidity and pressure, resistance to ionizing radiation, seismic resistance and electromagnetic compatibility. The use of cables in the NPP containment and safety systems imposes on them the most stringent requirements as regards nuclear and radiation safety in plant operation. The paper identifies features and operating conditions for cable lines as part of NPP safety systems and shows the general classification of cable products. Development of a regulatory document to combine requirements for cables of safety systems will facilitate their selection during upgrading.

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

    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)

  5. A study on LAN applications in nuclear safety systems

    It is a general tendency to digitalize the conventional relay based I and C systems in nuclear power plant. But, the digitalisation of nuclear safety systems has many a difficulty to surmount. The typical one thing of many difficulties is the data communication problem between local controllers and systems. The network architecture built with LAN (Local Area Network) in digital systems of the other industries are general. But in case of nuclear safety systems many considerations in point of safety and license are required to implement it in the field. In this parer, some considerations for applying LAN in nuclear safety systems were reviewed

  6. Coalmine Safety Assurance Information System Based on GIS

    LIU Qiao-xi; MAO Shan-jun; MA Ai-nai; MAO Yun-de; BAO Qing-guo

    2003-01-01

    The mine ventilation and safety is one of the most important factors to influence on the coal production.More attention has been paid to manage safety information in scientific, efficient, and real-time way. Therefore, it is important to develop a practical mine safety assurance information system (CSAIS). Based on analyzing the actual management mode for ventilation and safety on mine, the paper studies the structure and function of the mine safety assurance information system based on GIS in detail. Moreover, it also suggests some applications and solutions. By combining with the practical situation, the paper realizes the whole function of the present system.

  7. A Taxonomy of Fallacies in System Safety Arguments

    Greenwell, William S.; Knight, John C.; Holloway, C. Michael; Pease, Jacob J.

    2006-01-01

    Safety cases are gaining acceptance as assurance vehicles for safety-related systems. A safety case documents the evidence and argument that a system is safe to operate; however, logical fallacies in the underlying argument may undermine a system s safety claims. Removing these fallacies is essential to reduce the risk of safety-related system failure. We present a taxonomy of common fallacies in safety arguments that is intended to assist safety professionals in avoiding and detecting fallacious reasoning in the arguments they develop and review. The taxonomy derives from a survey of general argument fallacies and a separate survey of fallacies in real-world safety arguments. Our taxonomy is specific to safety argumentation, and it is targeted at professionals who work with safety arguments but may lack formal training in logic or argumentation. We discuss the rationale for the selection and categorization of fallacies in the taxonomy. In addition to its applications to the development and review of safety cases, our taxonomy could also support the analysis of system failures and promote the development of more robust safety case patterns.

  8. Needs for development of criticality safety evaluation system

    This paper provides an outline of development of a new criticality safety evaluation code system. The new system includes not only continuous energy Monte Carlo codes MVP and MCNP but also JACS code system traditionally used for criticality safety assessment of nuclear fuel cycle facility in Japan. The purpose of the new code system development is criticality safety evaluation of spent nuclear fuels taking burnup credit into account and error evaluation of criticality calculations. (author)

  9. Integrated Safety, Environmental and Emergency Management System (ISEEMS)

    The Risk Management and NEPA (National Environmental Policy Act) Department of Sandia National Laboratories/New Mexico (SNL/NM) recognized the need for hazard and environmental data analysis and management to support the line managers' need to know, understand, manage and document the hazards in their facilities and activities. The Integrated Safety, Environmental, and Emergency Management System (ISEEMS) was developed in response to this need. SNL needed a process that would quickly and easily determine if a facility or project activity contained only standard industrial hazards and therefore require minimal safety documentation, or if non-standard industrial hazards existed which would require more extensive analysis and documentation. Many facilities and project activities at SNL would benefit from the quick screening process used in ISEEMS. In addition, a process was needed that would expedite the NEPA process. ISEEMS takes advantage of the fact that there is some information needed for the NEPA process that is also needed for the safety documentation process. The ISEEMS process enables SNL line organizations to identify and manage hazards and environmental concerns at a level of effort commensurate with the hazards themselves by adopting a necessary and sufficient (graded) approach to compliance. All hazard-related information contained within ISEEMS is location based and can be displayed using on-line maps and building floor plans. This visual representation provides for quick assimilation and analysis

  10. 24 CFR 1006.220 - Crime prevention and safety activities.

    2010-04-01

    ... 24 Housing and Urban Development 4 2010-04-01 2010-04-01 false Crime prevention and safety... URBAN DEVELOPMENT NATIVE HAWAIIAN HOUSING BLOCK GRANT PROGRAM Eligible Activities § 1006.220 Crime... enforcement measures and activities appropriate to protect residents of affordable housing from...

  11. Plutonium finishing plant safety systems and equipment list

    The Safety Equipment List (SEL) supports Analysis Report (FSAR), WHC-SD-CP-SAR-021 and the Plutonium Finishing Plant Operational Safety Requirements (OSRs), WHC-SD-CP-OSR-010. The SEL is a breakdown and classification of all Safety Class 1, 2, and 3 equipment, components, or system at the Plutonium Finishing Plant complex

  12. Development and implementation of setpoint tolerances for special safety systems

    The establishment of tolerances and impairment limits for special safety system setpoints is part of the process whereby the plant operator demonstrates to the regulatory authority that the plant operates safely and within the defined plant licensing envelope. The licensing envelope represents the set of limits and plant operating state and for which acceptably safe plant operation has been demonstrated by the safety analysis. By definition, operation beyond this envelope contributes to overall safety system unavailability. Definition of the licensing envelope is provided in a wide range of documents including the plant operating licence, the safety report, and the plant operating policies and principles documents. As part of the safety analysis, limits are derived for each special safety system initiating parameter such that the relevant safety design objectives are achieved for all design basis events. If initiation on a given parameter occurs at a level beyond its limit, there is a potential reduction in safety system effectiveness relative to the performance credited in the plant safety analysis. These safety system parameter limits, when corrected for random and systematic instrument errors and other errors inherent in the process of periodic testing or calibration, are then used to derive parameter impairment levels and setpoint tolerances. This paper describes the methodology that has evolved at Ontario Hydro for developing and implementing tolerances for special safety system parameters (i.e., the shutdown systems, emergency coolant injection system and containment system). Tolerances for special safety system initiation setpoints are addressed specifically, although many of the considerations discussed here will apply to performance limits for other safety system components. The first part of the paper deals with the approach that has been adopted for defining and establishing setpoint limits and tolerances. The remainder of the paper addresses operational

  13. Asymptotic safety of gravity-matter systems

    Meibohm, J.; Pawlowski, J. M.; Reichert, M.

    2016-04-01

    We study the ultraviolet stability of gravity-matter systems for general numbers of minimally coupled scalars and fermions. This is done within the functional renormalization group setup put forward in [N. Christiansen, B. Knorr, J. Meibohm, J. M. Pawlowski, and M. Reichert, Phys. Rev. D 92, 121501 (2015).] for pure gravity. It includes full dynamical propagators and a genuine dynamical Newton's coupling, which is extracted from the graviton three-point function. We find ultraviolet stability of general gravity-fermion systems. Gravity-scalar systems are also found to be ultraviolet stable within validity bounds for the chosen generic class of regulators, based on the size of the anomalous dimension. Remarkably, the ultraviolet fixed points for the dynamical couplings are found to be significantly different from those of their associated background counterparts, once matter fields are included. In summary, the asymptotic safety scenario does not put constraints on the matter content of the theory within the validity bounds for the chosen generic class of regulators.

  14. Development of a safety parameter supervision system for Angra-1

    The Safety Parameter Supervision System (SSPS) which is a computerized system for monitoring essential parameters in real time, determining the safety status and emergency procedures for returning normal reactor operation, in case of an anomaly occurrence, is presented. The SSPS consists of three sub-systems: Integrated parameter monitoring system which gives to operators an integrated vision of values of a parameter set, able to detect any deviation of normal reactor operation; safety critical function system which evaluates safety status in terms of a safety critical function set appointed in advance, and in case of violation of any critical function, it initiates the adequate emergency procedure to return normal operation; and safety parameter computer system which carries out the arquirement of analogic and digital control signals of nuclear power plant. (M.C.K.)

  15. Safety Reviews of Technical System Modifications in the Nuclear Industry

    Falk, Thomas

    2013-01-01

    The function of safety reviews (here understood as expert judgements on proposals for design modifications and redesign of technical systems in commercial Nuclear Power Plants, supported by formalised safety review processes) plays a fundamental role for safety in nuclear installations. The primary aims of the presented case studies includes: critically examining and identifying the main areas for improvement of the existing technical safety review process as it is conducted at a Swedish nucl...

  16. NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security. Issue no. 4, June 2007

    This newsletter contains information on the Centre for Advanced Safety Assessment Tools (CASAT), the new strategy for the recovery of radioactive sources, the Technical Support Organization Conference and a message form the Director of the Division of Nuclear Installation Safety. To improve the efficiency of safety assessment methods, ensure transparency in their validation and application and establish an excellent knowledge base and training programmes, the IAEA's Centre for Advanced Safety Assessment Tools (CASAT) has therefore been formed. The Centre addresses the need for continuous technical support mechanisms for safety assessment methods. It provides support to Member States to enhance their safety assessment capabilities for present and future generations of nuclear systems, with a special focus on countries with a developing nuclear technology and nuclear safety infrastructure. It serves as a consolidated repository of relevant safety analysis knowledge, provides for focused training including advanced analytical simulations, and supports collaboration on safety assessment projects among Member States. The resources provided through CASAT include codes, models, databases, verification and validation information, analytical procedures and guides. The main purpose of the recently established Radioactive Source Technical Coordination Group (RSTCG) is to facilitate the technical coordination of activities of the IAEA related to the control and management of radioactive sources through the development of common approaches in technical matters and to advise the management of the relevant Divisions. It is the task of the RSTCG to provide the programme managers of the participating divisions/sections with a common opinion/advice on technical issues related to the control and management of radioactive sources. The RSTCG members obtain, inter alia from programme managers, information on all relevant project proposals, and share relevant materials in due time to

  17. Safety Classification of Structures, Systems and Components in Nuclear Power Plants. Specific Safety Guide

    This Safety Guide provides recommendations and guidance on how to meet the requirements established in Specific Safety Requirements No. SSR-2/1 and in General Safety Requirements No. GSR Part 4 for the identification of structures, systems and components (SSCs) important to safety in nuclear power plants and for their classification on the basis of their function and safety significance. This Safety Guide is intended primarily for use by organizations involved in the design of nuclear power plants, as well as by regulatory bodies and their technical support organizations. The Safety Guide can also be applied to other nuclear installations subject to appropriate adjustments relevant to the specific design of the type of the facility being considered

  18. The Management System for the Safe Transport of Radioactive Material. Safety Guide (Russian Edition)

    The purpose of this Safety Guide is to provide information to organizations that are developing, implementing or assessing a management system for activities relating to the transport of radioactive material. Such activities include, but are not limited to, design, fabrication, inspection and testing, maintenance, transport and disposal of radioactive material packaging. This publication is intended to assist those establishing or improving a management system to integrate safety, health, environmental, security, quality and economic elements to ensure that safety is properly taken into account in all activities of the organization

  19. Construction of SuperKEKB safety system based on CSS

    The KEKB operation was terminated on 2010/6/30 and the construction of SuperKEKB started. The safety system is being upgraded step by step. The EPICS (Experimental Physics and Industrial Control System) that had been adopted for the KEKB control system, was introduced to the safety system. EPCIS has been used also in other accelerators control system, such as AR, BT and Damping Ring. A variety of drawing tool is increased by introducing EPICS. The OPI of old safety system had been developed with a software tool based on FIX-FA. For the new safety system, the OPI (Operator Interface) base on CSS (Control System Studio) BOY, is chosen as a software tool, because it fits EPICS framework. Moreover, CSS Archiver is chosen as a logging software. This report shows present status and recent developments of KEKB/PF-AR safety system based on CSS BOY and CSS Archiver. (author)

  20. Plant assessment system and safety culture

    The government, upon these events, keenly felt the necessity for developing the safety culture which was already forwarded in nuclear industries and started taking actions to propagate it to all parts of society. The government established a social safety director position under the Prime Minister's jurisdiction and also established a Safety Culture Promotion Headquarters in which 7 ministries and other organizations, such as Korea Economic Council, Federation of Korea Trade Union and Women's Federation Council were participating. In accordance with the government's strong will to enhance the safety consciousness of people, safety campaigns are being developed voluntarily in the private sector. The formation of non-governmental organizations, such as People's Central Council of Safety Culture Promotion, shows a good example of such movement

  1. Cognitive Radio Network (CRN) System for Vehicle Safety Applications

    Lim, Jae Han

    2014-01-01

    As the number of vehicle accidents increases, car manufacturers and academic researchers have developed a vehicular safety system. The key component of the safety system is vehicular communications, by which vehicles exchange their local status information with neighbor vehicles and disseminate a warning message within a specified area. The challenge lies in satisfying stringent communication requirements of the safety system, extremely reliable packet delivery and low communication latency. ...

  2. Vehicle Safety Enhancement System: Sensing and Communication

    Huihuan Qian; Yongquan Chen; Yuandong Sun; Niansheng Liu; Ning Ding; Yangsheng Xu; Guoqing Xu; Yunjian Tang; Jingyu Yan

    2013-01-01

    With the substantial increase of vehicles on road, driving safety and transportation efficiency have become increasingly concerned focus from drivers, passengers, and governments. Wireless networks constructed by vehicles and infrastructures provide abundant information to share for the sake of both enhanced safety and network efficiency. This paper presents the systematic research to enhance the vehicle safety by wireless communication, in the aspects of information acquisition through vehic...

  3. Further activities of safety culture toward nuclear transportation industry

    On September 30, 1999, a criticality accident occurred at the uranium processing facility of the JCO Co. Ltd. (hereinafter referred to as ''JCO'') Tokai plant, located in Tokaimura, Ibaraki Prefecture. This was an unprecedented accident in Japan's history of peaceful use of nuclear power, resulting in three workers exposed to severe radiation, two of whom died, and the evacuation and enforced indoor confinement of local residents. Nuclear power suppliers must take personal responsibility for ensuring safety. In this connection, the electric power industry, heavy electric machinery manufacturers, fuel fabricators, and nuclear power research organizations gathered together to establish the Nuclear Safety Network (NSnet) in December 1999, based on the resolve to share and improve the level of the safety culture across the entire nuclear power industry and to assure that such an accident never occurs again. NSnet serves as a link between nuclear power enterprises, research organizations, and other bodies, based on the principles of equality and reciprocity. A variety of activities are pursued, such as diffusing a safety culture, implementing mutual evaluation among members, and exchanging safety-related information. Aiming to share and improve the safety culture throughout the entire nuclear power industry, NSnet thoroughly implements the principle of safety first, while at the same time making efforts to restore trust in nuclear power

  4. Safety analysis and evaluation methodology for fusion systems

    Three issues are critical to the public acceptability of nuclear fusion as an energy system. These are technological feasibility, economic viability and safety. Safety will be especially important when tritium is used as a fuel and the reactor becomes radioactive. As a result of this study a safety analysis and evaluation methodology for fusion systems were developed. In this all the safety-related issues in the fusion system could be integrated and resolved. A general descriptive model, the three principle items to be assured, an approach to safety assurance based on event categorization and the function based safety analysis are all discussed. The usefulness of the methodology was illustrated by the application of the safety evaluation to the R-Tokamak. (author)

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

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

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

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

    2001-02-01

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

  7. A systems engineering approach to implementation of safety management systems in the Norwegian fishing fleet

    The fishing industry is plagued by a long history of fatality and injury occurrence. Commercial fishing is hence recognized as the most dangerous and difficult of professional callings, in all jurisdictions. Fishing vessels have their own unique set of hazards, a myriad collection of complex occupational accident potentials, barely controlled, co-existing in a perilous work environment. The work in this article is directed by the Norwegian Systematic Health, Environmental and Safety Activities in Enterprises (1997) (Internal Control Regulations [1]), the ISM Code [2] for vessels and their recent applicability to the fishing fleet of Norway. Both safety management works place requirements on the vessel operators and crew to actively manage safety as an on-going concern. The application of these safety management system (SMS) control documents to fishing vessels is just the latest instalment in a continual drive to improve safety in this sector. The difficulty is that there has been no previous systematic approach to safety within the fishing fleet. This article uses the tenants of systems engineering to determine the requirements for such a SMS, detailing the limiting factors and restrictive issues of this complex operating environment. - Highlights: • Systems engineer is applied as a tool for determining requirements for design and construction of a safety management system (SMS). • Outlining a simplistic format, identifying, designingand facilitating improvement opportunities in the conduction and application of SMS’s on fishing vessels. • Knowledge provision is a key requirement of management systems, through provision of understanding, detail orientation and applicable skills for realization. • Outlining, what is to be done and how it is to be completed to accomplish compliance with pertinent legislative requirements. • Promoting a combination of documentation and communication arrangements by which the actionsnecessary for management can be

  8. Safety systems and features of boiling and pressurized water reactors

    The safe operation of nuclear power plants (NPP) requires a deep understanding of the functioning of physical processes and systems involved. This study was carried out to present an overview of the features of safety systems of boiling and pressurized water reactors that are available commercially. Brief description of purposes and functions of the various safety systems that are employed in these reactors was discussed and a brief comparison between the safety systems of BWRs and PWRs was made in an effort to emphasize of safety in NPPs.(Author)

  9. Automated Safety Incident Surveillance and Tracking System (ASISTS)

    Department of Veterans Affairs — The Automated Safety Incident Surveillance and Tracking System (ASISTS) is a repository of Veterans Health Administration (VHA) employee accident data. Many types...

  10. Perspectives of expert systems for nuclear reactor safety

    There is a wide range of possible expert system applications in the field of nuclear reactor safety: - in the safety-oriented design review of reactor systems, here particularly for subsequent modifications indicated by operating experience; - for safety analyses, (nuclear plant analyser, fault free analysis); - for operational safety engineering including accident management (diagnostic systems); - for maintenance and training purposes. The potentials of expert systems are based on the following factors: storage of information in the knowledge base, efficient use of extensive data bases, intensive interactive mode operation, rapid development of prototypes. (orig./DG)

  11. Problems of Rural Food Safety and Strategies of Constructing Supervision System

    2011-01-01

    This paper expounds the practical necessity of constructing diversified rural food safety supervision system as follows: it is the necessary requirements of guaranteeing people’s health and life safety; it is an important component of governmental function of social management and the logical extension of administrative responsibilities; it is the basis of maintaining order of rural society and constructing harmonious society. The main problems existing in the supervision of rural food safety are analyzed as follows: first, the legislative work of rural food safety lags behind to some extent; second, the supervision of governmental departments on rural food safety is insufficient; third, the industrial supervision mechanism of rural food security is not perfect; fourth, the role of rural social organizations in supervising food safety is limited; fifth, the farmers’ awareness of food safety supervision is not strong. Based on these problems, the targeted strategies of constructing diversified rural food safety supervision system are put forward as follows: accelerate the legislation of rural food safety, and ensure that there are laws to go by; give play to the dominant role of government, and strengthen administrative supervision on rural food safety; perfect industrial convention of rural food safety, and improve industrial supervision mechanism; actively support the fostering of social organizations, and give play to the role of supervision of organizations; cultivate correct concept of rights and obligations of farmers, and form awareness of food safety supervision.

  12. Safety System Designs and Characteristics of the 4S

    The 4S (Super-Safe, Small and Simple) is a small-sized, sodium-cooled fast reactor with a reflector-controlled core. The 4S design includes features such as 'no on-site refueling', 'passive safety' and 'low maintenance requirements'. In this paper, the safety design and safety features are described. The reactor shutdown system consists of two redundant and diverse systems, as does the residual heat removal system and either system can remove 100% of the core decay heat. The containment system consists of a guard vessel and a top dome. Measures to exclude any previously identified accident initiators have been applied to the 4S reflector drive, EMP and the steam generator. A 4S safety analysis has been carried out and demonstrates that the safety acceptance criteria is satisfied and the safety of 4S is confirmed. (author)

  13. SAFETY MARGIN CRITERION OF NONLINEAR UNBALANCE ELASTIC AXLE SYSTEM

    陈予恕; 李银山; 薛禹胜

    2003-01-01

    The safety margin criterion of nonlinear dynamic question of an elastic rotor system are given. A series of observing spaces were separated from integral space by resolving and polymerizing method. The stable-state trajectory of high dimensional nonlinear dynamic systems was got within integral space. According to international standard of rotor system vibration, energy limits of safety criterion were determined. The safety margin was calculated within a series of observing spaces by comparative positive-area criterion (CPAC) method. A quantitative example calculating safety margin for unbalance elastic rotor system was given by CPAC. The safety margin criterion proposed includes the calculation of current stability margin in engineering. This criterion is an effective method to solve quantitative calculation question of safety margin and stability margin for nonlinear dynamic systems.

  14. Analyzing Software Requirements Errors in Safety-Critical, Embedded Systems

    Lutz, Robyn R.

    1993-01-01

    This paper analyzes the root causes of safety-related software errors in safety-critical, embedded systems. The results show that software errors identified as potentially hazardous to the system tend to be produced by different error mechanisms than non- safety-related software errors. Safety-related software errors are shown to arise most commonly from (1) discrepancies between the documented requirements specifications and the requirements needed for correct functioning of the system and (2) misunderstandings of the software's interface with the rest of the system. The paper uses these results to identify methods by which requirements errors can be prevented. The goal is to reduce safety-related software errors and to enhance the safety of complex, embedded systems.

  15. Summary of the Safety Culture Activities in HANARO of KAERI

    The definition of safety culture in HANARO takes the IAEA's definition and it is the assembly of characteristics of attitudes in the HANARO center and individuals which establishes that, as an overriding priority, the HANARO safety issues receive the attention warranted by their significance. Since the power operation of HANARO started in 1996, HANARO has been operated for about 11 years and its degree of utilization and the number of experimental facilities have increased. This achievement is partly due to the spread of safety culture to the operators and the reactor users. In this paper, the safety culture activities done by the HANARO center of KAERI are described, and its efforts necessary for an improvement of it are presented

  16. Design an optimum safety policy for personnel safety management - A system dynamic approach

    Personnel safety management (PSM) ensures that employee's work conditions are healthy and safe by various proactive and reactive approaches. Nowadays it is a complex phenomenon because of increasing dynamic nature of organisations which results in an increase of accidents. An important part of accident prevention is to understand the existing system properly and make safety strategies for that system. System dynamics modelling appears to be an appropriate methodology to explore and make strategy for PSM. Many system dynamics models of industrial systems have been built entirely for specific host firms. This thesis illustrates an alternative approach. The generic system dynamics model of Personnel safety management was developed and tested in a host firm. The model was undergone various structural, behavioural and policy tests. The utility and effectiveness of model was further explored through modelling a safety scenario. In order to create effective safety policy under resource constraint, DOE (Design of experiment) was used. DOE uses classic designs, namely, fractional factorials and central composite designs. It used to make second order regression equation which serve as an objective function. That function was optimized under budget constraint and optimum value used for safety policy which shown greatest improvement in overall PSM. The outcome of this research indicates that personnel safety management model has the capability for acting as instruction tool to improve understanding of safety management and also as an aid to policy making

  17. Design an optimum safety policy for personnel safety management - A system dynamic approach

    Balaji, P. [The Glocal University, Mirzapur Pole, Delhi- Yamuntori Highway, Saharanpur 2470001 (India)

    2014-10-06

    Personnel safety management (PSM) ensures that employee's work conditions are healthy and safe by various proactive and reactive approaches. Nowadays it is a complex phenomenon because of increasing dynamic nature of organisations which results in an increase of accidents. An important part of accident prevention is to understand the existing system properly and make safety strategies for that system. System dynamics modelling appears to be an appropriate methodology to explore and make strategy for PSM. Many system dynamics models of industrial systems have been built entirely for specific host firms. This thesis illustrates an alternative approach. The generic system dynamics model of Personnel safety management was developed and tested in a host firm. The model was undergone various structural, behavioural and policy tests. The utility and effectiveness of model was further explored through modelling a safety scenario. In order to create effective safety policy under resource constraint, DOE (Design of experiment) was used. DOE uses classic designs, namely, fractional factorials and central composite designs. It used to make second order regression equation which serve as an objective function. That function was optimized under budget constraint and optimum value used for safety policy which shown greatest improvement in overall PSM. The outcome of this research indicates that personnel safety management model has the capability for acting as instruction tool to improve understanding of safety management and also as an aid to policy making.

  18. Design an optimum safety policy for personnel safety management - A system dynamic approach

    Balaji, P.

    2014-10-01

    Personnel safety management (PSM) ensures that employee's work conditions are healthy and safe by various proactive and reactive approaches. Nowadays it is a complex phenomenon because of increasing dynamic nature of organisations which results in an increase of accidents. An important part of accident prevention is to understand the existing system properly and make safety strategies for that system. System dynamics modelling appears to be an appropriate methodology to explore and make strategy for PSM. Many system dynamics models of industrial systems have been built entirely for specific host firms. This thesis illustrates an alternative approach. The generic system dynamics model of Personnel safety management was developed and tested in a host firm. The model was undergone various structural, behavioural and policy tests. The utility and effectiveness of model was further explored through modelling a safety scenario. In order to create effective safety policy under resource constraint, DOE (Design of experiment) was used. DOE uses classic designs, namely, fractional factorials and central composite designs. It used to make second order regression equation which serve as an objective function. That function was optimized under budget constraint and optimum value used for safety policy which shown greatest improvement in overall PSM. The outcome of this research indicates that personnel safety management model has the capability for acting as instruction tool to improve understanding of safety management and also as an aid to policy making.

  19. Convoy active safety technologies war fighter experiment II

    Schoenherr, Edward W.

    2009-01-01

    The operational ability to project and sustain forces in distant, anti-access and area denial environments poses new challenges for combatant commanders. One of the new challenges is the ability to conduct sustainment operations at operationally feasible times and places on the battlefield. Combatant commanders require a sustainment system that is agile, versatile, and survivable throughout the range of military operations and across the spectrum of conflict. A key component of conducting responsive, operationally feasible sustainment operations is the ability to conduct sustainment convoys. Sustainment convoys are critical to providing combatant commanders the right support, at the right time and place, and in the right quantities, across the full range of military operations. The ability to conduct sustainment convoys in a variety of hostile environments require force protection measures that address the enemy threat and protect the Soldier. One cost effective, technically feasible method of increasing the force protection for sustainment convoys is the use of robotic follower technology and autonomous navigation. The Convoy Active Safety Technologies (CAST) system is a driver assist, convoy autopilot technology aimed to address these issues. The CAST Warfigher Experiment II, being held at The Nevada Automotive Test Center in the fall of 2008, will continue analysis of the utility of this vehicle following technology not only in measures of system integrity and performance vs. manual driving, but also the physiological effects on the operators themselves. This paper will detail this experiment's methodology and analysis. Results will be presented at the SPIE Electronic Imaging 2009 symposium.

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

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

  1. Optimization of safety system test frequency

    Full text: A longstanding feature of Canadian research reactor safety philosophy is a requirement to be able to demonstrate, via periodic testing, that the reactor trip (scram) safety system is meeting a target unavailability (Q) of 10-3 for each trip parameter. The historical basis of this stringent requirement can be traced back to the recommendations made subsequent to the NRX reactor accident of 1952. This paper discusses details of the long term historical improvements made to the 125 MW NRU research reactor trip system test verification program. The reactor trip parameters are based on both triplicated and quadruplicated, independent channelized systems. Testing frequencies were originally set using engineering judgement, but can now be confidently optimized. The unavailability formulas, used in conjunction with the test result data originally assumed complete independence between the trip parameter channels, to demonstrate compliance with the required target. Assuming independent channels for the unavailability model has, however, historically raised uncertainty in the demonstrated predictions for Q, for two reasons. Firstly, only in recent years have common cause failure (CCF) quantification models been developed for redundant systems. Secondly there is a significant absence of quality generic data, to validate the various CCF unavailability model parameters. The model chosen to represent the unavailability was the Multiple Greek Letter (MGL) method. This is more accurate in principle than using a simple beta factor CCF model. The beta factor CCF model does not provide credit for the high multiplicity systems, particularly those with quadruplicated redundancy. Without data to represent the MGL CCF parameters though, use of the MGL model is still not practical. With over 25 years of well documented NRU historical test data, from 27 different multi-channel trip parameters, is was possible to derive values for CCF parameters to an accuracy where use of the MGL

  2. Safety evalution of cryptography modules within safety related control systems for railway applications

    Maria Franekova; Marek Vyrostko

    2011-01-01

    The paper deals with the problem of safety evaluation of cryptographic modules used within safety-related control system for applications with increasing safety integrity level. The requirements to cryptographic tec...

  3. Safety management systems and their role in achieving high standards of operational safety

    Achieving high standards of operational safety requires a robust management framework that is visible to all personnel with responsibility for its implementation. The structure of the management framework must ensure that all processes used to manage safety interlink in a logical and coherent manner, that is, they form a management system that leads to continuous improvement in safety performance. This Paper describes BNFL's safety management system (SMS). The SMS has management processes grouped within 5 main elements: 1. Policy, 2. Organisation, 3. Planning and Implementation, 4. Measuring and Reviewing Performance, 5. Audit. These elements reflect the overall process of setting safety objective (from Policy), measuring success and reviewing the performance. Effective implementation of the SMS requires senior managers to demonstrate leadership through their commitment and accountability. However, the SMS as a whole reflects that every employee at every level within BNFL is responsible for safety of operations under their control. The SMS therefore promotes a proactive safety culture and safe operations. The system is formally documented in the Company's Environmental, Health and Safety (EHS) Manual. Within in BNFL Group, the Company structures enables the Manual to provide overall SMS guidance and co-ordination to its range of nuclear businesses. Each business develops the SMS to be appropriate at all levels of its organisation, but ensuring that each level is consistent with the higher level. The Paper concludes with a summary of BNFL's safety performance. (author)

  4. Safety applications of computer based systems for the process industry

    Computer based systems, generally referred to as Programmable Electronic Systems (PESs) are being increasingly used in the process industry, also to perform safety functions. The process industry as they intend in this document includes, but is not limited to, chemicals, oil and gas production, oil refining and power generation. Starting in the early 1970's the wide application possibilities and the related development problems of such systems were recognized. Since then, many guidelines and standards have been developed to direct and regulate the application of computers to perform safety functions (EWICS-TC7, IEC, ISA). Lessons learnt in the last twenty years can be summarised as follows: safety is a cultural issue; safety is a management issue; safety is an engineering issue. In particular, safety systems can only be properly addressed in the overall system context. No single method can be considered sufficient to achieve the safety features required in many safety applications. Good safety engineering approach has to address not only hardware and software problems in isolation but also their interfaces and man-machine interface problems. Finally, the economic and industrial aspects of the safety applications and development of PESs in process plants are evidenced throughout all the Report. Scope of the Report is to contribute to the development of an adequate awareness of these problems and to illustrate technical solutions applied or being developed

  5. A safety-based decision making architecture for autonomous systems

    Musto, Joseph C.; Lauderbaugh, L. K.

    1991-01-01

    Engineering systems designed specifically for space applications often exhibit a high level of autonomy in the control and decision-making architecture. As the level of autonomy increases, more emphasis must be placed on assimilating the safety functions normally executed at the hardware level or by human supervisors into the control architecture of the system. The development of a decision-making structure which utilizes information on system safety is detailed. A quantitative measure of system safety, called the safety self-information, is defined. This measure is analogous to the reliability self-information defined by McInroy and Saridis, but includes weighting of task constraints to provide a measure of both reliability and cost. An example is presented in which the safety self-information is used as a decision criterion in a mobile robot controller. The safety self-information is shown to be consistent with the entropy-based Theory of Intelligent Machines defined by Saridis.

  6. Activities Related to Safety Regulations of Spent Fuel Interim Storage at Japan Nuclear Energy Safety Organization

    Major research activities in safety regulation of spent fuel interim storage at JNES are presented. In Japan, the first license application was approved by the government in May 2010 and the design and construction method will be submitted to the regulatory authority NISA soon. A commencement of its operation is expected at December 2012. In its plan, dual purpose metal casks for storage and transport will be stored in a concrete building for about 50 years, and then they will be transported to a spent fuel reprocessing facility. When they will be shipped out after the storage, no visual inspection for cask internals will be scheduled. Major reason of no visual inspection is to avoid any radiation exposure from contingent incident during opening the casks lid. JNES as TSO has conducted research activities to support NISA. Before the license application, those activities focused on three areas. The first area was to investigate fundamental safety function of the cask, that is, confinement, shielding, heat removal and subcriticality. Especially, a long term performance of the safety function was key issues. The second one was to confirm integrity of spent fuel cladding during the storage. The third one was to improves and verify the computer codes and/or methods for safety evaluation of the spent fuel interim storage facilities. In usual safety review process in Japan, NISA sometimes asks JNES to perform independent analysis and check the adequacy of the safety analysis conducted by licensees. After the approval of the license application, the applicant should have approvals of “design and construction method”, the welding inspection of the cask and the pre-service inspection. JNES is now supporting to prepare the criteria of the design and construction method. (author)

  7. Development of web-based safety review advisory system

    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

  8. Propulsion system safety analysis methodology for commercial transport aircraft

    Knife, S.

    1997-01-01

    Airworthiness certification of commercial transport aircraft requires a safety analysis of the propulsion system to establish that the probability of a failure jeopardising the safety of the aeroplane is acceptably low. The needs and desired features of such a propulsion system safety analysis are discussed, and current techniques and assumptions employed in such analyses are evaluated. It is concluded that current assumptions and techniques are not well suited to predicting...

  9. Research on the Evaluation System for Rural Public Safety Planning

    Sun, Ming; YAN, Jianxin

    2014-01-01

    The indicator evaluation system is introduced to the study of rural public safety planning in this article. By researching the current rural public safety planning and environmental carrying capacity, we select some carrying capacity indicators influencing the rural public safety, such as land, population, ecological environment, water resources, infrastructure, economy and society, to establish the environmental carrying capacity indicator system. We standardize the indicators, use gray corr...

  10. Nuclear power plants. Electrical equipment of the safety system. Qualification

    This International Standard applies to electrical parts of safety systems employed at nuclear power plants, including components and equipment of any interface whose failure could affect unfavourably properties of the safety system. The standard also applies to non-electrical safety-related interfaces. Furthermore, the standard describes the generic process of qualification certification procedures and methods of qualification testing and related documentation. (P.A.)

  11. Specifying Safety Monitors for Autonomous Systems using Model-checking

    Machin, Mathilde; Dufossé, Fanny; Blanquart, Jean-Paul; Guiochet, Jérémie; Powell, David; Waeselynck, Hélène

    2014-01-01

    International audience Autonomous systems operating in the vicinity of humans are critical in that they potentially harm humans. As the complexity of autonomous system software makes the zero-fault objective hardly at- tainable, we adopt a fault-tolerance approach. We consider a separate safety channel, called a monitor, that is able to partially observe the sys- tem and to trigger safety-ensuring actuations. A systematic process for specifying a safety monitor is presented. Hazards are fo...

  12. Safety control program for complex system based on behavior science

    LIANG Mei-jian; YANG Guang; CHEN Da-wei

    2008-01-01

    To control complex system's safety effectively, safety control program was supported based on the principles of behavioral science that shapes organizational be-havior, and organizational behavior produced individual behavior. The program can be structured into a model that consists of three modules including individual behavior rectifi-cation, organization behavior diagnosis and model of safety culture. The research result not only reveals the deep cause of complex system accidents but also provides structural descriptions with the accidents cause.

  13. Safety control program for complex system based on behavior science

    LIANG Mei-jian; YANG Guang; CHEN Da-wei

    2008-01-01

    To control complex system's safety effectively,safety control program was supported based on the principles of behavioral science that shapes organizational behavior,and organizational behavior produced individual behavior.The program can be structured into a model that consists of three modules including individual behavior rectification,organization behavior diagnosis and model of safety culture.The research result not only reveals the deep cause of complex system accidents but also provides structural descriptions with the accidents cause.

  14. Research on the improvement of nuclear safety -Thermal hydraulic tests for reactor safety system-

    The present research aims at the development of the thermal hydraulic verification test technology for the safety system of the conventional and advanced nuclear power plant and the development of the advanced thermal hydraulic measuring techniques. In this research, test facilities simulating the primary coolant system and safety system are being constructed for the design verification tests of the existing and advanced nuclear power plant. 97 figs, 14 tabs, 65 refs. (Author)

  15. Research on the improvement of nuclear safety -Thermal hydraulic tests for reactor safety system-

    Jung, Moon Kee; Park, Choon Kyung; Yang, Sun Kyoo; Chun, Se Yung; Song, Chul Hwa; Jun, Hyung Kil; Jung, Heung Joon; Won, Soon Yun; Cho, Yung Roh; Min, Kyung Hoh; Jung, Jang Hwan; Jang, Suk Kyoo; Kim, Bok Deuk; Kim, Wooi Kyung; Huh, Jin; Kim, Sook Kwan; Moon, Sang Kee; Lee, Sang Il [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-06-01

    The present research aims at the development of the thermal hydraulic verification test technology for the safety system of the conventional and advanced nuclear power plant and the development of the advanced thermal hydraulic measuring techniques. In this research, test facilities simulating the primary coolant system and safety system are being constructed for the design verification tests of the existing and advanced nuclear power plant. 97 figs, 14 tabs, 65 refs. (Author).

  16. Upgrade of accelerator radiation safety system for SPring-8 (2)

    Radiation safety interlock system for the SPring-8 accelerator complex, which protects personnel from radiation hazard induced by electron beams and synchrotron radiation, has been operating over a decade. In the past 10 years, the accelerator was upgraded to extend accelerator/beam-transport areas, and it was implemented new functions. The safety interlock system was also extended. The extended radiation safety interlock system had the complicated safety logic to handle the upgraded accelerator because the safety interlock system was closely related to “Operation MODE” of the accelerator, which is the combination of accelerator/beam-transport areas in operation. This circumstance provoked extensive discussions on the design of new radiation safety interlock system to satisfy the requirements and smooth migration from the old system to the new one. The construction of the new radiation safety interlock system was finalized in September 2010. And the system started the user operation in October 2010. We will report the design of the new radiation safety interlock system and introduction results. (author)

  17. System and safety studies of accelerator driven transmutation systems

    The research on safety of Accelerator-Driven Transmutation Systems (ADS) at the department has been focused on: a) ADS core design and development of advanced nuclear fuel optimised for high transmutation rates and good safety features; b) analysis of ADS-dynamics c) computer code and nuclear data development relevant for simulation and optimization of ADS; d) participation in ADS experiments including 1 MW spallation target manufacturing, subcritical experiments MUSE (CEA-Cadarache). Moreover, during the reporting period the EU-project 'IABAT', co-ordinated by the department has been finished and 4 other projects have been initiated in the frame of the 5th European Framework Programme. Most of the research topics reported in this paper are referred to appendices, which have been published in the open literature. The topics, which are not yet published, are described here in more details

  18. System and safety studies of accelerator driven transmutation systems

    Gudowski, W.; Wallenius, J.; Tucek, K.; Eriksson, Marcus; Carlsson, Johan; Seltborg, P.; Cetnar, J. [Royal Inst. of Technology, Stockholm (Sweden). Dept. of Nuclear and Reactor Physics

    2001-05-01

    The research on safety of Accelerator-Driven Transmutation Systems (ADS) at the department has been focused on: a) ADS core design and development of advanced nuclear fuel optimised for high transmutation rates and good safety features; b) analysis of ADS-dynamics c) computer code and nuclear data development relevant for simulation and optimization of ADS; d) participation in ADS experiments including 1 MW spallation target manufacturing, subcritical experiments MUSE (CEA-Cadarache). Moreover, during the reporting period the EU-project 'IABAT', co-ordinated by the department has been finished and 4 other projects have been initiated in the frame of the 5th European Framework Programme. Most of the research topics reported in this paper are referred to appendices, which have been published in the open literature. The topics, which are not yet published, are described here in more details.

  19. Application of model systems in nanobiotechnology safety

    Full text : Last 10-15 years the human civilization, as a result of fast development of biotechnology, cases of new and known illnesses and increase of danger of bioterrorism, collides with new biological dangers. Now, all necessity of actions for biology for prevention of possible dangers admits. Nanobiotechnological researches and offers on application of the scientific results reached in this area prevail of all others. And thus, in many cases or it is at all left outside of attention possible harmful effects of application in an expert of nanoparticles, or it is limited to researches on subcellular level. Adequate results can be received only in case of carrying out of such researches on organism level. Greater prospects in this area have the model systems consisting the culture of unicellular green seaweed, on which now we have been studying the ionizing radiation influence effects. It speaks that on behalf of such cultures we have simultaneously cellular, organism and population levels of the structural organization. Some optimal laboratory methods of maintenance and propagating of this unicellular green seaweed have already been developed. The way offered was a studying at cellular-organism level of the structural organization of effects of action on vital systems of nanoparticles (especially what are offered for application in pharmaceutics) with use of culture of unicellular green seaweed Chlamydomonas reinhardti. Genes of many enzymes of this eucariotic seaweed are established, and also its perspective value in biological synthesis of hydrogen is shown. Studying of negative effects of action of nanoparticles in an example of the object, many molecular features of which are investigated, will allow to establish borders of safety of all biosystems.

  20. The relationship between safety net activities and hospital financial performance

    Khan Nasreen

    2010-01-01

    Full Text Available Abstract Background During the 1990's hospitals in the U.S were faced with cost containment charges, which may have disproportionately impacted hospitals that serve poor patients. The purposes of this paper are to study the impact of safety net activities on total profit margins and operating expenditures, and to trace these relationships over the 1990s for all U.S urban hospitals, controlling for hospital and market characteristics. Methods The primary data source used for this analysis is the Annual Survey of Hospitals from the American Hospital Association and Medicare Hospital Cost Reports for years 1990-1999. Ordinary least square, hospital fixed effects, and two-stage least square analyses were performed for years 1990-1999. Logged total profit margin and operating expenditure were the dependent variables. The safety net activities are the socioeconomic status of the population in the hospital serving area, and Medicaid intensity. In some specifications, we also included uncompensated care burden. Results We found little evidence of negative effects of safety net activities on total margin. However, hospitals serving a low socioeconomic population had lower expenditure raising concerns for the quality of the services provided. Conclusions Despite potentially negative policy and market changes during the 1990s, safety net activities do not appear to have imperiled the survival of hospitals. There may, however, be concerns about the long-term quality of the services for hospitals serving low socioeconomic population.

  1. Software for the occupational health and safety integrated management system

    Vătăsescu, Mihaela [University Politehnica Timisoara, Department of Engineering and Management, 5 Revolutiei street, 331128 Hunedoara (Romania)

    2015-03-10

    This paper intends to present the design and the production of a software for the Occupational Health and Safety Integrated Management System with the view to a rapid drawing up of the system documents in the field of occupational health and safety.

  2. Software for the occupational health and safety integrated management system

    This paper intends to present the design and the production of a software for the Occupational Health and Safety Integrated Management System with the view to a rapid drawing up of the system documents in the field of occupational health and safety

  3. Safety Characteristics in System Application Software for Human Rated Exploration

    Mango, E. J.

    2016-01-01

    NASA and its industry and international partners are embarking on a bold and inspiring development effort to design and build an exploration class space system. The space system is made up of the Orion system, the Space Launch System (SLS) and the Ground Systems Development and Operations (GSDO) system. All are highly coupled together and dependent on each other for the combined safety of the space system. A key area of system safety focus needs to be in the ground and flight application software system (GFAS). In the development, certification and operations of GFAS, there are a series of safety characteristics that define the approach to ensure mission success. This paper will explore and examine the safety characteristics of the GFAS development.

  4. IAEA activities on safety aspects of NPP ageing

    A review of IAEA activities concerned with safety aspects of nuclear power plants ageing is given for the period from 1995 to 1998 with the prospects till year 2000. Coordinated Research programs were conducted on Management Ageing of Concrete Containment Buildings; Management of Ageing of In-Containment I and C cables. TECDOCs were published on Assessment and Management of Ageing of Major NPP Components Important for Safety of CANDU, PWR and BWR NPPs. Technical Committee Meetings and Interregional training courses concerned with the same subjects were held

  5. Role of quality management system in ensuring of NPP safety

    The article describes some system factors of the accident on Chornobyl NPP in 1986. The analysis shows that we can improve the safety of nuclear power plants through the implementation of integrated management systems.

  6. DOE standard: Integration of environment, safety, and health into facility disposition activities. Volume 1: Technical standard

    NONE

    1998-05-01

    This Department of Energy (DOE) technical standard (referred to as the Standard) provides guidance for integrating and enhancing worker, public, and environmental protection during facility disposition activities. It provides environment, safety, and health (ES and H) guidance to supplement the project management requirements and associated guidelines contained within DOE O 430.1A, Life-Cycle Asset Management (LCAM), and amplified within the corresponding implementation guides. In addition, the Standard is designed to support an Integrated Safety Management System (ISMS), consistent with the guiding principles and core functions contained in DOE P 450.4, Safety Management System Policy, and discussed in DOE G 450.4-1, Integrated Safety Management System Guide. The ISMS guiding principles represent the fundamental policies that guide the safe accomplishment of work and include: (1) line management responsibility for safety; (2) clear roles and responsibilities; (3) competence commensurate with responsibilities; (4) balanced priorities; (5) identification of safety standards and requirements; (6) hazard controls tailored to work being performed; and (7) operations authorization. This Standard specifically addresses the implementation of the above ISMS principles four through seven, as applied to facility disposition activities.

  7. An Investigation of Safety Improvements using Additional Safety Class Instrument Air System in Nuclear Power Plant

    An additional safety class instrument air (IA) system delivers air to safety class air operated valves (AOVs) such as pressurizer PORVs, the steam generator PORVs, and auxiliary feedwater modulation valves related to natural circulation, when a loss of offsite power (LOOP) occurs. This paper analyzes the risk change before and after installing the new IA system based on the probabilistic safety assessment (PSA) methodology. This approach identifies the cause of the risk reduction through a detailed cutset investigation and measures the importance of the added components and human error. Three main conclusions were elicited: there was a 64.6%∼99.1% reduction in the unavailability of the supporting system related to the safety AOVs, a 19.1% CDF reduction due to the new IA system, and the importance measures of human error were decreased

  8. An Investigation of Safety Improvements using Additional Safety Class Instrument Air System in Nuclear Power Plant

    Bae, Yeon Kyoung; Chi, Moon Goo [Korea Hydro and Nuclear Power Co., Daejeon (Korea, Republic of); Kim, Hak Seon [Korea Hydro and Nuclear Power Co., Busan (Korea, Republic of)

    2011-08-15

    An additional safety class instrument air (IA) system delivers air to safety class air operated valves (AOVs) such as pressurizer PORVs, the steam generator PORVs, and auxiliary feedwater modulation valves related to natural circulation, when a loss of offsite power (LOOP) occurs. This paper analyzes the risk change before and after installing the new IA system based on the probabilistic safety assessment (PSA) methodology. This approach identifies the cause of the risk reduction through a detailed cutset investigation and measures the importance of the added components and human error. Three main conclusions were elicited: there was a 64.6%{approx}99.1% reduction in the unavailability of the supporting system related to the safety AOVs, a 19.1% CDF reduction due to the new IA system, and the importance measures of human error were decreased.

  9. Thermal hydraulic tests for reactor safety system -Research on the improvement of nuclear safety-

    The present research aims at the development of the thermal hydraulic verification test technology for the reactor safety system of the conventional and advanced nuclear power plant and the development of the advanced thermal hydraulic measuring techniques. (Author)

  10. CONTROL COMMAND SYSTEMS IMPACT ON THE RAILWAY OPERATIONAL SAFETY

    Marek Pawlik

    2015-04-01

    Full Text Available Purpose. Safety is seen as a must, for railway transport market. However it is not so obvious what does safety exactly mean as it means different things for different experts. Showing safety ensured by control command systems as a component of the railway operational safety and pointing associated challenges especially those arising from subdivision of the national railway system into different entities. Methodology. To achieve this purpose control command and signalling systems keeping safe distances between trains, preventing setting conflicting train routs, locking of the mobile elements of the switches, protecting the level crossings, enabling safe incorporation of additional trains were analyzed. Findings. Article analyses how control command system influence operational safety taking into account safety of the control-command system itself, interfaces on one side between signalling systems and control command system and on the other side between control command system and vehicle control systems, transmission, maintenance, and operation in degraded modes of running. Originality. New and high-effective scope of tests which are necessary for putting new control command installation into service both track-side and on-board are proposed. Practical value. Control command implementations will significantly improve operational safety, however it is possible only when recommendations defined in this article are taken into account. This means that all the components including interfaces have to meet acceptable hazard rate 10E-9 and have to be properly design, constructed, assembled and maintained, all taking into account whole chain of functions performed and supervised by different railway entities.

  11. Radiation safety interlock system at Indus accelerator complex

    A Radiation Safety Interlock System (a part of Radiation Safety System) that ensures protection of personnel during the facility operation from radiation hazards induced by electron beam and synchrotron radiation has been in operation very effectively for over a decade at Indus Accelerator complex (IAC). Radiation Safety Interlock System (RSIS) consists of two parts - Safety Interlock Unit (SIU) and Mode Selection Unit (MSU). Separate Safety Interlock Units are provided for four machine areas of IAC, namely Microtron and Booster, Indus-1 storage ring, Indus-1 user hall and Indus-2 storage ring. The efficacy of the Safety Interlock Units of Indus-1 user hall, Indus-1 storage ring and Indus-2 storage ring is governed by the operation modes that are selected through Mode Selection Unit. RSIS has been modified during past 1 and 1/2 year by addition of new interlock features and changes in the final beam control scheme. Machine Safety Interlock System (MSIS) was also interlocked with RSIS to facilitate termination of machine operation in case of any unsafe condition of Indus-2 systems. This paper describes the design philosophy, recent modifications, implementation and future upgrade plans of the present Radiation Safety Interlock Systems at Indus accelerator complex. (author)

  12. Guidance for software safety planning in digital protection systems

    Real-time embedded software used in nuclear reactor protection systems is an area where software safety planning must be subject to highly rigorous and systematic analysis. Recently, the safety planning for safety-critical software systems is being recognized as the most important phase in the software life cycle and is currently leading to new regulatory positions and standards by the regulatory and the standardization organizations. The requirements for software of digital protection systems are described in such standards as, for example, the new Standard Review Plan, International Electrochemical Commission (IEC) 880 supplements, Institute of Electrical and Electronics Engineers (IEEE) Standard 1228-1994, IEEE Standard 7-4.3.2-1993, and International Atomic Energy Agency (IAEA) Safety Series No. 50-SG-D3 and D8 which are being updated. Most of them describe mandatory requirements, what shall be done, for safety-critical software. The vendors of software-based safety systems have developed their own work practices for developing the software. However, there has been much controversy between the licenser and the licensee over whether work practices satisfy regulatory requirements and whether the safety of a system developed by work practices is justified. We believe that the controversy is caused by a gap between the mandatory requirements (what) and the work practices (how). We have developed a guidance to fill such a gap, which can be useful to both licenser and licensee to justify the safety in the planning phase of software development for nuclear reactor protection systems

  13. Safety analysis and evaluation methodology for fusion systems

    A synthesized methodology of safety analysis and evaluation for general fusion systems is proposed. In the course of the methodology development, its main frame has been constructed in order to take account of all safety-related items and to ensure a logical consistency. The safety-related items are divided broadly into two groups. One of them is the public protection from radiological hazard, which is introduced as a safety requirement from an external viewpoint for the fusion system. The other items are the matter from an internal viewpoint and are related to the fusion system behavior in itself. These items are composed of the understanding of a fusion system, the safety ensuring principle and the function based safety analysis. All of these items have been mapped on the frame, considering the mutual relations, among them, consistently. To complete the methodology development, the safety evaluation for the actual design of a fusion system has been performed in conformity to this methodology. Thus, it has been demonstrated that the methodology proposed here is appropriate to the safety analysis and evaluation for the fusion system. (author). 9 refs, 4 figs, 2 tabs

  14. Reliability assessment of CEFR protection and safety monitoring system

    Nuclear safety is always the focus of public concern. At present, probabilistic safety assessment is one of the standard methods to assess the safety of nuclear power plants. It is also necessary to use probabilistic method to do the reliability analysis of each system of the nuclear power plant. China Experimental Fast Reactor (CEFR) is the first pool type sodium cooling fast breeder reactor in China. It is significant to carry through its probabilistic safety assessment and reliability analysis. In this paper, the fault trees of CEFR protection and safety monitoring system are constructed. The unavailability, importance, sensitivity and uncertainty are calculated. The common cause failures of the components in the typical positions are assessed. The analysis results indicate that the distribution of system minimal cut sets is well-proportioned. The design of this system is balanced, and do not have obvious weakness. The requirements of reactor shutdown during abnormal events are satisfied. (authors)

  15. HIGH VOLTAGE SAFETY MANAGEMENT SYSTEM OF ELECTRIC VEHICLE

    2008-01-01

    In order to improve the drivability and energy efficiency of electric vehicle (EV), more and more batteries are connected in series with high voltage which makes it necessary to monitor the electric parameters of high voltage system (HVS) to ensure the high voltage safety. A high voltage safety management system is developed to solve this critical issue. Several key electric parameters including pre-charge, contact resistance, insulation resistance and remaining capacity are monitored and analyzed based on the presented equivalent models. An electronic unit called high voltage safety controller is developed. By the help of hardware-in-loop system, the equivalent models integrated in the high voltage safety controller are validated and the on-line electric parameters monitor strategy is discussed. The real vehicle experiment results indicate that the high voltage safety management system designed is suitable for EV application.

  16. Technical feasibility and reliability of passive safety systems for nuclear power plants. Proceedings of an advisory group meeting

    The meeting provided an overview of the key issues on passive safety. Technical problems which may affect future deployment, and the operating experience of passive systems and components, as well as, definitions of passive safety terms, were discussed. Advantages and disadvantages of passive systems were also highlighted. The philosophy behind different passive safety systems was presented and the range of possibility between fully passive and fully active systems was discussed. Refs, figs, tabs

  17. A formal safety analysis for PLC software-based safety critical system using Z

    This paper describes a formal safety analysis technique which is demonstrated by performing empirical formal safety analysis with the case study of beamline hutch door Interlock system that is developed by using PLC (Programmable Logic Controller) systems at the Pohang Accelerator Laboratory. In order to perform formal safety analysis, we have built the Z formal specifications representation from user requirement written in ambiguous natural language and target PLC ladder logic, respectively. We have also studied the effective method to express typical PLC timer component by using specific Z formal notation which is supported by temporal history. We present a formal proof technique specifying and verifying that the hazardous states are not introduced into ladder logic in the PLC-based safety critical system. And also, we have found that some errors or mismatches in user requirement and final implemented PLC ladder logic while analyzing the process of the consistency and completeness of Z translated formal specifications. In the case of relatively small systems like Beamline hutch door interlock system, a formal safety analysis including explicit proof is highly recommended so that the safety of PLC-based critical system may be enhanced and guaranteed. It also provides a helpful benefits enough to comprehend user requirement expressed by ambiguous natural language

  18. Tank waste remediation system nuclear criticality safety program management review

    BRADY RAAP, M.C.

    1999-06-24

    This document provides the results of an internal management review of the Tank Waste Remediation System (TWRS) criticality safety program, performed in advance of the DOE/RL assessment for closure of the TWRS Nuclear Criticality Safety Issue, March 1994. Resolution of the safety issue was identified as Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-40-12, due September 1999.

  19. Safety Verification of Interconnected Hybrid Systems Using Barrier Certificates

    Guobin Wang; Jifeng He; Jing Liu; Haiying Sun; Zuohua Ding; Miaomiao Zhang

    2016-01-01

    Safety verification determines whether any trajectory starting from admissible initial states would intersect with a set of unsafe states. In this paper, we propose a numerical method for verifying safety of a network of interconnected hybrid dynamical systems with a state constraint based on bilinear sum-of-squares programming. The safety verification is conducted by the construction of a function of states called barrier certificate. We consider a finite number of interconnected hybrid syst...

  20. Tank waste remediation system nuclear criticality safety program management review

    This document provides the results of an internal management review of the Tank Waste Remediation System (TWRS) criticality safety program, performed in advance of the DOE/RL assessment for closure of the TWRS Nuclear Criticality Safety Issue, March 1994. Resolution of the safety issue was identified as Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-40-12, due September 1999

  1. Safety Inspection System Based on the Internet of Things

    Dong-Tao Hu; Yu-Jie Wang; Jian Chen; Ying Sun

    2013-01-01

    The Safety inspection system uses the Internet of things technology to identify the location of mobile terminal automatically and bring up the correspondent safety inspection table through the equipments of Hand-hold Terminal and specific location wireless router. Inspection information including the inspection results, photos or video can be transport to general platform for storing and processing through the wireless network immediately. The process of safety i...

  2. Development of a risk-informed safety management system at the Gentilly-2 Nuclear Generating Station

    Komljenovic, D.; Hotte, G.; Beaudet, M. [Hydro-Quebec, Nuclear Generating Station Gentilly-2, Gentilly, Quebec (Canada)], E-mail: komljenovic.dragan@hydro.qc.ca

    2009-07-01

    The paper presents an overview regarding current and future activities related to the management of safety and regulatory framework at the Gentilly-2 Nuclear Generating Station. The paper discusses alignment of these activities with the best Canadian and international practices. It also proposes manners to develop a consistent risk-informed safety management system. The paper takes particularly into consideration the impact of this new framework on the refurbishment project, and the operations after the refurbishment of the station. (author)

  3. Design requirements of communication architecture of SMART safety system

    To develop the communication network architecture of safety system of SMART, the evaluation elements for reliability and performance factors are extracted from commercial networks and classified the required-level by importance. A predictable determinacy, status and fixed based architecture, separation and isolation from other systems, high reliability, verification and validation are introduced as the essential requirements of safety system communication network. Based on the suggested requirements, optical cable, star topology, synchronous transmission, point-to-point physical link, connection-oriented logical link, MAC (medium access control) with fixed allocation are selected as the design elements. The proposed architecture will be applied as basic communication network architecture of SMART safety system

  4. From passive vehicle safety to integrated safety systems. The evolution of crash safety; Von der passiven Fahrzeugsicherheit zum vernetzten Sicherheitsystem. Eine Entwicklungsgeschichte

    Hahn, W. [Opel (A.) AG, Ruesselsheim (Germany)

    2004-07-01

    The centennial of automotive manufacturing in Zwickau provides a fitting occasion to take a look back at a special subdiscipline of vehicle development, namely crash safety. Conceptions of ''safety'' have changed considerably in the course of automotive history. Originally, safety was merely understood to mean the rigidity of the vehicle body. Later, measures relating to energy management at the body front end led to the development of a complex deformation structure which was required to function optimally in a wide variety of accident constellations. In car body design, the objective of crash safety has widened from its original focus on self-protection to include the protection of the other party. Today, crash safety is foremost aimed at ensuring vehicle compatibility. Developments in occupant safety systems have been equally dramatic. The central element of occupant safety continues to be the safety belt, which has evolved from a static, manually adjustable belt into a complex device with pyrotechnical and electrical retractors and variable force limiters. New potentials for improving crash safety are being tapped in the form of electronic sensing systems for occupants and the vehicle environment. However, further progress from here will require considerably higher expenditures. Significant improvements in vehicle safety will in future only be achievable through the integration of active and passive safety with vehicle communication and environment sensing systems. [German] Das hundertjaehrige Bestehen des Automobilbaus in der Stadt Zwickau gibt den Anlass zum Rueckblick auf ein spezielles Gebiet der Fahrzeugentwicklung, die Unfallsicherheit. Im Verlauf der Entwicklungsgeschichte des Automobils wandelte sich das Verstaendnis des Begriffs 'Sicherheit' massgeblich. Urspruenglich wurden darunter nur die Steifigkeit der Karosserie verstanden. Ueber Massnahmen zum Energiemanagement im Vorderbau vollzog sich ein Weg zur komplexen

  5. The development of regulatory expectations for computer-based safety systems for the UK nuclear programme

    The Nuclear Installations Inspectorate (NII) of the UK's Health and Safety Executive (HSE) has completed a review of their Safety Assessment Principles (SAPs) for Nuclear Installations recently. During the period of the SAPs review in 2004-2005 the designers of future UK naval reactor plant were optioneering the control and protection systems that might be implemented. Because there was insufficient regulatory guidance available in the naval sector to support this activity the Defence Nuclear Safety Regulator (DNSR) invited the NII to collaborate with the production of a guidance document that provides clarity of regulatory expectations for the production of safety cases for computer based safety systems. A key part of producing regulatory expectations was identifying the relevant extant standards and sector guidance that reflect good practice. The three principal sources of such good practice were: IAEA Safety Guide NS-G-1.1 (Software for Computer Based Systems Important to Safety in Nuclear Power Plants), European Commission consensus document (Common Position of European Nuclear Regulators for the Licensing of Safety Critical Software for Nuclear Reactors) and IEC nuclear sector standards such as IEC60880. A common understanding has been achieved between the NII and DNSR and regulatory guidance developed which will be used by both NII and DNSR in the assessment of computer-based safety systems and in the further development of more detailed joint technical assessment guidance for both regulatory organisations. (authors)

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

    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

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

    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

  8. Integrated Passive Safety System (IPSS) for Ultimate Safe Nuclear Power Plants

    Chang, Soon Heung; Kim, Sang Ho; Choi, Jae Young [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)

    2012-05-15

    The integrity of reactor core could be preserved if there was a passive safety system enough to remove the decay heat in the Fukushima accident. Also, even if the core was molten and there was no electrical power, the reactor vessel would not be damaged and the release of radioactive materials could be prevented by using safety systems of containment cooling and filtered venting. Not only for the Fukushima accident, there is a possibility that a nuclear power plant can experience a severe accident in a case of SBO (Station Black Out). Even if it is sure that the reasonable proportion of active and passive safety system has to be considered based on the safety and economics of a nuclear power plant, the researches to enhance the safety of a nuclear power plant must be continued for the future. In order to solve the problem and enhance the safety of nuclear power plants, integrated passive safety system (IPSS) is proposed. It is the wholly passive system by natural phenomena like gravity, natural circulation and pressure difference. The purpose of this paper is to propose the conceptual design of the integrated passive safety system and make the overall evaluation of IPSS characters

  9. When the Safety System Fails the Worker: Did We Do Our Job?...A Case Study

    McConnell, S

    2006-02-03

    As safety professionals, we strive to implement a robust safety process in our organizations to maximize worker protection. We sell our philosophy and ideas to senior management, and then work with line management and the work force to develop and implement the safety process. Through this effort, we are likely to accomplish two major objectives. First, we obtain buy-in from line management and the workers, maybe even ownership for the safety process we implement. Second, we increase the likelihood that the hazards (and necessary controls) associated with the work activities performed by our workforce are identified and addressed by the safety process we implement. Our ambition is to maximize safety and health in the work place, and prevent injuries. Realizing this goal improves overall business operations. Petersen suggests an accident is an indication of something wrong in the management system (Petersen, pg 15). Successful organizations operate with the safety process fully integrated into the management system. If the management system fails, the safety process has failed the worker. As safety professionals, we must ask ourselves whether we did our job adequately. The better organizations strive for continuous improvement. The overall success of safety processes, in terms of accident and injury prevention has improved since safety professionals have learned to involve line management and the workers in the process. Although we maintain the label of 'safety expert', our role has shifted somewhat to that of a 'facilitator' in the process. The role of the safety professional is to advise and counsel line management (Kohn & Ferry, pg 28). Line management owns safety! If you subscribe to this philosophy, our role of advisor to line management makes perfect sense. Most safety professionals no longer operate as the 'safety cop'. That role belongs to line management. Instead, our role falls into the category of 'oversight' or

  10. Cost/benefit analyses of reactor safety systems

    The study presents a methodology for quantitative assessment of the benefit yielded by the various engineered safety systems of a nuclear reactor containment from the standpoint of their capacity to protect the environment compared to their construction costs. The benefit is derived from an estimate of the possible damage from which the environment is protected, taking account of the probabilities of occurrence of malfunctions and accidents. For demonstration purposes, the methodology was applied to a 1 300-MWe PWR nuclear power station. The accident sequence considered was that of a major loss-of-coolant accident as investigated in detail in the German risk study. After determination of the benefits and cost/benefit ratio for the power plant and the containment systems as designed, the performance characteristics of three subsystems, the leakoff system, annulus exhaust air handling system and spray system, were varied. For this purpose, the parameters which describe these systems in the activity release programme were altered. The costs were simultaneously altered in order to take account of the performance divergences. By varying the performance of the individual sub-systems an optimization in design of these systems can be arrived at

  11. Safety analysis and evaluation methodology for fusion systems

    Fusion systems which are under development as future energy systems have reached a stage that the break even is expected to be realized in the near future. It is desirable to demonstrate that fusion systems are well acceptable to the societal environment. There are three crucial viewpoints to measure the acceptability, that is, technological feasibility, economy and safety. These three points have close interrelation. The safety problem is more important since three large scale tokamaks, JET, TFTR and JT-60, start experiment, and tritium will be introduced into some of them as the fusion fuel. It is desirable to establish a methodology to resolve the safety-related issues in harmony with the technological evolution. The promising fusion system toward reactors is not yet settled. This study has the objective to develop and adequate methodology which promotes the safety design of general fusion systems and to present a basis for proposing the R and D themes and establishing the data base. A framework of the methodology, the understanding and modeling of fusion systems, the principle of ensuring safety, the safety analysis based on the function and the application of the methodology are discussed. As the result of this study, the methodology for the safety analysis and evaluation of fusion systems was developed. New idea and approach were presented in the course of the methodology development. (Kako, I.)

  12. Safety evaluation of the KNICS digital reactor protection system

    Korean Nuclear I and C System (KNICS) project, a national research program for developing a safety-class digital system, has designed a new reactor protection system (RPS). The usage of digital equipment in a safety critical application increases the importance of a risk evaluation since microprocessors and software technologies make the digital system very complex and their unavailability is hard to quantify. This paper addresses the safety evaluation of the KNICS RPS in consideration of the several technical concerns of a safety modeling for a digital system. We also present the fault-tree modeling technique and the risk evaluation results. A fault-tree model which includes the common cause failure events, the coverage of a fault-tolerant mechanism and the software failure event is developed. Based on the minimal cut sets of the model, we discuss the system unavailability of the newly developed design of the KNICS RPS

  13. Study of system safety evaluation on LTO of national project. NISA safety research project on system safety of nuclear power plants

    Japanese safety regulatory body, that is, Nuclear and Industrial Safety Agency (NISA) started a 5-year national safety research project as 'the first stage' from 2006 FY to 2010 FY whose objective is 'Improve the technical information basis in order to utilize knowledge as well as information related to ageing management and maintenance of NPPs. Fukushima disaster happened in March 2011, and the priority of research needs for ageing management dramatically changed in Japan. The second-stage national project started in October 2011 with the concept of 'system safety' of NNPs where not only ageing management on degradation phenomena of important components but also safety management on total plant systems are paid attention to. The second-stage project is so called 'Japanese Ageing Management Program for System Safety (JAMPSS)'. (author)

  14. NASA safety program activities in support of the Space Exploration Initiatives Nuclear Propulsion program

    Sawyer, J. C., Jr.

    1993-01-01

    The activities of the joint NASA/DOE/DOD Nuclear Propulsion Program Technical Panels have been used as the basis for the current development of safety policies and requirements for the Space Exploration Initiatives (SEI) Nuclear Propulsion Technology development program. The Safety Division of the NASA Office of Safety and Mission Quality has initiated efforts to develop policies for the safe use of nuclear propulsion in space through involvement in the joint agency Nuclear Safety Policy Working Group (NSPWG), encouraged expansion of the initial policy development into proposed programmatic requirements, and suggested further expansion into the overall risk assessment and risk management process for the NASA Exploration Program. Similar efforts are underway within the Department of Energy to ensure the safe development and testing of nuclear propulsion systems on Earth. This paper describes the NASA safety policy related to requirements for the design of systems that may operate where Earth re-entry is a possibility. The expected plan of action is to support and oversee activities related to the technology development of nuclear propulsion in space, and support the overall safety and risk management program being developed for the NASA Exploration Program.

  15. Incident warning systems : accident review. DRIVE II Project V2002 Horizontal Project for the Evaluation of Safety HOPES, Deliverable 17, Workpackage 31, Activity 31.2.

    Oppe, S. Lindeijer, J.E. & Barjonet, P.

    1995-01-01

    The objective of this accident review is to check what proportion of accidents recorded in the past could in principle have been prevented by using an incident warning system (IWS). The accident review was carried out for all three IWS test sites that are part of the HOPES evaluation study. These in

  16. Safety Inspection System Based on the Internet of Things

    Dong-Tao Hu

    2013-01-01

    Full Text Available The Safety inspection system uses the Internet of things technology to identify the location of mobile terminal automatically and bring up the correspondent safety inspection table through the equipments of Hand-hold Terminal and specific location wireless router. Inspection information including the inspection results, photos or video can be transport to general platform for storing and processing through the wireless network immediately. The process of safety inspection and hidden trouble rectification have been formed a closed-loop management system which start from the draft and inquiry of the inspection table to the implementation of safety inspection, the feedback of results, the instruction about of rectify hidden trouble, the inspection and acceptance of results. At last, it also solves the problem of timely record the dynamic checking information; make the operability of safety inspection system greatly enhanced.

  17. Research on the Evaluation System for Rural Public Safety Planning

    Ming; SUN; Jianxin; YAN

    2014-01-01

    The indicator evaluation system is introduced to the study of rural public safety planning in this article.By researching the current rural public safety planning and environmental carrying capacity,we select some carrying capacity indicators influencing the rural public safety,such as land,population,ecological environment,water resources,infrastructure,economy and society,to establish the environmental carrying capacity indicator system.We standardize the indicators,use gray correlation analysis method to determine the weight of indicators,and make DEA evaluation of the indicator system,to obtain the evaluation results as the basis for decision making in rural safety planning,and provide scientific and quantified technical support for rural public safety planning.

  18. Safety Management Characteristics Reflected in Interviews at Swedish Nuclear Power Plants: A System Perspective Approach

    The present study investigated safety management characteristics reflected in interviews with participants from two Swedish nuclear power plants. A document analysis regarding the plants' organization, safety policies, and safety culture work was carried out as well. The participants (n=9) were all nuclear power professionals, and the majority managers at different levels with at least 10 years of nuclear power experience. The interview comprised themes relevant for organizational safety and safety management, such as: organizational structures and organizational change, threats to safety, information feedback and knowledge transfer, safety analysis, safety policy, and accident and incident analysis and reporting. The results were in part modeled to important themes derived from a general system theoretical framework suggested by Svenson and developed by Svenson and Salo in relation to studies of 'non-nuclear' safety organizations. A primer to important features of the system theoretical framework is presented in the introductory chapter. The results from the interviews generated interesting descriptions about nuclear safety management in relation to the above themes. Regarding organizational restructuring, mainly centralizations of resources, several examples of reasons for the restructuring and related benefits for this centralization of resources were identified. A number of important reminders that ought to be considered in relation to reorganization were also identified. Regarding threats to the own organization a number of such was interpreted from the interviews. Among them are risks related to generation and competence change-over and risks related to outsourcing of activities. A thorough picture of information management and practical implications related to this was revealed in the interviews. Related to information feedback is the issue of organizational safety indicators and safety indicators in general. The interview answers indicated that the area

  19. Integrating Safety and Mission Assurance into Systems Engineering Modeling Practices

    Beckman, Sean; Darpel, Scott

    2015-01-01

    During the early development of products, flight, or experimental hardware, emphasis is often given to the identification of technical requirements, utilizing such tools as use case and activity diagrams. Designers and project teams focus on understanding physical and performance demands and challenges. It is typically only later, during the evaluation of preliminary designs that a first pass, if performed, is made to determine the process, safety, and mission quality assurance requirements. Evaluation early in the life cycle, though, can yield requirements that force a fundamental change in design. This paper discusses an alternate paradigm for using the concepts of use case or activity diagrams to identify safety hazard and mission quality assurance risks and concerns using the same systems engineering modeling tools being used to identify technical requirements. It contains two examples of how this process might be used in the development of a space flight experiment, and the design of a Human Powered Pizza Delivery Vehicle, along with the potential benefits to decrease development time, and provide stronger budget estimates.

  20. Development and application of digital safety system in NPPs

    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

  1. Establishment of Safety Analysis System and Technology for CANDU Reactors

    To improve the CANDU design/operation safety analysis codes and the CANDU safety analysis methodology, the following works have been done. From the development of the lattice codes (WIMS/CANDU), the lattice model simulates the real core lattice geometry and the effect of the pressure tube creep to the core lattice parameter has been evaluated. From the development of the 3-dimensional thermal-hydraulic analysis model of the moderator behavior (CFX4-CAMO), validation of the model against STERN Lab experiment has been executed. The butterfly-shaped grid structure and the 3-dimensional flow resistance model for porous media were developed and applied to the moderator analysis for Wolsong units 2/3/4. The single fuel channel analysis codes for blowdown and post-blowdown were unified by CATHENA. The 3-dimensional fuel channel analysis model (CFX-CACH) has been developed for validation of CATHENA fuel channel analysis model. The interlinking analysis system (CANVAS) of the thermal-hydraulic safety analysis codes for the primary heat transport system and containment system has been executed. The database system of core physics and thermal-hydraulics experimental data for safety analysis has been established on the URL: http://CANTHIS.kaeri.re.kr. For documentation and Standardization of the general safety analysis procedure, the general safety analysis procedure is developed and applied to a large break LOCA. The present research results can be utilized for establishment of the independent safety analysis technology and acquisition of the optimal safety analysis technology

  2. Occupational Safety and Health Systems: A Three-Country Comparison.

    Singleton, W. T.

    1983-01-01

    This article compares the occupational safety and health systems of Switzerland, the United Kingdom, and the United States, looking at the origins of their legislation and its effects on occupational safety and health, with a view to determining what lessons may emerge, particularly for developing countries. (Author/SSH)

  3. SAFETY ASPECTS OF THE WATER TREATMENT SYSTEMS FOR MEDICAL UTILIZATION

    Endre Ianosi

    2012-01-01

    To make sustainable the human life, in normal or specific medical situations, it is necessary to have adequate water resources. In medical utilization's of the water (dialysis, perfusable or liquid medication) some special water treatment systems and methods are necessary. These water treatment systems must accomplish some safety requirements. The safety of the patients relied to water treatment systems in medical utilization and the risk's identification are important aspects in this type of...

  4. Modernisation of the safety systems of Kozloduy NPP

    In 2008 SPE 'Radium' won the international tender for the design, manufacture , supply and implementation of 6 safety control systems for reactors 5 and 6 of Kozloduy NPP. The modernization project is based on the use of software and hardware complexes for safety control systems, developed by specialists from 'Radiy'. This complex is a distributed control system , in which the functions of technological protection locks , automatic control , remote control , alarm are integrated into the hardware of the complex

  5. Risk Analysis of Safety-Critical Control Systems

    Karol Rastocny

    2008-01-01

    This paper deals with problems associated with risks analysis of a safety-critical control system. In the paper there are introduced recommendations enabling practical enforceability of risk analysis by the assurance of sufficient objectivity level. In the initial phases of the system lifecycle risk analysis serves for a tolerable hazard rate definition for individual safety relevant functions. In the end of the control system development process the risk analysis (an analysis of failures con...

  6. Regulatory system reform of occupational health and safety in China

    WU, Fenghong; Chi, Yan

    2015-01-01

    With the explosive economic growth and social development, China’s regulatory system of occupational health and safety now faces more and more challenges. This article reviews the history of regulatory system of occupational health and safety in China, as well as the current reform of this regulatory system in the country. Comprehensive, a range of laws, regulations and standards that promulgated by Chinese government, duties and responsibilities of the regulatory departments are described. P...

  7. Improved safety of the system 80+TM standard plants design through increased diversity and redundancy of safety systems

    Safely systems in the System 80+TM Standard Plant are designed with more redundancy, diversity and simplicity than earlier nuclear power plant designs. These gains were accomplished by an evolutionary process that preserved the desirable and proven features in currently operating nuclear plants, while improving reliability and defense-in-depth. The System 80+ safety systems are the primary contributors to a core damage frequency that is more than 100 times lower than 1980's vintage U. S. designs, including the predecessor System 80R standard nuclear steam supply system (NSSS) design. The System 80+ design includes significant improvements to the safety injection system, emergency feedwater system, shutdown cooling system, containment spray system, reactor coolant gas vent system, and to their vital support systems. These improvements enhance performance for traditional design basis events and significantly reduce the probability of a severe accident. The System 80+ design also incorporates safety systems to mitigate a severe accident. The added systems include the rapid depressurization system, the in-containment refueling water storage tank, the cavity flooding system. These systems fully address the U. S. Nuclear Regulatory Commission's (US NRC) severe accident policy. The System 80+ safety systems are integrated with the System 80+ Nuclear Island (NI) design. The NI general arrangement provides quadrant separation of the safety systems for protection from fire and flooding, and large equipment pull spaces and lay down areas for maintenance. This paper will describe the System 80+ safety systems advanced design features, the improved accident prevention and mitigation capabilities, and startup, operating and maintenance benefits

  8. BUCS: Patterns and Robustness: Experimentation with Safety Patterns in Safety-Critical Software Systems

    Ljosland, Ingvar

    2006-01-01

    In modern society, we rely on safely working software systems. This is the final report in a masters degree project to reveal key issues in the science field of computer software architecture and design of safety-critical software systems. A pre-study of a navigation system implied that functionality related problems and safety-critical problems do not stack one to one, but rather is a case of solving these aspects in different layers. This means that changes in software systems functionalit...

  9. Fuzzy synthetic assessment of building fire safety system

    YANG Gao-shang; PENG Li-min

    2005-01-01

    A multistage assessment index set is chosen based on the analysis of building fire safety system, whereby the weight of each index is determined through an analy tie.hierarchy process; a fuzzy synthetic assessment model for the building fire safety system is constructed, and the quantified result was obtained by using hierarchy parameter judgment. This fuzzy synthetic assessment method can quantify assessment result of the building fire safety system, so thatthe fire precautions may be accurately adopted, and the serious potential risk may be avoided. The application shows that this method possesses both objectivity and feasibility.

  10. Assessment of Primary Production of Horticultural Safety Management Systems of Mushroom Farms in South Africa.

    Dzingirayi, Garikayi; Korsten, Lise

    2016-07-01

    Growing global consumer concern over food safety in the fresh produce industry requires producers to implement necessary quality assurance systems. Varying effectiveness has been noted in how countries and food companies interpret and implement food safety standards. A diagnostic instrument (DI) for global fresh produce industries was developed to measure the compliancy of companies with implemented food safety standards. The DI is made up of indicators and descriptive grids for context factors and control and assurance activities to measure food safety output. The instrument can be used in primary production to assess food safety performance. This study applied the DI to measure food safety standard compliancy of mushroom farming in South Africa. Ten farms representing almost half of the industry farms and more than 80% of production were independently assessed for their horticultural safety management system (HSMS) compliance via in-depth interviews with each farm's quality assurance personnel. The data were processed using Microsoft Office Excel 2010 and are represented in frequency tables. The diagnosis revealed that the mushroom farming industry had an average food safety output. The farms were implementing an average-toadvanced HSMS and operating in a medium-risk context. Insufficient performance areas in HSMSs included inadequate hazard analysis and analysis of control points, low specificity of pesticide assessment, and inadequate control of suppliers and incoming materials. Recommendations to the industry and current shortcomings are suggested for realization of an improved industry-wide food safety assurance system. PMID:27357039

  11. Safety evaluation and management of complex systems: A system engineering approach

    Guillerm, Romaric; Demmou, Hamid; Sadou, Nabil

    2012-01-01

    International audience This paper addresses the problem of safety evaluation of complex systems. It proposes an original and rigorous approach that integrates safety analysis in system engineering processes. The approach is based on system engineering (SE) principles and uses the famous industrial SE standard ANSI/EIA-632. The objective is to help designers and safety engineers in safety management of complex systems. For an efficient design, the model driven design is adopted through the ...

  12. The ITER safety control systems-Status and plans

    The operation of a complex experimental machine like ITER will involve a number of potential hazards to personnel, the environment, and to the machine itself. While some protections are usually embedded within the overall control system, when it comes to the protection of people, the environment or the safe operation of the machine, dedicated systems are required. At ITER, the safety control systems are dedicated to the protection of people and the environment. These systems represents one of the three independent tiers on which the ITER Instrumentation and Control is based. They have to respect stringent requirements in terms of reliability, availability, safety and maintainability for operation, security and national and/or international safety regulations. This paper describes the current status and plans of the safety control systems, the functions to be performed, the envisaged architecture and the main design options including the principles of separation and independence between the three tiers.

  13. Safety classification of nuclear power plant systems, structures and components

    The Safety Classification principles used for the systems, structures and components of a nuclear power plant are detailed in the guide. For classification, the nuclear power plant is divided into structural and operational units called systems. Every structure and component under control is included into some system. The Safety Classes are 1, 2 and 3 and the Class EYT (non-nuclear). Instructions how to assign each system, structure and component to an appropriate safety class are given in the guide. The guide applies to new nuclear power plants and to the safety classification of systems, structures and components designed for the refitting of old nuclear power plants. The classification principles and procedures applying to the classification document are also given

  14. Reliability evaluation of communication network switching scheme for safety systems

    To develop the communication network architecture of a safety system of nuclear power plant, the five essence in the design requirements of a communication network for safety-critical systems are determined such as status based architecture, deterministic scheme, separation and isolation, high reliability, verification and validation. In this paper, the data communication network switching scheme for safety systems is proposed based on the circuit switched network with time division multiplexing bus technology considered adequate to the essence of the design requirements and the design elements. The proposed communication network switching scheme was applied to the network design of the SMART protection system, and the reliability was evaluated with the data of components failure rates to determine the applicability of the proposed switching scheme. The proposed switching scheme will be applied as basic communication network architecture of safety system

  15. The Danish patient safety experience: the Act on Patient Safety in the Danish Health care system

    Lundgaard, Mette; Rabøl, Louise; Jensen, Elisabeth Agnete Brøgger;

    2005-01-01

    This paper describes the process that lead to the passing of the Act for Patient Safety in the Danisk health care sytem, the contents of the act and how the act is used in the Danish health care system. The act obligates frontline health care personnel to report adverse events, hospital owners to...... act on the reports and the National Board of Health to commuicate the learning nationally. The act protects health care providers from sanctions as a result of reporting. In January 2004, the Act on Patient Safety in the Danish health care system was put into force. In the first twelve months 5740...... adverse events were reported. the reports were analyzed locally (hospital and region), anonymized ad then sent to the National Board af Health. The Act on Patient Safety has driven the work with patient safety forward but there is room for improvement. Continuous and improved feedback from all parts of...

  16. Development of active rear steer actuator. Development of four wheel steer actuator for active safety; Active rear steer actuator no kaihatsu. Yobo anzen ni muketa 4WS actuator no kaihatsu

    Yamanaka, T. [Aisin Seiki Co. Ltd., Aichi (Japan)

    1997-10-01

    Recently, ecology, energy saving and safety have become important issues. And Active Safety is spotlighted in vehicle control area. Many researches and developments on four wheel steer system have been done to improve vehicle stability. We have developed the Active Rear Steer system with electromechanical Actuator, which is mass-productive, compact, and high response and durable. 10 figs., 5 tabs.

  17. Human aspects for safety-critical systems

    This report addresses crew, i.e., human, aspects of the widespread introduction of digital technology into nuclear power plant control rooms. Such changes as increased levels of automation, intelligent electronic displays, and compact work stations influence crew situation awareness, workload, etc. The overall impact is expected to be enhanced safety, although such challenges as automation complacency and access to information in multi-dimensional space must be handled. In considering design certification for safety, it is desirable that guidelines be available. Since digital technology is developing more rapidly than accepted guidelines, regulatory emphasis is placed on the design process and verification and validation. The lack of adequate guidance creates a need to assess knowledge from other applications already experienced with digital technology (e.g., foreign nuclear and fossil plant upgrades, commercial aviation), and to perform application research on such topics as automation and information management

  18. Entrainment analysis and monitoring major safety systems

    The authors are convinced that taking account of internal and external experience and a plant-specific living PSA frequently reduces the notifiable incidents occurring as design errors due to inadequate checks on safety margins. On the basis of the considerations formulated in this article, Leibstadt nuclear power station has decided to overhaul the earlier PSA and work towards and implement a living PSA. The project has been given the green light and should be completed in two years. 5 figs., 4 refs

  19. Safety requirements for wiring systems and connectors for photovoltaic systems

    Lundtveit, T.

    1984-09-01

    Safety requirements for roof-mounted photovoltaic (PV) arrays were established by considering the environmental use-conditions applicable to PV arrays and the differences between integral-, direct-, standoff- and rack-mounted modules. Those articles in the National Electrical Code (NEC) covering wiring systems are discussed to: (1) define the wiring systems; (2) identify the permitted uses and use-restrictions; (3) outline the advantages and disadvantages; and (4) address the concerns regarding support, protection against mechanical damage, and wet versus dry locations. The advantages and disadvantages of each wiring system are assessed to arrive at candidate wiring systems that are best suited for use in PV arrays. For candidate wiring systems having prohibitive use-restrictions issues are considered that need to be addressed by any proposed revision to the National Electrical Code to permit acceptance by the inspection authorities. Various wiring termination methods permitted by the NEC are discussed and those which have features that are desirable for PV applications are identified. Performance and construction requirements for PV cable and for PV connectors are presented in separate outlines of proposed investigations of these products.

  20. The impact of blanket design on activation and thermal safety

    Activation and thermal safety analyses for experimental and power reactors are presented. The effects of a strong neutron absorber, B4C, on activation and temperature response of experimental reactors to Loss-of-Cooling Accidents are investigated. Operational neutron fluxes, radioactivities of elements and thermal transients are calculated using the codes ONEDANT, REAC and THIOD, respectively. The inclusion of a small amount of B4C in the steel blanket of an experimental reactor reduces its activation and the post LOCA temperature escalation significantly. Neither the inclusion of excessive amounts of B4C nor enriched 10B in the first walls of an experimental reactor bring much advantage. The employment of a 2 cm graphite tile liner before the first wall helps to limit the post LOCA escalation of first wall temperature. The effect of replacing a 20 cm thick section of a steel shield of a fusion power reactor with B4C is also analyzed. The first wall temperature peak is reduced by 100 degree C in the modified blanket. The natural convection effect on thermal safety of a liquid lithium cooled blanket are investigated. Natural convection has no impact at all, unless the magnetic field can be reduced. If magnets can be shut off rapidly after the accident, then the temperature escalation of the first wall will be limited. Upflow of the coolant is better than the initial downflow design from a thermal safety point of view. Activities of three structural materials, OTR stainless steel, SS-316 and VCrTi are compared. Although VCrTi has higher activity for a period of two hours after the accident, it has one to two orders of magnitude less activity than those of the steels in the mid- and long-terms. 29 refs., 42 figs., 9 tabs

  1. Concepts and techniques: Active electronics and computers in safety-critical accelerator operation

    Frankel, R.S.

    1995-12-31

    The Relativistic Heavy Ion Collider (RHIC) under construction at Brookhaven National Laboratory, requires an extensive Access Control System to protect personnel from Radiation, Oxygen Deficiency and Electrical hazards. In addition, the complicated nature of operation of the Collider as part of a complex of other Accelerators necessitates the use of active electronic measurement circuitry to ensure compliance with established Operational Safety Limits. Solutions were devised which permit the use of modern computer and interconnections technology for Safety-Critical applications, while preserving and enhancing, tried and proven protection methods. In addition a set of Guidelines, regarding required performance for Accelerator Safety Systems and a Handbook of design criteria and rules were developed to assist future system designers and to provide a framework for internal review and regulation.

  2. The technology for safety I and C systems in nuclear power plants: the SPINLINE 3 solution

    The SPINLINE 3 technology is the latest digital technology produced by Schneider to offer the most adequate solution to safety I and C systems, particularly for modernisation of VVER reactors. This technology developed in co-operation with FRAMATOME has the great advantage of more than 200 reactors x years of cumulated experience in the field of digital safety systems. The design criteria mainly devoted to achieve the most stringent safety requirement are also combined with the economic objectives in term of investment, maintenance and long term operation. The SPINLINE 3 technology is fully supported by the activity on the French Nuclear Program with 59 NPPs in operation. (author)

  3. 14 CFR 417.309 - Flight safety system analysis.

    2010-01-01

    ... 12-dB margin, each link analysis must account for the following nominal system performance and... 14 Aeronautics and Space 4 2010-01-01 2010-01-01 false Flight safety system analysis. 417.309... analysis. (a) General. (1) Each flight termination system and command control system, including each...

  4. Analysis of Aviation Safety Reporting System Incident Data Associated With the Technical Challenges of the Vehicle Systems Safety Technology Project

    Withrow, Colleen A.; Reveley, Mary S.

    2014-01-01

    This analysis was conducted to support the Vehicle Systems Safety Technology (VSST) Project of the Aviation Safety Program (AVsP) milestone VSST4.2.1.01, "Identification of VSST-Related Trends." In particular, this is a review of incident data from the NASA Aviation Safety Reporting System (ASRS). The following three VSST-related technical challenges (TCs) were the focus of the incidents searched in the ASRS database: (1) Vechicle health assurance, (2) Effective crew-system interactions and decisions in all conditions; and (3) Aircraft loss of control prevention, mitigation, and recovery.

  5. The Norwegian approach to safety in the offshore petroleum activity

    The Norwegian Petroleum Directorate (NPD) is the agency vested with the task of supervising offshore licensees' performance with regard to regulatory compliance. The strategy has developed towards system-oriented supervision, with emphasis on the decision-making processes within the responsible companies. The NPD safety regulations are expressed in terms of goal-setting requirements, thus focusing on the purpose of the requirement rather than specifying the technical solution. Risk analyses are important parts of the decision-making process. The NPD has issued regulations concerning risk analyses, which require the licensee to establish safety goals and acceptance criteria, to carry out a systematic identification of relevant risks, and to ensure that adequate measures are taken to minimize risks, as an integrated part of the decision-making system. (author)

  6. Safety system of nuclear power plants and its management example

    Safety system of nuclear power plants(NPP) and its management example in pressurized water reactor NPP, e.g. Qinshan NPP, the first NPP designed and constructed domestically in China are described. 5 figs

  7. Automated Flight Safety Inference Engine (AFSIE) System Project

    National Aeronautics and Space Administration — We propose to develop an innovative Autonomous Flight Safety Inference Engine (AFSIE) system to autonomously and reliably terminate the flight of an errant launch...

  8. Performance indicators for monitoring safety management systems in chemical industry

    M. Jovašević-Stojanović

    2009-01-01

    Full Text Available The development of the Safety Management System (SMS in chemical industry appears as one of the important requirements introduced by the EU "Seveso II" Directive on the control of major-accident hazards. This paper aims to provide a contribution regarding the SMS structure and the definition of the tools for assessing the effectiveness of this system by means of safety performance indicators. The performance indicators are linked to a reference values or policy targets, illustrating how far the SMS is from the desired level. We developed a system of performance indicators for SMS in chemical industry by using the concept of environmental performance indicators defined in standard ISO 14031. A set of three types of safety system performance indicators was proposed: management performance indicators, operational performance indicators and safety status indicators. These indicators represent the most important factors in the linkage between a possible cause of an accident and its effects.

  9. Analyzing Software Errors in Safety-Critical Embedded Systems

    Lutz, Robyn R.

    1994-01-01

    This paper analyzes the root causes of safty-related software faults identified as potentially hazardous to the system are distributed somewhat differently over the set of possible error causes than non-safety-related software faults.

  10. Kozloduy nuclear power plant. Units 1-4. Status of safety assessment activities. Rev. 2

    This paper presents the results of the status of safety assessment activities carried out by the Kozloduy Nuclear Power Plant (KNPP) in order to evaluate the current status of the safety of its reactor units 1-4. The steam supply system of this units is based of the reactor WWER-440/ B-230, which is a PWR of Russian design developed according to the safety standards in force in USSR in late 60-s. Now a days 10 reactor units of this type are in operation in four NPPs. Despite of efforts of the different plants to implement safety improvements measures during first 10-15 years of operation of this type of reactor its major safety problems were not eliminated and were a subject of international concern. The systematic evaluation of the deficiencies of the original design of this type of reactors have been initiated by IAEA in the beginning of 1990 and brought to developing a comprehensive list of safety problems which required urgent implementation of safety measures in all plants. To solve this problems in 1991 KNPP initiated implementation of so called 'short term' safety improvement program, developed with the help of WANO under agreement with Bulgarian Nuclear Safety Authority (BNSA) and consortium RISKAUDIT. The program was based on a stage approach and was foreseen to be implemented by tree stages in very tight time schedule in order to achieve significant and rapid improvements of the level of safety in operation of the units. The Short Tenn Program was implemented between the years 1991 and 1997 thanks of the strong safety commitment of NEK and KNPP staff and the broad international cooperation and financial support. Important part of resources were supplied under PHARE program of CEC, EBRD grant agreement and EDF support. The plant current safety level analysis has been performed using IAEA analytical methodology according to 50-SG-O12 standard 'Periodic safety review of operational nuclear power plants'. The approach and criteria for acceptable safety level

  11. ITER safety

    As part of the series of publications by the IAEA that summarize the results of the Conceptual Design Activities for the ITER project, this document describes the ITER safety analyses. It contains an assessment of normal operation effluents, accident scenarios, plasma chamber safety, tritium system safety, magnet system safety, external loss of coolant and coolant flow problems, and a waste management assessment, while it describes the implementation of the safety approach for ITER. The document ends with a list of major conclusions, a set of topical remarks on technical safety issues, and recommendations for the Engineering Design Activities, safety considerations for siting ITER, and recommendations with regard to the safety issues for the R and D for ITER. Refs, figs and tabs

  12. What is Clinical Safety in Electronic Health Care Record Systems?

    Davies, George

    There is mounting public awareness of an increasing number of adverse clinical incidents within the National Health Service (NHS), but at the same time, large health care projects like the National Programme for IT (NPFIT) are claiming that safer care is one of the benefits of the project and that health software systems in particular have the potential to reduce the likelihood of accidental or unintentional harm to patients. This paper outlines the approach to clinical safety management taken by CSC, a major supplier to NPFIT; discusses acceptable levels of risk and clinical safety as an end-to-end concept; and touches on the future for clinical safety in health systems software.

  13. Computational methods for criticality safety analysis within the scale system

    The criticality safety analysis capabilities within the SCALE system are centered around the Monte Carlo codes KENO IV and KENO V.a, which are both included in SCALE as functional modules. The XSDRNPM-S module is also an important tool within SCALE for obtaining multiplication factors for one-dimensional system models. This paper reviews the features and modeling capabilities of these codes along with their implementation within the Criticality Safety Analysis Sequences (CSAS) of SCALE. The CSAS modules provide automated cross-section processing and user-friendly input that allow criticality safety analyses to be done in an efficient and accurate manner. 14 refs., 2 figs., 3 tabs

  14. The strengthening of the nuclear safety regulatory system in restructuring of electric power industry sector

    Nuclear safety concern, which may accompany such external environmental factors as privatization and restructuring of the electric power industry, is emerging as an international issue. In order to cope with the concern about nuclear safety, it is important to feedback valuable experiences of advanced countries which ever restructured their electric power industries earlier and further to reflect the current safety issues, which are raised internationally, fully into the nuclear safety regulatory system. This paper is to review the safety issues that might take place in the process of increasing competition in the nuclear power industry, and further to present a basic direction and effective measures for ensuring nuclear safety in response thereto from the viewpoint of safety regulation. It includes a political direction for regulatory body's efforts to rationalize and enforce efficiently its regulation. It proposes to ensure that regulatory specialty and regulatory cost are stably secured. Also, this paper proposes for maintaining a sound nuclear safety regulatory system to monitor thoroughly the safety management activities of the industry, which might be neglected as a result of focusing on reduction of the cost for producing electric power

  15. Deliberations on nuclear safety regulatory system in a changing industrial environment

    Nuclear safety concern, which may accompany such external environmental factors as privatization and restructuring of the electric power industry, is emerging as an international issue. In order to cope with the concern about nuclear safety, it is important to feedback valuable experiences of advanced countries that restructured their electric power industries earlier and further to reflect the current safety issues, which are raised internationally, fully into the nuclear safety regulatory system. This paper is to review the safety issues that might take place in the process of increasing competition in the nuclear power industry, and further to present a basic direction and effective measures for ensuring nuclear safety in response thereto from the viewpoint of safety regulation. It includes a political direction for a regulatory body's efforts to rationalize and enforce efficiently its regulation. It proposes to ensure that regulatory specialty and regulatory cost are stably secured. Also, this paper proposes maintaining a sound nuclear safety regulatory system to monitor thoroughly the safety management activities of the industry, which might be neglected as a result of focusing on reduction of the cost for producing electric power. (author)

  16. The Effect of Safety System on Production Indices

    Manouchehr Omidvari; Naser Javaheri; Masoud Davudi

    2012-01-01

    Nowadays, in addition to implement the quality of management systems and environment management and due to the effects of safety and health issues on working processes, the organizations have also sought to acquire health and safety management systems. This descriptive –analytic and past reviewing study has been implemented based on five years (from 2006 to 2010) recorded documents and statistics information in food industrial. Information was collected based on the food industries checklists...

  17. Remarks on statistical aspects of safety analysis of complex systems

    Pal, L.; Makai, M.

    2003-01-01

    We analyze safety problems of complex systems using the methods of mathematical statistics for testing the output variables of a code simulating the operation of the system under consideration when the input variables are uncertain. We have defined a black box model of the code and derived formulas to calculate the number of runs needed for a given confidence level to achieve a preassigned measure of safety. In order to show the capabilities of different statistical methods, firstly we have i...

  18. Design patterns for safety-critical embedded systems

    Armoush, Ashraf

    2010-01-01

    Over the last few years, embedded systems have been increasingly used in safety-critical applications where failure can have serious consequences. The design of these systems is a complex process, which is requiring the integration of common design methods both in hardware and software to fulfill functional and non-functional requirements for these safety-critical applications. Design patterns, which give abstract solutions to commonly recurring design problems, have been widely used in the s...

  19. 33 CFR 96.220 - What makes up a safety management system?

    2010-07-01

    ... Company and Vessel Safety Management Systems § 96.220 What makes up a safety management system? (a) The safety management system must document the responsible person's— (1) Safety and pollution prevention...) Reporting responsibilities. (b) A safety management system must also be consistent with the...

  20. Radiation safety management system in a radioactive facility

    Full text: This paper illustrates the Cuban experience in implementing and promoting an effective radiation safety system for the Centre of Isotopes, the biggest radioactive facility of our country. Current management practice demands that an organization inculcate culture of safety in preventing radiation hazard. The aforementioned objectives of radiation protection can only be met when it is implemented and evaluated continuously. Commitment from the workforce to treat safety as a priority and the ability to turn a requirement into a practical language is also important to implement radiation safety policy efficiently. Maintaining and improving safety culture is a continuous process. There is a need to establish a program to measure, review and audit health and safety performance against predetermined standards. All those areas of the radiation protection program are considered (e.g. licensing and training of the staff, occupational exposure, authorization of the practices, control of the radioactive material, radiological occurrences, monitoring equipment, radioactive waste management, public exposure due to airborne effluents, audits and safety costs). A set of indicators designed to monitor key aspects of operational safety performance are used. Their trends over a period of time are analyzed with the modern information technologies, because this can provide an early warning to plant management for searching causes behind the observed changes. In addition to analyze the changes and trends, these indicators are compared against identified targets and goals to evaluate performance strengths and weaknesses. A structured and proper radiation self-auditing system is seen as a basic requirement to meet the current and future needs in sustainability of radiation safety. The integrated safety management system establishment has been identified as a goal and way for the continuous improvement. (author)

  1. Simplified safety and containment systems for the iris reactor

    The IRIS (International Reactor Innovative and Secure) is a 100 - 300 MW modular type pressurized water reactor supported by the U.S. DOE NERI Program. IRIS features a long-life core to provide proliferation resistance and to reduce the volume of spent fuel, as well as reduce maintenance requirements. IRIS utilizes an integral reactor vessel that contains all major primary system components. This integral reactor vessel makes it possible to reduce containment size; making the IRIS more cost competitive. IRIS is being designed to enhance reactor safety, and therefore a key aspect of the IRIS program is the development of the safety and containment systems. These systems are being designed to maximize containment integrity, prevent core uncover following postulated accidents, minimize the probability and consequences of severe accidents, and provide a significant simplification over current safety system designs. The design of the IRIS containment and safety systems has been identified and preliminary analyses have been completed. The IRIS safety concept employs some unique features that minimize the consequences of postulated design basis events. This paper will provide a description of the containment design and safety systems, and will summarize the analysis results. (author)

  2. Development of safety analysis methodology for fusion systems. 1

    One of the most important safety characteristics of a fusion energy system is the fact that energy and RI (radioisotope) sources as a hazard potential are distributed over and some of them move around the system. Abnormal release of these energy sources result in abnormal state of the system and may induce another energy release, an increase of vulnerable RI (source term) or a formation of flow path from system to environment (RI leak path). Moreover, these relationship is complex and extended over the system. Then, in this study, I will arrange these relationship in order and develop safety analytical model to be able to analyze system behavior quantitatively under abnormal conditions. In this report, I constructed a system model as the first stage of development of a comprehensive analytical model. The system model is composed of conceptual system elements such as control functions, spaces and boundaries. This model describes the characteristics of general fusion systems in an overall sense. Then, I arranged in order the system model mass and/or energy transport or storage processes between system elements on normal and/or abnormal conditions and defined the inter-relationship precisely. Based on the system model, a mathematical model is being developed. This mathematical model enables us to analyze system behavior quantitatively and to survey parameters controlled by safety features. The mathematical model will be the basis to develop a computer program which will be a good tool for selection of dominant event sequences and request for rational safety features. (author)

  3. Radiation Safety System for SPIDER Neutral Beam Accelerator

    Sandri, S.; Coniglio, A.; D'Arienzo, M.; Poggi, C.

    2011-12-01

    SPIDER (Source for Production of Ion of Deuterium Extracted from RF Plasma only) and MITICA (Megavolt ITER Injector Concept Advanced) are the ITER neutral beam injector (NBI) testing facilities of the PRIMA (Padova Research Injector Megavolt Accelerated) Center. Both injectors accelerate negative deuterium ions with a maximum energy of 1 MeV for MITICA and 100 keV for SPIDER with a maximum beam current of 40 A for both experiments. The SPIDER facility is classified in Italy as a particle accelerator. At present, the design of the radiation safety system for the facility has been completed and the relevant reports have been presented to the Italian regulatory authorities. Before SPIDER can operate, approval must be obtained from the Italian Regulatory Authority Board (IRAB) following a detailed licensing process. In the present work, the main project information and criteria for the SPIDER injector source are reported together with the analysis of hypothetical accidental situations and safety issues considerations. Neutron and photon nuclear analysis is presented, along with special shielding solutions designed to meet Italian regulatory dose limits. The contribution of activated corrosion products (ACP) to external exposure of workers has also been assessed. Nuclear analysis indicates that the photon contribution to worker external exposure is negligible, and the neutron dose can be considered by far the main radiation protection issue. Our results confirm that the injector has no important radiological impact on the population living around the facility.

  4. Radiation Safety System for SPIDER Neutral Beam Accelerator

    Sandri, S.; Poggi, C. [ENEA, Radiation Protection Institute, IRP-FUAC, Frascati (Italy); Coniglio, A. [Medical Physics Department, S. Giovanni Calibita Hospital, Fatebenefratelli, Isola Tiberina, Roma (Italy); D' Arienzo, M. [ENEA, Ionizing Radiation Metrology National Institute, METR, Casaccia, Rome (Italy)

    2011-12-13

    SPIDER (Source for Production of Ion of Deuterium Extracted from RF Plasma only) and MITICA (Megavolt ITER Injector Concept Advanced) are the ITER neutral beam injector (NBI) testing facilities of the PRIMA (Padova Research Injector Megavolt Accelerated) Center. Both injectors accelerate negative deuterium ions with a maximum energy of 1 MeV for MITICA and 100 keV for SPIDER with a maximum beam current of 40 A for both experiments. The SPIDER facility is classified in Italy as a particle accelerator. At present, the design of the radiation safety system for the facility has been completed and the relevant reports have been presented to the Italian regulatory authorities. Before SPIDER can operate, approval must be obtained from the Italian Regulatory Authority Board (IRAB) following a detailed licensing process. In the present work, the main project information and criteria for the SPIDER injector source are reported together with the analysis of hypothetical accidental situations and safety issues considerations. Neutron and photon nuclear analysis is presented, along with special shielding solutions designed to meet Italian regulatory dose limits. The contribution of activated corrosion products (ACP) to external exposure of workers has also been assessed. Nuclear analysis indicates that the photon contribution to worker external exposure is negligible, and the neutron dose can be considered by far the main radiation protection issue. Our results confirm that the injector has no important radiological impact on the population living around the facility.

  5. Behaviour analysis of AC-600 passive safety systems

    Southwest Center of Reactor Engineering Research and Design has finished the first step conceptual design of 600 mwe advanced PWR (AC-600). The main research emphases of AC-600 conceptual design include the advanced reactor core, the passive safety systems and the simplification. The passive safety systems of AC-600 consist of two reactor make up water tanks, two accumulators, two emergency feedwater tanks, two emergency natural draft air condensers, a containment water jacket and an enhanced primary cycle natural circulation flow system. 25% of the rated reactor power can be removed by the natural circulation cooling. The full pressure reactor make up water tanks are able to provide enough borated water which would be injected into the reactor coolant system during small LOCA. The coolant natural circulations can be established in the primary system and the passive secondary emergency feedwater system, removing residual heat from the reactor core to the atmosphere when station blackout occurs. It is indicated from analysis that the containment diameter of AC-600 is about 35 m. The large tanks and the large vertical distances between the tanks and reactor core are the main reason of using the big containment. It is also indicated from analysis that the low head safety injection pumps are required in AC-600 design to assure the recirculation system operation when large LOCA occurs. The reliability of AC-600 engineered safety systems is increased because the function of the passive safety systems is conducted through the immutable natural laws. The paper discusses the natural circulation ability and safety behavior of the passive safety systems during LOCA or station blackout for AC-600. The passive limits to excess reactivity and thermal hydraulic transients are also preliminarily discussed. Figs and tabs

  6. Optimization of maintenance periodicity of complex of NPP safety systems

    The analysis of the positive and negative aspects connected to maintenance of the safety systems equipment which basically is in a standby state is executed. Tests of systems provide elimination of the latent failures and raise their reliability. Poor quality of carrying out the tests can be a source of the subsequent failures. Therefore excess frequency of tests can result in reducing reliability of safety systems. The method of optimization of maintenance periodicity of the equipment taking into account factors of its reliability and restoration procedures quality is submitted. The unavailability factor is used as a criterion of optimization of maintenance periodicity. It is offered to use parameters of reliability of the equipment and each of safety systems of NPPs received at developing PSA. And it is offered to carry out the concordance of maintenance periodicity of systems within the NPP maintenance program taking into account a significance factor of the system received on the basis of the contribution of system in CDF. Basing on the submitted method the small computer code is developed. This code allows to calculate reliability factors of a separate safety system and to determine optimum maintenance periodicity of its equipment. Optimization of maintenance periodicity of a complex of safety systems is stipulated also. As an example results of optimization of maintenance periodicity at Zaporizhzhya NPP are presented. (author)

  7. IAEA activities in preparation of reglamentary documents on nuclear power plant safety

    The activities of the IAEA in the field of working out practical rules and recommendations ensuring the nuclear power plant safety are discussed. The practical rules will establish the aims and the minimum of requirements, that must be carried out to ensure the necessary safety of systems, components and equipment of the nuclear power plant throughout the whole period of its exploitation. Described is the procedure of the document preparation, consisting of the collection of documents, edited in different countries, the integration of documents by the IAEA Secretariat, the consideratiom of documents by the Group of senior advisers, the preparation of the draft document, the additional wort at the document in accordaqce with the remarks of the IAEA member-countries, the edition and dissemination of documents. The necessity for the active participation of the CMEA member-countries in the development and discussion of documents concerning the nuclear power plant safety is stated

  8. A review of tsunami simulation activities for NPPs safety

    The tsunami generated on December 26, 2004 due to Sumatra earthquake of magnitude 9.3 resulted in inundation at the various coastal sites of India. The site selection and design of Indian nuclear power plants demand the evaluation of run up and the structural barriers for the coastal plants: Besides it is also desirable to evaluate the early warning system for tsunamigenic earthquakes. The tsunamis originate from submarine faults, underwater volcanic activities, sub-aerial landslides impinging on the sea and submarine landslides. In case of a submarine earthquake-induced tsunami the wave is generated in the fluid domain due to displacement of the seabed. There are three phases of tsunami: generation, propagation, and run-up. Reactor Safety Division (RSD) of Bhabha Atomic Research Centre (BARC), Trombay has initiated computational simulation for all the three phases of tsunami source generation, its propagation and finally run up evaluation for the protection of public life, property and various industrial infrastructures located on the coastal regions of India. These studies could be effectively utilized for design and implementation of early warning system for coastal region of the country apart from catering to the needs of Indian nuclear installations. This paper presents some results of tsunami waves based on finite difference numerical approaches with shallow water wave theory. The present paper evaluate the results of various simulation i.e. Single fault Sumatra model, four and five fault Sumatra Model, Nias insignificant tsunami and also some parametric studies results for tsunami waring system scenario generation. A study is carried for the tsunami due to Sumatra earthquake in 2004 with TUNAMI-N2 software. Bathymetry data available from the National Geophysical Data Center was used for this study. The single fault and detailed four and five fault data were used to calculate sea surface deformations which were subsequently used as initial conditions for

  9. Safety design integrated in the building delivery system

    Jørgensen, Kirsten

    2013-01-01

    In construction, it is important to view safety and health as an integrated part of the way that “designers” are working. The designers cowers architects, constructors, engineers and others who carry out their consulting services in the design phase of a construction project. The philosophy....... The purpose of this article is to demonstrate how safety and health can be integrated in the design phases integrated in the management delivery systems within construction, The method for the research was to go through the building delivery system step by step and create a normative description of what, when...... and how to fully integrate safety in each part of the process. The result is a concept and guideline including control forms for how to integrate safety design in the Building Delivery System plus what to do and when. The concept has been tested in an educational context. The practical value...

  10. Comparative advantages of AP1000 passive safety system

    With the increasing need of nuclear power, almost all countries who want to build new nuclear power plant take the generation Ⅲ technology as their first choice. The main reason is that the safety of generation Ⅲ technology has been improved greatly than generation Ⅱ and Ⅱ + technology. The passive safety technology is introduced by AP1000 and it is one of the best in generation Ⅲ technologies. The representative passive containment cooling system of AP1000 and containment spray system of generation Ⅱ nuclear power plant were compared in the paper and analyzed using probabilistic safety assessment method. The reasons of passive safety system possessing comparative advantages were obtained by the concrete calculation. (authors)

  11. A concept of safety indicator system for nuclear power plants

    The fundamental principle in the safety technology of nuclear power is embodied in the strategy of defence in depth. The defence lines of the strategy, completed with a PSA logic model and structure, are considered to provide an appropriate framework for identification and structuring of the operational safety performance areas for nuclear power plants. Once these areas are identified the safety indicators can be defined. Based on this approach a concept of safety indicator system was outlined. About one hundred indicator specifications have been collected, refined and related to the performance areas. The specifications enable the utilities and authorities to check the coverage of their indicators set from the operational safety point of view and select or refine indicators for testing and routine use. Finally various statistical approaches and methods for using indicators in performance evaluation are presented. (orig.) (16 refs., 2 figs., 2 tabs.)

  12. Safety system function trend indicator: Theory and test application

    Methods for formulation, interpretation, and validation of dynamic risk and reliability indicators are studied. The use of these indicators for monitoring various levels of safety performance in nuclear power plants, as identified by probabilistic risk assessments (PRAs), such as safety system unavailability, safety system failure frequency, and core-damage frequency, are explored. Simplified indicators for detecting trends in the unavailability of safety systems in nuclear power plants not requiring PRA models and extensive data collection effort are being developed for possible NRC use. These indicators, called safety system function trend indicators (SSFT), are designed because they are easy to implement to display trends in system unavailability which can be detected through their visual inspections. The characteristics of these indicators are studied and optimized through simulation studies to assure sufficient capability in displaying a trend. To further substantiate the findings from visual examination of these indicators, statistical trend tests for sparse data are developed to aid the interpretation of these indicators. To evaluate the indicators from a safety point of view (rather than pure statistical sense) methods for comparing these indicators to a given alert level are being explored. Finally, approaches for engineering interpretation of these indicators are being studied by identifying the major contributors and causes for anomalies in indicator behavior. A preliminary pilot application/validation of these indicators, based on data from a sample of eight units, was completed in FY89. The findings are promising and warrant further refinement in the methodology. 5 refs., 3 figs

  13. Control of gamma irradiation facility with improved safety system

    Modern industrial control systems are based on computer technology and robotics with real-time information processing, multiuser databases, and communication networks. Due to the latest advances in information technology, some irradiator operations are already gaining significant benefits. However, in the case of safety critical systems such as irradiation plant, the requirements concerning the high degree of safety and reliability are priority, apart from these for better process control and cost savings. This paper presents the architecture and design of a new highly flexible control system with an improved safety system. The proposed control system has been designed, installed as an upgrade to an existing irradiation facility and successfully validated. The system controls the entire irradiation process from loading of products to the production of post-treatment reports. In addition to completely automated control, remote monitoring of the facility operation, including video surveillance, is provided via the Internet and GSM network. (author)

  14. Modular reliability modeling of the TJNAF personnel safety system

    A reliability model for the Thomas Jefferson National Accelerator Facility (formerly CEBAF) personnel safety system has been developed. The model, which was implemented using an Excel spreadsheet, allows simulation of all or parts of the system. Modularity os the model's implementation allows rapid open-quotes what if open-quotes case studies to simulate change in safety system parameters such as redundancy, diversity, and failure rates. Particular emphasis is given to the prediction of failure modes which would result in the failure of both of the redundant safety interlock systems. In addition to the calculation of the predicted reliability of the safety system, the model also calculates availability of the same system. Such calculations allow the user to make tradeoff studies between reliability and availability, and to target resources to improving those parts of the system which would most benefit from redesign or upgrade. The model includes calculated, manufacturer's data, and Jefferson Lab field data. This paper describes the model, methods used, and comparison of calculated to actual data for the Jefferson Lab personnel safety system. Examples are given to illustrate the model's utility and ease of use

  15. Nuclear activities at KIT: reactor safety research and safety research for waste

    The Karlsruhe Institute of Technology (KIT) is the merger of the former Forschungszentrum Karlsruhe (FZK), and the Technical University of Karlsruhe, into one single organisation, inheriting the previously existing missions of research, higher education and innovation, and creating a huge potential for synergies, that is now being successfully exploited step by step. One of the major strategic focuses of KIT is energy research, integrating more than 1 250 researchers from both KIT predecessors in the KIT Energy Centre.Within the KIT Energy Centre, the topic NUKLEAR is one of currently seven topics, together covering the integral field of energy including system and society aspects. Currently, the KIT Programme Nuclear Waste Disposal and Safety consists of about 250 research, technical, and management staff. After the reactor accident in Fukushima (Japan) in 2011, the German parliament decided with support of a broad societal consensus to terminate nuclear electricity production with the last nuclear power plant to be shutdown in 2022. Regarding the final disposal of radioactive waste, the Konrad repository is approved and will be available for the disposal of low and intermediate level waste at the end of this decade. A new federal law is expected to be issued in the near future to re-define the site selection procedure for the German high level waste repository. It seems clear that various host rock formations will be investigated. The long-term safety of such a repository is one of the most challenging aspects about nuclear energy in public debates. For these reasons, nuclear expertise in Germany must be maintained, focusing in particular on research into reactor safety and final disposal. Highest safety requirements have to be applied to the operation, shutdown and decommissioning of nuclear power plants and to the final disposal of radioactive waste

  16. KAERI software verification and validation guideline for developing safety-critical software in digital I and C system of NPP

    This technical report is to present V and V guideline development methodology for safety-critical software in NPP safety system. Therefore it is to present V and V guideline of planning phase for the NPP safety system in addition to critical safety items, for example, independence philosophy, software safety analysis concept, commercial off the shelf (COTS) software evaluation criteria, inter-relationships between other safety assurance organizations, including the concepts of existing industrial standard, IEEE Std-1012, IEEE Std-1059. This technical report includes scope of V and V guideline, guideline framework as part of acceptance criteria, V and V activities and task entrance as part of V and V activity and exit criteria, review and audit, testing and QA records of V and V material and configuration management, software verification and validation plan production etc., and safety-critical software V and V methodology. (author). 11 refs

  17. Bayesian Statistics and Uncertainty Quantification for Safety Boundary Analysis in Complex Systems

    He, Yuning; Davies, Misty Dawn

    2014-01-01

    The analysis of a safety-critical system often requires detailed knowledge of safe regions and their highdimensional non-linear boundaries. We present a statistical approach to iteratively detect and characterize the boundaries, which are provided as parameterized shape candidates. Using methods from uncertainty quantification and active learning, we incrementally construct a statistical model from only few simulation runs and obtain statistically sound estimates of the shape parameters for safety boundaries.

  18. Challenges in Performance of Food Safety Management Systems: A Case of Fish Processing Companies in Tanzania

    Kussaga, J.B.; Luning, P.A.; Tiisekwa, B.P.M.; Jacxsens, L.

    2014-01-01

    This study provides insight for food safety (FS) performance in light of the current performance of core FS management system (FSMS) activities and context riskiness of these systems to identify the opportunities for improvement of the FSMS. A FSMS diagnostic instrument was applied to assess the per

  19. 76 FR 5296 - Safety Management System for Part 121 Certificate Holders; Extension of Comment Period

    2011-01-31

    ... Federal Aviation Administration 14 CFR Parts 5 and 119 RIN 2120-AJ86 Safety Management System for Part 121... management system (SMS) to improve its aviation related activities. Several trade and membership... Register published on April 11, 2000 (65 FR 19477-19478), as well as at http://DocketsInfo.dot.gov ....

  20. Radiation and electrical safety systems for PEP

    At SLAC, the Personnel Protection System (PPS) protects people from radiation hazards. For PEP, the system has been expanded to include protection against electrical and RF hazards. This paper describes the overall system design, giving particular attention to the novel features not found in similar systems in other areas of SLAC. These include the Restricted Access Mode to allow limited occupancy in the ring while high voltage or RF may be present, the automatic badge reader system for improving the efficiency of entry logging and control, and the solid state lighting control system for switching large lighting loads with minimum electro-magetic interference

  1. Review of safety system performance and its safety implications at Bruce A nuclear generating station

    The reactor shutdown system performance with respect to meeting all nuclear safety and regulatory requirements is discussed for the Bruce A nuclear generating station. The operating experience at Bruce A spans over 17 years starting from September 1977. The two shutdown systems have performed well over the years in spite of constantly more stringent safety requirements for the safe operating envelope and new regulatory requirements. The system surveillance programme has been effective in identifying problems. As a result, several changes to system design, operating procedures and testing and maintenance have been made to improve the system performance. A life-cycle management programme is in place, in which ageing-related problems are closely monitored. Testing programmes are being reassessed and system upgrade for environmental qualification is in progress. Lessons learned over the years and corrective actions taken are discussed. (author). 4 figs, 1 tab

  2. Current Activities on Nuclear Safety Culture in Korea. How to meet the challenges for Safety and Safety Culture?

    'Statement of Nuclear Safety Policy' declared by the Korean Government elucidates adherence to the principle of 'priority to safety'. The 3. Comprehensive Nuclear Energy Promotion Plan (2007-2011) more specifically addressed the necessity to develop and apply 'safety culture evaluation criteria' and to strengthen safety management of concerned organizations in an autonomous way. Putting these policies as a backdrop, Korean Government has taken diverse safety culture initiatives and has encouraged the relevant organizations to develop safety culture practices of their own accord. Accordingly, KHNP, the operating organization in Korea, developed a 'safety culture performance indicator', which has been used to evaluate safety mind of employees and the evaluation results have been continuously reflected in operational management and training programs. Furthermore, KHNP inserted 'nuclear safety culture subject' into every course of more than two week length, and provided employees with special lectures on safety culture. KINS, the regulatory organization, developed indicators for the safety culture evaluation based on the IAEA Guidelines. Also, KINS has hosted an annual Nuclear Safety Technology Information Meeting to share information between regulatory organizations and industries. Furthermore, KINS provided a nuclear safety culture class to the new employees and they are given a chance to participate in performance of a role-reversal socio-drama. Additionally, KINS developed a safety culture training program, published training materials and conducted a 'Nuclear Safety Culture Basic Course' in October 2007, 4 times of which are planed this year. In conclusion, from Government to relevant organizations, 'nuclear safety culture' concept is embraced as important and has been put into practice on a variety of forms. Specifically, 'education and training' is a starting line and sharing information and lessons learned through symposium, meeting, and etc are also done in a

  3. A framework for software reuse in safety-critical system of systems

    Warren, Bradley R.

    2008-01-01

    This thesis concerns the effective and safe software reuse in safety-critical system-of-systems. Software reuse offers many unutilized benefits such as achieving rapid system development, saving resources and time, and keeping up technologically in an increasingly advancing global environment. System software needs to be designed for both reuse and safety and available information shared effectively. We introduce a process neutral framework for software reuse in safety-critical system of ...

  4. Safety upgrading activities against tsunami, earthquake, and severe accident at Hamaoka NPPs

    As the lessons learned by the Fukushima Daiichi NPPs accident, Chubu Electric Power carried out the Emergency Safety Measures at Hamaoka NPPs immediately, and announced the plan for tsunami countermeasures including the construction of 18m-height tsunami protection wall in July 2011. Furthermore, the company announced the additional severe accident and tsunami countermeasures, and etc. in December 2012 and in April 2013, such as the installation of Filtered Containment Venting System and increasing the height of the tsunami protection wall from 18m to 22m. In this paper, we present major safety upgrading activities against tsunami, earthquake and severe accident at Hamaoka NPPs. (author)

  5. System of Volcanic activity

    P. HÉDERVARI

    1972-06-01

    Full Text Available A comparison is made among the systems of B. G.
    Escher (3, of R. W. van Bemmelen (1 and that of the author (4. In this
    connection, on the basis of Esclier's classification, the terms of "constructiv
    e " and "destructive" eruptions are introduced into the author's system and
    at the same time Escher's concept on the possible relation between the depth
    of magma-chamber and the measure of the gas-pressure is discussed briefly.
    Three complementary remarks to the first paper (4 011 the subject of system
    of volcanic activity are added.

  6. Safety assessment of a robotic system handling nuclear material

    This paper outlines the use of a Failure Modes and Effects Analysis for the safety assessment of a robotic system being developed at Sandia National Laboratories. The robotic system, The Weigh and Leak Check System, is to replace a manual process at the Department of Energy facility at Pantex by which nuclear material is inspected for weight and leakage. Failure Modes and Effects Analyses were completed for the robotics process to ensure that safety goals for the system had been meet. These analyses showed that the risks to people and the internal and external environment were acceptable

  7. Analyzing system safety in lithium-ion grid energy storage

    Rosewater, David; Williams, Adam

    2015-12-01

    As grid energy storage systems become more complex, it grows more difficult to design them for safe operation. This paper first reviews the properties of lithium-ion batteries that can produce hazards in grid scale systems. Then the conventional safety engineering technique Probabilistic Risk Assessment (PRA) is reviewed to identify its limitations in complex systems. To address this gap, new research is presented on the application of Systems-Theoretic Process Analysis (STPA) to a lithium-ion battery based grid energy storage system. STPA is anticipated to fill the gaps recognized in PRA for designing complex systems and hence be more effective or less costly to use during safety engineering. It was observed that STPA is able to capture causal scenarios for accidents not identified using PRA. Additionally, STPA enabled a more rational assessment of uncertainty (all that is not known) thereby promoting a healthy skepticism of design assumptions. We conclude that STPA may indeed be more cost effective than PRA for safety engineering in lithium-ion battery systems. However, further research is needed to determine if this approach actually reduces safety engineering costs in development, or improves industry safety standards.

  8. Surface Mine System Simulation and Safety Risk Management

    ZHANG Rui-xin; YU Dong-fang; LI Xin-wang; YAO Xin-gang; LIU Yu

    2006-01-01

    Modern surface mines, either mono-system or multi-systems, need a large fleet of equipment consisting of excavators, loaders, haulers and auxiliary machines. Presently, the complexity of the system, the interference between sub-systems and the lag in management skills has been a bottle neck for improving productivity of the system. Based on the fact that the traditional tools for safety analysis have been insufficient to evaluate systematically and dynamically the safety risks, this paper tries to create a virtual reality tool consisting of human, machine and mines, using Pro/E and the 3D MAX software in order to evaluate visually the operations of typical mining equipment, such as the bucket wheel excavator (BWE), the shovel, the truck and the dragline. Within this virtual world, the behavior of the system, such as interaction, interference and potential risk can be replayed and reviewed visually. The objective of the study is to identify the critical safety issues of the system and to provide a convenient and powerful tool for safety training and safety management.

  9. Safety activities and human resource development at NCA

    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 252Cf neutron source. (S.K.)

  10. Evaluation Indicator System for China’s Agricultural Industrial Safety

    Qingpeng; GAO; Bin; CHEN; Qinyang; LI

    2013-01-01

    On the basis of new characteristics and trend of China’s agricultural development in the post-WTO period,combining analysis of factors influencing agricultural industrial safety,this paper builds an evaluation indicator system for China’s agricultural industrial safety by scientific indicator system design method.This indicator system includes risk factor indicators(showing risk degree)and capacity factor indicators(showing guaranteeing ability),and consists of 7 subsystems:consumption safety,production safety,industrial controlling capacity,industrial development capacity,industrial development environment,government functions and industrial foundation condition.Risk factor is divided into 5 levels:higher risk,high risk,medium risk,low risk and lower risk;guarantee risk is also divided into five levels:strong,healthy,normal,weak and disabled.According to the overall evaluation score obtained from weighting sum,the agricultural industrial safety includes 5 types:very safe,safe,basically safe,not safe and hazardous.This evaluation indicator system is expected to providing theoretical reference for evaluating China’s agricultural industrial safety.

  11. Modelling of Hazards Effect on Safety Integrity of Open Transmission Systems

    Karol Rástočný; Mária Franeková; Peter Holečko; Iveta Zolotová

    2016-01-01

    The paper is concerned with safety appraisal of safety-related communication systems (SRComSs) with open transmission system, where except in addition to message transmission integrity also confidentiality is recommended to be provided. The authors focused on safety analysis of safety-related messages transmission secured using cryptographic and safety code mechanisms and on the possibilities of modelling safety-related industrial communication system, where a high safety integrity level SIL3...

  12. Safety analysis of reactor's cooling system

    Results of the analysis of reactor's RBMK-1500 coolant system during normal operation mode, hydrodynamic testing and in the case of earthquake are presented. Analysis was performed using RELAP5 code. Calculations showed the most vulnerable place in the reactor's coolant system. It was found that in the case of earthquake the horizontal support system of drum separator could be damaged

  13. The advantages of reliability centered maintenance for standby safety systems

    of predictive monitoring. The testing in this strategy is part of an effort to ensure that the desired function is not only available today, but will be available tomorrow as well. This paper considers the application of a streamlined form of RCM to the Emergency Core Cooling (ECC) and Standby Diesel Generator (SDG) Systems of a CANDU plant. Recently completed studies provide useful insight into the important value added of the systematic assessment approach (using RCM techniques) for these standby safety systems. In the case of RCM analysis performed on the Emergency Core Cooling (ECC) System of Point Lepreau Nuclear Power Generating Station (PLGS), it was found that 60% of the current maintenance tasks are testing (functional, stroke, logic, and annunciation tests). Similarly, the SDGs have 50% of the maintenance tasks associated with testing. The paper considers how the results of the RCM analysis demonstrate that the analysis can be used to assist in the optimization of the testing program (as dictated by reliability) while also taking better advantage of the testing through condition monitoring and predictive maintenance techniques. Further, the results illustrate the importance of identifying and linking the different plant activities within a well integrated plant culture. (author)

  14. The advantages of reliability centered maintenance for standby safety systems

    predictive monitoring. The testing in this strategy is part of an effort to ensure that the desired function is not only available today, but will be available tomorrow as well. This paper considers the application of a streamlined form of RCM to the Emergency Core Cooling (ECC) and Standby Generator (SG) Systems of a CANDU plant. Recently completed studies provide useful insight into the important value added of the systematic assessment approach (using RCM techniques) for these standby safety systems. In the case of RCM analysis performed on the Emergency Core Cooling (ECC) System of Point Lepreau Nuclear Power Generating Station (PLGS), it was found that 60% of the current maintenance tasks are testing (functional, stroke, logic, and annunciation tests). Similarly, the SGs have 50% of the maintenance tasks associated with testing. The paper considers how the results of the RCM analysis demonstrate that the analysis can be used to assist in the optimization of the testing program dictated by reliability while also taking better advantage of the testing through condition monitoring and predictive maintenance techniques. Further, the results illustrate the importance of identifying and linking the different plant activities within a well integrated plant culture. (author)

  15. L-Band Digital Aeronautical Communications System Engineering - Initial Safety and Security Risk Assessment and Mitigation

    Zelkin, Natalie; Henriksen, Stephen

    2011-01-01

    This document is being provided as part of ITT's NASA Glenn Research Center Aerospace Communication Systems Technical Support (ACSTS) contract NNC05CA85C, Task 7: "New ATM Requirements--Future Communications, C-Band and L-Band Communications Standard Development." ITT has completed a safety hazard analysis providing a preliminary safety assessment for the proposed L-band (960 to 1164 MHz) terrestrial en route communications system. The assessment was performed following the guidelines outlined in the Federal Aviation Administration Safety Risk Management Guidance for System Acquisitions document. The safety analysis did not identify any hazards with an unacceptable risk, though a number of hazards with a medium risk were documented. This effort represents a preliminary safety hazard analysis and notes the triggers for risk reassessment. A detailed safety hazards analysis is recommended as a follow-on activity to assess particular components of the L-band communication system after the technology is chosen and system rollout timing is determined. The security risk analysis resulted in identifying main security threats to the proposed system as well as noting additional threats recommended for a future security analysis conducted at a later stage in the system development process. The document discusses various security controls, including those suggested in the COCR Version 2.0.

  16. Design of Traceability System for Pork Safety Production

    2009-01-01

    With the development of society and the improvement of living standards,consumers’demand for high quality meat products is constantly increasing.Traceability for livestock products is widely recognized to be an effective measure for any modern and integrated food safety control system.The quality tracing and traceability system of production’s entire processes is an important technology tool to protect pork safety.This paper proposes a RFID-enabled traceability system for pork supply chain.By adopting SQL Server 2000 databases and intelligent identification technology,a tracing system suitable to Chinese situation for monitoring and controlling quality of pork is constructed,and it manages to realize information traceability for entire pork production.The study indicates that the traceability system is valuable for practical reference and feasible.It can help consumers to confide in pork safety and encourage the pork industry developing.

  17. A safety system for a laser-beam utilising facility

    A safety system for a laser-beam utilising facility incorporates a safety enclosure and an infra-red monitoring system for detecting the development of hot spots at internal surfaces of the enclosure walls and ceiling which may occur as a result of stray laser radiation impinging on such surfaces. The development of a hot spot leads to shutting off the laser source or interruption of the beams by means of a shutter. The facility may be a welding or cutting apparatus and may be used with nuclear fuel elements. The monitoring system may be a scanning system. Two such scanning systems may be provided, scanning at different speeds, to detect respectively hot spots and the presence of a human body within the safety enclosure. (author)

  18. Digital Signal Processing for In-Vehicle Systems and Safety

    Boyraz, Pinar; Takeda, Kazuya; Abut, Hüseyin

    2012-01-01

    Compiled from papers of the 4th Biennial Workshop on DSP (Digital Signal Processing) for In-Vehicle Systems and Safety this edited collection features world-class experts from diverse fields focusing on integrating smart in-vehicle systems with human factors to enhance safety in automobiles. Digital Signal Processing for In-Vehicle Systems and Safety presents new approaches on how to reduce driver inattention and prevent road accidents. The material addresses DSP technologies in adaptive automobiles, in-vehicle dialogue systems, human machine interfaces, video and audio processing, and in-vehicle speech systems. The volume also features: Recent advances in Smart-Car technology – vehicles that take into account and conform to the driver Driver-vehicle interfaces that take into account the driving task and cognitive load of the driver Best practices for In-Vehicle Corpus Development and distribution Information on multi-sensor analysis and fusion techniques for robust driver monitoring and driver recognition ...

  19. New Paradigm in Nuclear Safety from Quality Assurance to Safety Management System

    The initial concept of Quality Control (QC) controlling the quality of products is now evolving toward the Management System (MS) achieving safety, through Quality Assurance (QA) ensuring the quality of products and Quality Management (QM) managing the quality by a systematic approach. Nuclear safety can be achieved through an integrated MS that ensures the health, environmental, security, quality and economic requirements being considered together with nuclear safety requirements. MS approach is developed through realizing that most of nuclear accidents had occurred not by the malfunction of hardware or equipment, but by the human error. The MS is a set of inter-related or interacting elements (system) that establishes policies and objectives and which enables those objectives to be achieved in an efficient and effective way

  20. Capturing Safety Requirements to Enable Effective Task Allocation Between Humans and Automaton in Increasingly Autonomous Systems

    Neogi, Natasha A.

    2016-01-01

    There is a current drive towards enabling the deployment of increasingly autonomous systems in the National Airspace System (NAS). However, shifting the traditional roles and responsibilities between humans and automation for safety critical tasks must be managed carefully, otherwise the current emergent safety properties of the NAS may be disrupted. In this paper, a verification activity to assess the emergent safety properties of a clearly defined, safety critical, operational scenario that possesses tasks that can be fluidly allocated between human and automated agents is conducted. Task allocation role sets were proposed for a human-automation team performing a contingency maneuver in a reduced crew context. A safety critical contingency procedure (engine out on takeoff) was modeled in the Soar cognitive architecture, then translated into the Hybrid Input Output formalism. Verification activities were then performed to determine whether or not the safety properties held over the increasingly autonomous system. The verification activities lead to the development of several key insights regarding the implicit assumptions on agent capability. It subsequently illustrated the usefulness of task annotations associated with specialized requirements (e.g., communication, timing etc.), and demonstrated the feasibility of this approach.

  1. Critical Characteristics of Radiation Detection System Components to be Dedicated for use in Safety Class and Safety Significant System

    This document identifies critical characteristics of components to be dedicated for use in Safety Significant (SS) Systems, Structures, or Components (SSCs). This document identifies the requirements for the components of the common, radiation area, monitor alarm in the WESF pool cell. These are procured as Commercial Grade Items (CGI), with the qualification testing and formal dedication to be performed at the Waste Encapsulation Storage Facility (WESF) for use in safety significant systems. System modifications are to be performed in accordance with the approved design. Components for this change are commercially available and interchangeable with the existing alarm configuration This document focuses on the operational requirements for alarm, declaration of the safety classification, identification of critical characteristics, and interpretation of requirements for procurement. Critical characteristics are identified herein and must be verified, followed by formal dedication, prior to the components being used in safety related applications

  2. Remarks on statistical aspects of safety analysis of complex systems

    Pál, L

    2003-01-01

    We analyze safety problems of complex systems using the methods of mathematical statistics for testing the output variables of a code simulating the operation of the system under consideration when the input variables are uncertain. We have defined a black box model of the code and derived formulas to calculate the number of runs needed for a given confidence level to achieve a preassigned measure of safety. In order to show the capabilities of different statistical methods, firstly we have investigated one output variable with unknown and known distribution functions. The general conclusion has been that the different methods do not bring about large differences in the number of runs needed to ensure a given level of safety. Analyzing the case of several statistically dependent output variables we have arrived at the conclusion that the testing of the variables separately may lead to false, safety related decisions with unforseen consequences. We have advised two methods: the sign test and the tolerance inte...

  3. The system 80+ design for safety, economy, and reliability

    ABB Combustion Engineering, Inc. and Duke Engineering and Service, Inc. have been developing the next generation of pressurized water reactor (PWR), the System 80+TM Standard Plant, for worldwide deployment since 1985. The complete 18-volume standard safety analysis report (CESSAR-DC) was officially docketed by the U.S. Nuclear Regulatory Commission (NRC) in May 1991, answers to over 1,500 NRC questions were completed in early 1992, and the draft Safety Evaluation Report (SER) was issued in September 1992. Severe accident prevention and mitigation are the major focus of regulatory review for next generation designs. Severe accident design features, management guidelines, and a probabilistic safety assessment for both power and shutdown conditions, were refined and completed in 1992 to address new NRC requirements. System 80+ represents a major advancement in the technology of PWR safety. Accidents are far less probable -- the result of a balanced and integrated approach to nuclear plant design that considers both prevention and mitigation. (author)

  4. Failure and factors of safety in piping system design

    An important body of test and performance data on the behavior of piping systems has led to an ongoing reassessment of the code stress allowables and their safety margin. The codes stress allowables, and their factors of safety, are developed from limits on the incipient yield (for ductile materials), or incipient rupture (for brittle materials), of a test specimen loaded in simple tension. In this paper, we examine the failure theories introduced in the B31 and ASME III codes for piping and their inherent approximations compared to textbook failure theories. We summarize the evolution of factors of safety in ASME and B31 and point out that, for piping systems, it is appropriate to reconsider the concept and definition of factors of safety

  5. Failure and factors of safety in piping system design

    Antaki, G.A.

    1993-01-01

    An important body of test and performance data on the behavior of piping systems has led to an ongoing reassessment of the code stress allowables and their safety margin. The codes stress allowables, and their factors of safety, are developed from limits on the incipient yield (for ductile materials), or incipient rupture (for brittle materials), of a test specimen loaded in simple tension. In this paper, we examine the failure theories introduced in the B31 and ASME III codes for piping and their inherent approximations compared to textbook failure theories. We summarize the evolution of factors of safety in ASME and B31 and point out that, for piping systems, it is appropriate to reconsider the concept and definition of factors of safety.

  6. Failure and factors of safety in piping system design

    Antaki, G.A.

    1993-06-01

    An important body of test and performance data on the behavior of piping systems has led to an ongoing reassessment of the code stress allowables and their safety margin. The codes stress allowables, and their factors of safety, are developed from limits on the incipient yield (for ductile materials), or incipient rupture (for brittle materials), of a test specimen loaded in simple tension. In this paper, we examine the failure theories introduced in the B31 and ASME III codes for piping and their inherent approximations compared to textbook failure theories. We summarize the evolution of factors of safety in ASME and B31 and point out that, for piping systems, it is appropriate to reconsider the concept and definition of factors of safety.

  7. Safety Cases for Global Navigation Satellite Systems' Safety of Life(SOL) Applications

    Johnson, C. W.; Yepez, Amaya Atencia

    2010-09-01

    Global Navigation Satellite Systems(GNSS) have recently been enhanced to provide additional guarantees for the accuracy, integrity, reliability and coverage of their services. These infrastructures are intended to be robust against jamming. They support real-time self-diagnostic error detection and provide end-users with detailed information about precision and integrity. In consequence, they are gradually being introduced into safety-related applications. This paper argues that greater attention needs to be paid to the ways in which these navigation infrastructures are being integrated into the safety cases that support Safety of Life(SoL) applications. In particular, we contrast the significant investments that have been made in analysing the safety of GNSS aviation applications, such as en-route operations and non-precision approaches, with the relative lack of progress in other industries. There is also a need for greater consistency between the safety arguments that support similar GNSS applications. This helps to ensure that safety managers and regulators consider a similar set of hazards when seeking to integrate these new navigation infrastructures into SoL systems. While international aviation organisations have taken important steps to establish communication mechanisms within their industry, the same cannot be said for other industries. The ad hoc nature of the safety arguments supporting many recent proposals creates a danger that technological innovation will outstrip our commitment to mitigate or avoid future hazards. Unless these issues are addressed then accidents involving the first wave of SoL applications will further jeopardise the development of GNSS infrastructures.

  8. Artificial intelligence enhancements to safety parameter display systems

    Two prototype knowledge based systems have been developed at The Ohio State University to be the basis of an operator aid that can be attached to an existing nuclear power plant Safety Parameter Display System. The first system uses improved sensor validation techniques to provide input to a fault diagnosis process. The second system would use the diagnostic system output to synthesize corrective procedures to aid the control room licensed operator in plant recovery

  9. Use of digital computing devices in systems important to safety

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

  10. IRIS safety system and equipment design verification test plan

    The International Reactor Innovative and Secure (IRIS) is an advanced, integral, light-water cooled reactor of medium generating capacity (335 MWe), geared at near term deployment (2012-2015). IRIS is an innovative design that features an integral reactor vessel that contains all the reactor coolant system components, including the steam generators, coolant pumps, pressurizer and heaters, and control rod drive mechanisms; in addition to the: typical core, internals, control rods and neutron reflector. Other IRIS innovations also include a small, high design pressure, spherical steel containment; and a simplified passive safety system concept and equipment features that derive from its unique 'safety-by-design' IM philosophy. The IRIS ('safety-by-design')TM approach not only improves safety, but it also reduces the overall cost by allowing a significant reduction and simplification in safety systems. Moreover, IRIS improved safety supports licensing the power plant without the need for off-site emergency response planning an objective which is part of the pre-application with NRC and is also is being pursued in collaboration with IAEA. The IRIS innovative integral reactor coolant system design, as well as its innovative ('safety-by-design')TM approach features, has resulted in the need for new safety analyses and new equipment design and qualification, in order to successfully license the plant. Therefore, the IRIS design team has developed a test plan that will provide the necessary data for safety analyses verification as well as the demonstration of equipment manufacturing feasibility and operation. This paper will present the 'IRIS Safety System and Equipment Design Verification Test Plan' which develops and confirms the operation of all the IRIS unique features, and includes component manufacturing feasibility tests, component separate effects tests, component qualification tests, and integral effects tests. These tests will also provide the data necessary to

  11. A regulatory frame for safety digital systems in nuclear power plants

    The paper focuses on Spanish experience regarding software based systems for safety applications from the regulator's point of view. It describes the actual situation in Spain, number and models of reactors, modernization projects, digital systems implemented and licensing documentation and processes already followed by some upgrading projects. The paper wonders what documents should be required for safety and reliability demonstration of a safety system, when they should be reviewed, and what other activities may be necessary to acquire confidence on a particular system. It describes Spanish laws regarding nuclear safety under which, national standards from the NPP design original country apply to nuclear reactors in Spain. It finally suggests that an international standard jointly used by system manufacturers, nuclear licensees and nuclear safety authorities, both from the country where the NPP is installed, and from the original design country, should be developed so that rapid and easy agreement on licensing issues is reached among all parties. The last part of the paper describes the licensing approach proposed by CSN (Spanish Nuclear Safety Authority). It is still under development and it is based on previous experience on digital systems for non-safety applications. It consists of constructing several frames: 1) databases of existing software based systems, 2) guides for inspection and 3) questionnaires for helping in verification and validation activities evaluation. The scope is to establish a well defined procedure that helps in evaluating the particular system. However, in order for such a procedure to be useful, both regulators and utilities and, perhaps also system manufacturers, should agree on it. Joint CSN-utilities working groups may be suitable for such a purpose. (author)

  12. HANARO Safety Performance Indicators

    HANARO is a 30 MW open-tank-in-pool type multi-purpose research reactor. Safety improvement activities have been implemented and the importance of safety management in nuclear activities for reactor application and utilization has also been emphasized. Safety performance indicators (SPIs) are used to assess the safety management status, in combination with other factors such as safety culture, human performance and operation status. The SPI system can provide a proactive approach to complement other safety assessment activities. HANARO has tried to develop a programme for the establishment of safety performance indicators. In this paper the application experience of safety performance indicators in HANARO is described. (author)

  13. Study on safety classifications of software used in nuclear power plants and distinct applications of verification and validation activities in each class

    This paper describes the safety classification regarding instrumentation and control (I and C) systems and their software used in nuclear power plants, provides regulatory positions for software important to safety, and proposes verification and validation (V and V) activities applied differently in software classes which are important elements in ensuring software quality assurance. In other word, the I and C systems important to safety are classified into IC-1, IC-2, IC-3, and Non-IC and their software are classified into safety-critical, safety-related, and non-safety software. Based upon these safety classifications, the extent of software V and V activities in each class is differentiated each other. In addition, the paper presents that the software for use in I and C systems important to safety is divided into newly-developed and previously-developed software in terms of design and implementation, and provides the regulatory positions on each type of software

  14. System and safety studies of accelerator driven transmutation systems. Annual report 1999

    In 1996, SKB commenced funding of the project 'System and safety studies of accelerator driven transmutation systems and development of a spallation target'. The aim of the project was stated as: Development of a complete code for simulation of transmutation processes in an accelerator driven system. Application of the code for analysis of neutron flux, transmutation rates, reactivity changes, toxicity and radiation damages in the transmutation core. Build up of competence regarding issues related to spallation targets, development of research activities regarding relevant material issues. Performing of basic experiments in order to investigate the adequacy of using the spallation. target as a neutron source for a transmutation system, and participation in the planning and implementation of an international demonstration experiment. In the present report, activities within and related to the framework of the project, performed at the department of Nuclear and Reactor Physics at the Royal Institute of Technology during 1999, are accounted for

  15. Nuclear safety enhancement of the Instrumentation and Control System at TRIGA SSR 14 MW-Romania

    Preda, Marin; Ciocanescu, Marin; Mugurel Ana, Emil; Barbalata, Eugenia [Institute for Nuclear Research, Pitesti (Romania)

    2008-10-29

    In order to comply with the IAEA safety standards and national regulations and to enhance the nuclear safety at TRIGA SSR 14 MW Romanian reactor in 2006 has began a process of instrumentation and control system modifications. By taking account of the operation experience and IAEA guides, the basic requirement for instrumentation and control system modification is the separation between safety and operating components in order to decrease the human error consequences and avoid the common cause failures. Beside that system modernization consists in TRIGA 14 MW console replacement. New instrumentation and control system consists in: - a new reactor operation console, that contains all the necessary modules for reactor operation and parameter display, - three racks for control system that contains all the necessary modules for safety parameter measurement and in scram logic the required redundancy, data acquisition, annunciators, - a terminal boundary rack for connections between field transducers and control room equipments. Modernization did not cover any sensor replacement but keep the actual scram logic and enhance the reactor safety features. The instrumentation and control system is designed, manufactured by INVAP Argentina and will be delivered, installed and tested by the end of 2008. Following to these activities safety documentation will be completed and issued to National Regulatory Body in order to obtain the operation license. Financially the Project is supported by IAEA Vienna and Romanian Government in the framework of a technical cooperation program. (authors)

  16. Design of integrated passive safety system (IPSS) for ultimate passive safety of nuclear power plants

    Highlights: • We newly propose the design concept of integrated passive safety system (IPSS). • It has five safety functions for decay heat removal and severe accident mitigation. • Simulations for IPSS show that core melt does not occur in accidents with SBO. • IPSS can achieve the passive in-vessel retention and ex-vessel cooling strategy. • The applicability of IPSS is high due to the installation outside the containment. -- Abstract: The design concept of integrated passive safety system (IPSS) which can perform various passive safety functions is proposed in this paper. It has the various functions of passive decay heat removal system, passive safety injection system, passive containment cooling system, passive in-vessel retention and cavity flooding system, and filtered venting system with containment pressure control. The objectives of this paper are to propose the conceptual design of an IPSS and to estimate the design characters of the IPSS with accident simulations using MARS code. Some functions of the IPSS are newly proposed and the other functions are reviewed with the integration of the functions. Consequently, all of the functions are modified and integrated for simplicity of the design in preparation for beyond design based accidents (BDBAs) focused on a station black out (SBO). The simulation results with the IPSS show that the decay heat can be sufficiently removed in accidents that occur with a SBO. Also, the molten core can be retained in a vessel via the passive in-vessel retention strategy of the IPSS. The actual application potential of the IPSS is high, as numerous strong design characters are evaluated. The installation of the IPSS into the original design of a nuclear power plant requires minimal design change using the current penetrations of the containment. The functions are integrated in one or two large tanks outside the containment. Furthermore, the operation time of the IPSS can be increased by refilling coolant from the

  17. Design of integrated passive safety system (IPSS) for ultimate passive safety of nuclear power plants

    Chang, Soon Heung; Kim, Sang Ho, E-mail: proton@kaist.ac.kr; Choi, Jae Young

    2013-07-15

    Highlights: • We newly propose the design concept of integrated passive safety system (IPSS). • It has five safety functions for decay heat removal and severe accident mitigation. • Simulations for IPSS show that core melt does not occur in accidents with SBO. • IPSS can achieve the passive in-vessel retention and ex-vessel cooling strategy. • The applicability of IPSS is high due to the installation outside the containment. -- Abstract: The design concept of integrated passive safety system (IPSS) which can perform various passive safety functions is proposed in this paper. It has the various functions of passive decay heat removal system, passive safety injection system, passive containment cooling system, passive in-vessel retention and cavity flooding system, and filtered venting system with containment pressure control. The objectives of this paper are to propose the conceptual design of an IPSS and to estimate the design characters of the IPSS with accident simulations using MARS code. Some functions of the IPSS are newly proposed and the other functions are reviewed with the integration of the functions. Consequently, all of the functions are modified and integrated for simplicity of the design in preparation for beyond design based accidents (BDBAs) focused on a station black out (SBO). The simulation results with the IPSS show that the decay heat can be sufficiently removed in accidents that occur with a SBO. Also, the molten core can be retained in a vessel via the passive in-vessel retention strategy of the IPSS. The actual application potential of the IPSS is high, as numerous strong design characters are evaluated. The installation of the IPSS into the original design of a nuclear power plant requires minimal design change using the current penetrations of the containment. The functions are integrated in one or two large tanks outside the containment. Furthermore, the operation time of the IPSS can be increased by refilling coolant from the

  18. A fundamental study for safety in advanced PWR systems

    Park, Goon Cherl; Kang, C. S.; Lee, E. C.; Kim, S. N.; Lee, J. S.; Kim, M. H.; Chae, W. S.; Kim, M. H.; Lee, D. H.; No, S. T.; Jeon, G. D.; Lee, T. H.; Kim, B. S.; Park, H. J.; Yoon, J. I.; Kim, J. H.; Jeon, J. H.; Jang, W. H.; Sa, Y. C.; Lee, H. W.; Kim, S. J.; Kim, J. W.; Kim, Y. H.; Lee, S. W.; Yang, C. G.; Kim, Y. S.; Ha, J. B.; Son, M. S.; An, Y. C.; Bae, S. W. [Seoul National University, Seoul (Korea, Republic of)

    1997-07-01

    For the development of integral type small and medium reactor which is remarkably safer than existing plants, the operability of passive safety systems should be studied and its applicability to the integral type reactor should be evaluated. The purposes of this study are to evaluate the characteristics of various passive safety systems and provide the proper data for the future design with performing experiments and developing analytical methodology. Thus in this study, the following techniques for small reactors and passive safety systems subject to this study are evaluated and a part of basic experiments and numerical works necessary to the experiments were performed, First, heat pipes used in containment vessel which removes hear by passive mechanism during accidents, second, natural circulation characteristics for the passive safety analysis of integrated reactor, third, heat evaluation of the effective function of hydraulic valve in passive decay heat removal systems, fifth, the determination of the improved source term for the integral reactor, and the last, passive containment cooling system, which is the first step in the analysis of the integrated safety and the environmental impacts of nuclear power plant. 184 refs., 49 tabs., 188 figs. (author)

  19. SAFETY

    M. Plagge, C. Schaefer and N. Dupont

    2013-01-01

    Fire Safety – Essential for a particle detector The CMS detector is a marvel of high technology, one of the most precise particle measurement devices we have built until now. Of course it has to be protected from external and internal incidents like the ones that can occur from fires. Due to the fire load, the permanent availability of oxygen and the presence of various ignition sources mostly based on electricity this has to be addressed. Starting from the beam pipe towards the magnet coil, the detector is protected by flooding it with pure gaseous nitrogen during operation. The outer shell of CMS, namely the yoke and the muon chambers are then covered by an emergency inertion system also based on nitrogen. To ensure maximum fire safety, all materials used comply with the CERN regulations IS 23 and IS 41 with only a few exceptions. Every piece of the 30-tonne polyethylene shielding is high-density material, borated, boxed within steel and coated with intumescent (a paint that creates a thick co...

  20. A Study of Cyber Security Activities for Development of Safety-related Controller

    Nuclear Power Plant Regulatory guide describes the regulatory requirements to implement cyber security activities to ensure that design and operate to respond to cyber threats that exploited to vulnerability of digital-based technologies associated with safety-related digital instrumentation and control systems at nuclear power plants. Cyber security activities coverage is instrumentation and control systems to perform safety functions and digital-based equipment to use development, test, analysis and asset for instrumentation and control systems. Regulatory guidance is required to the cyber security activities that should be performed in each development phase of safety-related controller. Development organization should establish and implement to cyber security plans for responding to cyber threats throughout each lifecycle phase and the result of the cyber security activities should be generated to the documents. In addition, the independent verification and validation organization should perform simulated penetration test for enhancing response capabilities to cyber security threats and development organization should establish and implement response hardening solutions for the cyber security vulnerabilities identified in the simulated penetration test

  1. Effect of national cultural values on safety climate, and safety management system

    This paper investigates the critical role played by the national culture in influencing how workers safely or otherwise behave (mainly in risky situations) on construction sites, and how site managers implement safety management processes and practices. The paper presents the findings of an empirical research study based on a questionnaire survey, administered in Pakistan, targeting construction site managers and workers to gauge the effect national culture has on managers preferences for and perceptions of safety management systems (policies and practices) and than linking this effect to predict workers attitudes and intentional behaviors. (author)

  2. Safety- and Risk Analysis Activities in Chemical Industry in Europe

    European and International mechanism of handling safety- and risk-related matters. So, the Organisation for Economic Co-operation and Development's (OECD) core objective on risk management is to support Member countries' efforts to develop national policies and actions, and, where appropriate, to develop and implement international risk management measures. In support of this objective, the OECD Risk Management Programme focuses on two areas: (1) developing methods and technical tools that can be used by OECD and Member countries to enhance their current risk management programmes; and (2) identifying specific chemical exposures of concern in Member countries and evaluating possible risk management opportunities. The current paper highlights the EU legislation on major accident hazards related to the chemical industry, differences in the national approaches to risk analyses in the process industry and European-scale activity in improving the understanding of the sources of uncertainty in risk assessments

  3. Risk and safety analysis of nuclear systems

    Lee, John C

    2011-01-01

    The book has been developed in conjunction with NERS 462, a course offered every year to seniors and graduate students in the University of Michigan NERS program. The first half of the book covers the principles of risk analysis, the techniques used to develop and update a reliability data base, the reliability of multi-component systems, Markov methods used to analyze the unavailability of systems with repairs, fault trees and event trees used in probabilistic risk assessments (PRAs), and failure modes of systems. All of this material is general enough that it could be used in non-nuclear a

  4. Monitoring and crisis system of radiation safety

    In this paper we have briefly described our practical experiences with the most complex Radiation Monitoring System we have designed. This system consists of number of stations; those data are collected in the main crisis center of the whole system. The main center integrates RMS Central Database, the IMS Model Suite workstation and the Graphics workstation. The radiations probes of the RP series are the base for stationary , portable sets and for sets measuring underwater radiation. The radiation and meteorological data, which are necessary for reasonable interpretation of radiation data, are archived in RMS Central database. The Lagrangian trajectory model from the IMS Model Suite serves for radiation dispersion modeling. (authors)

  5. Rapid Prototyping of the Central Safety System for Nuclear Risk in ITER

    Full text of publication follows: In the current ITER Baseline design, the Central Safety System for Nuclear Risk (CSS-N) is the safety control system in charge to assure nuclear safety for the plant, personnel and environment. In particular it is envisaged that the CSS shall interface to the plant safety systems for nuclear risk and shall coordinate the individual protection provided by the intervention of these systems by the activation, where required, of additional protections. The design of such a system, together with its implementation, strongly depends on the requirements, particularly in terms of reliability. The CSS-N is a safety critical system, thus its validation and commissioning play a very important role, since the required level of reliability must be demonstrated. In such a scenario, where a new and non-conventional system has to be deployed, it is strongly recommended to use modeling and simulation tools since the early design phase. Indeed, the modeling tools will help in the definition of the system requirements, and they will be used to test and validate the control logic. Furthermore these tools can be used to rapid design the safety system and to carry out hardware-in-the-loop (HIL) simulations, which permit to assess the performance of the control hardware against a plant simulator. Both a control system prototype and a safety system oriented plant simulator have been developed to assess first the requirements and then the performance of the CSS-N. In particular the presented SW/HW framework permits to design and verify the CSS protection logics and to test and validate these logics by means of HIL simulations. This work introduces both the prototype and plant simulator architectures, together with the methodology adopted to design and implement these validation tools. (authors)

  6. Expert evaluation in NPP safety important systems licensing process

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

  7. Russian NPP I and C systems and NPP safety problems

    The long experience of nuclear power plant (NPP) operation both in Russia and over the world confirms that both power and economic characteristics as well as NPP safety depend on possibilities and specifications of instrumentation and control (I and C) systems. That is why the more serious attention is paid to the problems of improvement of I and C systems in all countries

  8. New reactor technology: safety improvements in nuclear power systems.

    Corradini, M L

    2007-11-01

    Almost 450 nuclear power plants are currently operating throughout the world and supplying about 17% of the world's electricity. These plants perform safely, reliably, and have no free-release of byproducts to the environment. Given the current rate of growth in electricity demand and the ever growing concerns for the environment, nuclear power can only satisfy the need for electricity and other energy-intensive products if it can demonstrate (1) enhanced safety and system reliability, (2) minimal environmental impact via sustainable system designs, and (3) competitive economics. The U.S. Department of Energy with the international community has begun research on the next generation of nuclear energy systems that can be made available to the market by 2030 or earlier, and that can offer significant advances toward these challenging goals; in particular, six candidate reactor system designs have been identified. These future nuclear power systems will require advances in materials, reactor physics, as well as thermal-hydraulics to realize their full potential. However, all of these designs must demonstrate enhanced safety above and beyond current light water reactor systems if the next generation of nuclear power plants is to grow in number far beyond the current population. This paper reviews the advanced Generation-IV reactor systems and the key safety phenomena that must be considered to guarantee that enhanced safety can be assured in future nuclear reactor systems. PMID:18049233

  9. Architecture for decision making in a home safety system

    Uusitalo, Ilkka; Mantere, Matti

    2012-01-01

    We describe the requirements and architecture for decision making in the context of a home safety system. The architecture is capable of local- and network supported decision making. To develop and test the architecture in practice we define a use case of an elderly man in his daily chores. We also discuss the ethical concerns posed by such a system.

  10. Use of expert systems in nuclear safety

    One dominant aspect of improvement in safe nuclear power plant operation is the very high speed in the development and introduction of computer technologies. This development commenced recently when advanced control technology was incorporated into the nuclear industry. This led to an increasing implementation of information displays, annunciator windows and other devices inside the control room, eventually overburdening the control room operator with detailed information. Expert systems are a further step in this direction being designed to apply large knowledge bases to solve practical problems. These ''intelligent'' systems have to incorporate enough knowledge to reach expert levels of importance and represent a very advanced man-machine interface. The aims of the Technical Committee were addressed by the three Working Groups and summarized in Sections 2, 3 and 4 of this report. Section 2 summarizes the results and discussions on the current capabilities of expert systems and identifies features for the future development and use of Expert Systems in Nuclear Power Plants. Section 3 provides an overview of the discussions and investigations into the current status of Expert Systems in NPPs. This section develops a method for assessing the overall benefit of different applications and recommends a broad strategy for priority developments of Expert Systems in NPPs. Section 4 assesses the overall use of PSA type studies in Expert Systems in NPPs and identifies specific features to be adopted in the design of these systems in future applications. The conclusions of the three Working Groups are presented in Section 5. The 15 papers presented at the meeting formed the Annex of this document. A separate abstract was prepared for each of these papers. Refs, figs, tabs and pictures

  11. [New international initiatives to create systems of effective risk prediction and food safety].

    Efimochkinal, N R; Bagryantseva, E C; Dupouy, E C; Khotimchenko, S A; Permyakov, E V; Sheveleva, S A; Arnautov, O V

    2016-01-01

    Ensuring food safety is one of the most important problems that is directly related to health protection of the population. The problem is particularly relevant on aglobalscale because ofincreasingnumberoffood-borne diseases andimportance of the health consequence early detection. In accordance with the position of the Codex Alimentarius Commission, food safety concept also includes quality. In this case, creation of the national, supranational and international early warning systems related to the food safety, designed with the purpose to prevent or minimize risks on different stages of the food value chain in various countries, regions and climate zones specific to national nutrition and lifestyle in different groups of population, gains particular importance. The article describes the principles and working examples of international, supranational and national food safety early warning systems. Great importance is given to the hazards of microbial origin - emergent pathogens. Example of the rapid reaction to the appearance of cases, related to the melanin presence in infant formula, are presented. Analysis of the current food safety and quality control system in Russian Federation shows that main improvements are mostly related to the development of the efficient monitoring, diagnostics and rapid alert procedures forfood safety on interregional and international levels that will allow to estimate real contamination of food with the most dangerous pathogens, chemical and biological contaminants, and the development of the electronic database and scientifically proved algorithms for food safety and quality management for targeted prevention activities against existing and emerging microbiological and other etiology risks, and public health protection. PMID:27455605

  12. ADASY (Active Daylighting System)

    Vázquez-Moliní, Daniel; González-Montes, Mario; Fernández-Balbuena, Antonio Á.; Bernabéu, Eusebio; García-Botella, Ángel; García-Rodríguez, Lucas; Pohl, Wilfried

    2009-08-01

    The main objective of ADASY (Active Daylighting System) work is to design a façade static daylighting system oriented to office applications, mainly. The goal of the project is to save energy by guiding daylight into a building for lighting purpose. With this approach we can reduce the electrical load for artificial lighting, completing it with sustainable energy. The collector of the system is integrated on a vertical façade and its distribution guide is always horizontal inside of the false ceiling. ADASY is designed with a specific patent pending caption system, a modular light-guide and light extractor luminaire system. Special care has been put on the final cost of the system and its building integration purpose. The current ADASY configuration is able to illuminate 40 m2 area with a 300lx-400lx level in the mid time work hours; furthermore it has a good enough spatial uniformity distribution and a controlled glare. The data presented in this study are the result of simulation models and have been confirmed by a physical scaled prototype. ADASY's main advantages over regular illumination systems are: -Low maintenance; it has not mobile pieces and therefore it lasts for a long time and require little attention once installed. - No energy consumption; solar light continue working even if there has been a power outage. - High quality of light: the colour rendering of light is very high - Psychological benefits: People working with daylight get less stress and more comfort, increasing productivity. - Health benefits

  13. A Nuclear Safety System based on Industrial Computer

    The Plant Protection System(PPS), a nuclear safety Instrumentation and Control (I and C) system for Nuclear Power Plants(NPPs), generates reactor trip on abnormal reactor condition. The Core Protection Calculator System (CPCS) is a safety system that generates and transmits the channel trip signal to the PPS on an abnormal condition. Currently, these systems are designed on the Programmable Logic Controller(PLC) based system and it is necessary to consider a new system platform to adapt simpler system configuration and improved software development process. The CPCS was the first implementation using a micro computer in a nuclear power plant safety protection system in 1980 which have been deployed in Ulchin units 3,4,5,6 and Younggwang units 3,4,5,6. The CPCS software was developed in the Concurrent Micro5 minicomputer using assembly language and embedded into the Concurrent 3205 computer. Following the micro computer based CPCS, PLC based Common-Q platform has been used for the ShinKori/ShinWolsong units 1,2 PPS and CPCS, and the POSAFE-Q PLC platform is used for the ShinUlchin units 1,2 PPS and CPCS. In developing the next generation safety system platform, several factors (e.g., hardware/software reliability, flexibility, licensibility and industrial support) can be considered. This paper suggests an Industrial Computer(IC) based protection system that can be developed with improved flexibility without losing system reliability. The IC based system has the advantage of a simple system configuration with optimized processor boards because of improved processor performance and unlimited interoperability between the target system and development system that use commercial CASE tools. This paper presents the background to selecting the IC based system with a case study design of the CPCS. Eventually, this kind of platform can be used for nuclear power plant safety systems like the PPS, CPCS, Qualified Indication and Alarm . Pami(QIAS-P), and Engineering Safety

  14. Cooperatively active sensing system

    Aiming at development of a strong and flexible sensing system, a study on a sensing technology prepared with cooperativity, activity, and real time workability has been promoted. In the former period, together with preparation of plural moving robot group with real time processing capacity of a lot of sensor informations composing of platform, a parallel object direction language Eus Lisp effectively capable of describing and executing cooperative processing and action therewith was developed. And, it was also shown that capacity to adaptively act even at dynamic environment could be learnt experientially. And, on processing of individual sensor information, application of a photographing system with multiple resolution property similar to human visual sense property was attempted. In the latter period, together with intending of upgrading on adaptability of sensing function, by using moving robot group in center of a moving robot loaded with active visual sense, a cooperative active sensing prototype system was constructed to show effectiveness of this study through evaluation experiment of patrolling inspection at plant simulating environment. (G.K.)

  15. AP1000 passive safety system design and analysis

    Westinghouse Electric Company has designed an advanced 600 MW nuclear power plant called the AP600. The AP600 uses passive safety systems to enhance plant safety and to satisfy US licensing requirements. The use of passive safety systems has provided significant and measurable improvements in plant simplification, safety, reliability, investment protection and plant costs. The overnight capital cost for the first AP600 plant is calculated to be between 1300- 1500 $/kw depending on the site selection. Although the AP600 is the most cost effective plant ready for deployment, it is still more expensive than the $1000/kw needed to compete in the United States today. In order to develop a cost competitive nuclear power plant Westinghouse has completed design studies which demonstrate that it is feasible to increase the power output of the AP600 to at least 1000 MW, maintaining its current design configuration, use of proven components and licensing basis. The AP1000 reactor and passive safety features retain the same configuration as the AP600. The approach to designing the passive core cooling features is to evaluate each feature to determine if changes are necessary to provide proper safety margins at the higher power rating. Both design basis and PRA based accidents sequences are considered in this evaluation. Insights from the extensive AP600 test and analysis program are used to assist in this process. The results of preliminary accident analysis for DBA and PRA sequences are used to demonstrate the effectiveness of this approach. (author)

  16. Safety assessment of emergency power systems for nuclear power plants

    This publication is intended to assist the safety assessor within a regulatory body, or one working as a consultant, in assessing the safety of a given design of the emergency power systems (EPS) for a nuclear power plant. The present publication refers closely to the NUSS Safety Guide 50-SG-D7 (Rev. 1), Emergency Power Systems at Nuclear Power Plants. It covers therefore exactly the same technical subject as that Safety Guide. In view of its objective, however, it attempts to help in the evaluation of possible technical solutions which are intended to fulfill the safety requirements. Section 2 clarifies the scope further by giving an outline of the assessment steps in the licensing process. After a general outline of the assessment process in relation to the licensing of a nuclear power plant, the publication is divided into two parts. First, all safety issues are presented in the form of questions that have to be answered in order for the assessor to be confident of a safe design. The second part presents the same topics in tabulated form, listing the required documentation which the assessor has to consult and those international and national technical standards pertinent to the topics. An extensive reference list provides information on standards. 1 tab

  17. A software cost model with maintenance and risk costs for safety-critical systems

    LIU Hong-wei; YANG Xiao-zong; QU Feng; DONG Jian

    2006-01-01

    According to the consequences of software failures, software faults remaining in safety-critical systems can be classified into two sets: common faults and fatal faults. Common faults cause slight loss when they are activated. A fatal fault can lead to significant loss, and even damage the safety-critical system entirely when it is activated. A software reliability growth model for safety-critical systems is developed based on G-O model. And a software cost model is proposed too. The cost model considers maintenance and risk costs due to software failures. The optimal release policies are discussed to minimize the total software cost. A numerical example is provided to illustrate how to use the results we obtained.

  18. Low- and Intermediate Level Radioactive Waste Disposal Environmental and Safety Assessment Activities in Slovenia

    The protection of the environment is one of the main concerns in the management of radioactive waste, especially in repository planning. In different stages of repository lifetime the environmental assessment has different functions: it can be used as a decision making process and as a planning, communication and management tool. Safety assessment as a procedure for evaluating the performance of a disposal system, and its potential radiological impact on human health and environment, is also required. Following the international recommendations and Slovene legislation, a presentation is given of the role and importance of the environmental and safety assessment activities in the early stages following concept development and site selection for a low- and intermediate level radioactive waste (LILW) repository in Slovenia. As a case study, a short overview is also given of the preliminary safety assessment that has been carried out in the analysis of possibilities for long-lived LILW disposal in Slovenia. (author)

  19. Combining disparate sources of information in the safety assessment of software-based systems

    Dahll, G. [OECD Halden Reactor Project, Halden (Norway)

    2000-02-01

    The main topic of the paper is a discussion on how to combine disparate sources of information in the safety assessment of software-based systems. This is based on experience gained through the licensing process of a programmable system in the Swedish nuclear power plant Ringhals, where a guideline for reviewing software in safety-related systems was applied. One lesson learned from this activity is that the approval of a programmable safety critical system, in particular one which is based on commercial-off-the-shelf software, is based on a combination of disparate sources of information. This combination of information is made in a diagrammatic framework. An emerging methodology to combine information about disparate evidences in a systematic way is based on Bayesian belief networks. The objective is to show the link between basic information and the confidence one can have in a system. (orig.)

  20. NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security. Issue no. 3, April 2007

    This newsletter reports on the manual for first responders to a radiological emergency, the IAEA's testing laboratory for radiation measurement, monitoring and protection, which is the first UN laboratory accredited to the international standard ISO17025, and the International Conference on Lessons Learned fro the Decommissioning of Nuclear Facilities and the Safe Termination of Nuclear Activities. The IAEA, in recognition of this critical need, has developed a Manual for First Responders to a Radiological Emergency with the objective to provide practical guidance for those responding within the first few hours of a radiological emergency. This guidance document is co-sponsored by the Comite technique international de prevention et d'extinction du feu (CTIF), the Pan American Health Organization (PAHO) and the World Health Organization (WHO). The Manual for First Responders provides guidance in the form of action guides, instructions, and supporting data that can be easily applied by a State to build a basic capability to respond to a radiological emergency. The guidance also contains practical procedures and tools on the response to a radiological emergency again easily and quickly adaptable by Member States to prepare first responders to respond adequately to a radiological emergency. The Manual can be used for training purposes at the preparedness stage as well as during the response. The Policy and Programme Support Section (PPSS) within the Division of Radiation, Transport and Waste Security (NSRW) has been operating, for many years, a laboratory (the Testing Laboratory) for radiation safety monitoring of individuals and workplaces. The establishment of a quality management system, as required in the International Basic Safety Standards (the BSS), started in 2000 to cover all measurement methods of the laboratory. This system is based on the international standard ISO17025 (General requirements for the competence of testing and calibration laboratories). PPSS