WorldWideScience

Sample records for active safety systems

  1. Design of an Active Automotive Safety System

    Directory of Open Access Journals (Sweden)

    Y. Wang

    2013-07-01

    Full Text Available With the development of the national economy, the people's standard of living got corresponding improvement, cars has been one of the indispensable traffic tools in many families. An active safety system is proposed, which can real-time detect the vehicle's running status and judge the security status of the vehicle. The system, which takes single-chip microcomputer as the controlling core and combines with millimeter-wave and ultrasonic distance measurement technology, can detect the distance from vehicle to vehicle and judge the security status of the vehicle. The hardware composition of the system and the data acquiring circuit are proposed, the mathematic model for different situation is established, and the controlling algorithm is completed. This system can accurately measure speed and distance between vehicles; the active safety control system can meet the relevant data measurement and transmission requirement; and can meet the functional requirement of the active safety control system

  2. System analysis of vehicle active safety problem

    Science.gov (United States)

    Buznikov, S. E.

    2018-02-01

    The problem of the road transport safety affects the vital interests of the most of the population and is characterized by a global level of significance. The system analysis of problem of creation of competitive active vehicle safety systems is presented as an interrelated complex of tasks of multi-criterion optimization and dynamic stabilization of the state variables of a controlled object. Solving them requires generation of all possible variants of technical solutions within the software and hardware domains and synthesis of the control, which is close to optimum. For implementing the task of the system analysis the Zwicky “morphological box” method is used. Creation of comprehensive active safety systems involves solution of the problem of preventing typical collisions. For solving it, a structured set of collisions is introduced with its elements being generated also using the Zwicky “morphological box” method. The obstacle speed, the longitudinal acceleration of the controlled object and the unpredictable changes in its movement direction due to certain faults, the road surface condition and the control errors are taken as structure variables that characterize the conditions of collisions. The conditions for preventing typical collisions are presented as inequalities for physical variables that define the state vector of the object and its dynamic limits.

  3. Prestandardisation Activities for Computer Based Safety Systems

    DEFF Research Database (Denmark)

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

    1981-01-01

    . 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 and for some...

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

    International Nuclear Information System (INIS)

    2011-01-01

    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.

  5. Evaluating the effectiveness of active vehicle safety systems.

    Science.gov (United States)

    Jeong, Eunbi; Oh, Cheol

    2017-03-01

    Advanced vehicle safety systems have been widely introduced in transportation systems and are expected to enhance traffic safety. However, these technologies mainly focus on assisting individual vehicles that are equipped with them, and less effort has been made to identify the effect of vehicular technologies on the traffic stream. This study proposed a methodology to assess the effectiveness of active vehicle safety systems (AVSSs), which represent a promising technology to prevent traffic crashes and mitigate injury severity. The proposed AVSS consists of longitudinal and lateral vehicle control systems, which corresponds to the Level 2 vehicle automation presented by the National Highway Safety Administration (NHTSA). The effectiveness evaluation for the proposed technology was conducted in terms of crash potential reduction and congestion mitigation. A microscopic traffic simulator, VISSIM, was used to simulate freeway traffic stream and collect vehicle-maneuvering data. In addition, an external application program interface, VISSIM's COM-interface, was used to implement the AVSS. A surrogate safety assessment model (SSAM) was used to derive indirect safety measures to evaluate the effectiveness of the AVSS. A 16.7-km freeway stretch between the Nakdong and Seonsan interchanges on Korean freeway 45 was selected for the simulation experiments to evaluate the effectiveness of AVSS. A total of five simulation runs for each evaluation scenario were conducted. For the non-incident conditions, the rear-end and lane-change conflicts were reduced by 78.8% and 17.3%, respectively, under the level of service (LOS) D traffic conditions. In addition, the average delay was reduced by 55.5%. However, the system's effectiveness was weakened in the LOS A-C categories. Under incident traffic conditions, the number of rear-end conflicts was reduced by approximately 9.7%. Vehicle delays were reduced by approximately 43.9% with 100% of market penetration rate (MPR). These results

  6. Tuning permissiveness of active safety monitors for autonomous systems

    OpenAIRE

    Masson , Lola; Guiochet , Jérémie; Waeselynck , Hélène; Cabrera , Kalou; Cassel , Sofia; Törngren , Martin

    2018-01-01

    International audience; Robots and autonomous systems have become a part of our everyday life, therefore guaranteeing their safety is crucial.Among the possible ways to do so, monitoring is widely used, but few methods exist to systematically generate safety rules to implement such monitors. Particularly, building safety monitors that do not constrain excessively the system's ability to perform its tasks is necessary as those systems operate with few human interventions.We propose in this pap...

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

    International Nuclear Information System (INIS)

    Song, Tae Young

    2007-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2007-07-01

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

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

    Directory of Open Access Journals (Sweden)

    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

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

    International Nuclear Information System (INIS)

    Bermejo, J.M.; Goethem, G. van

    2000-01-01

    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)

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

    CERN Document Server

    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.

  12. Road identification for its-integrated systems of automotive active safety

    Directory of Open Access Journals (Sweden)

    V. Ivanov

    2005-04-01

    Full Text Available The paper discusses several aspects of active safety control for automotive application. Particular emphasis is placed on the fuzzy logic determination of friction properties of a tyre-road contact. An example of vehicle control systems equipped with off-board sensors of road roughness, temperature, moisture and rain intensity demonstrates the implementation of this approach. The paper proposes conceptual solutions for preventive active safety control applied to vehicles which are integrated in an intelligent transportation system.

  13. 78 FR 50079 - Information Collection Activities: Safety and Environmental Management Systems (SEMS); Proposed...

    Science.gov (United States)

    2013-08-16

    ... DEPARTMENT OF THE INTERIOR Bureau of Safety and Environmental Enforcement [Docket ID BSEE-2013-0005; OMB Control Number 1014-0017: 134E1700D2 EEEE500000 ET1SF0000.DAQ000] Information Collection Activities: Safety and Environmental Management Systems (SEMS); Proposed Collection; Comment Request...

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

    International Nuclear Information System (INIS)

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

    2015-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-05-15

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

  16. Application of the Management System for Facilities and Activities. Safety Guide (Spanish Edition)

    International Nuclear Information System (INIS)

    2016-01-01

    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.

  17. Application of the management system for facilities and activities. Safety guide

    International Nuclear Information System (INIS)

    2006-01-01

    This Safety Guide supports the Safety Requirements publication on The Management System for Facilities and Activities. It provides generic guidance to aid in establishing, implementing, assessing and continually improving a management system that complies with the requirements established. In addition to this Safety Guide, there are a number of Safety Guides for specific technical areas. Together these provide all the guidance necessary for implementing these requirements. This publication supersedes Safety Series No. 50-SG-Q1-Q7 (1996). The guidance provided here may be used by organizations in the following ways: - To assist in the development of the management systems of organizations directly responsible for operating facilities and activities and providing services for: Nuclear facilities; Activities using sources of ionizing radiation; Radioactive waste management; The transport of radioactive material; Radiation protection activities; Any other practices or circumstances in which people may be exposed to radiation from naturally occurring or artificial sources; The regulation of such facilities and activities; - To assist in the development of the management systems of the relevant regulatory bodies; - By the operator, to specify to a supplier, via contractual documentation, any guidance of this Safety Guide that should be included in the supplier's management system for the supply and delivery of products

  18. Mathematical modelling of active safety system functions as tools for development of driverless vehicles

    Science.gov (United States)

    Ryazantsev, V.; Mezentsev, N.; Zakharov, A.

    2018-02-01

    This paper is dedicated to a solution of the issue of synthesis of the vehicle longitudinal dynamics control functions (acceleration and deceleration control) based on the element base of the vehicle active safety system (ESP) - driverless vehicle development tool. This strategy helps to reduce time and complexity of integration of autonomous motion control systems (AMCS) into the vehicle architecture and allows direct control of actuators ensuring the longitudinal dynamics control, as well as reduction of time for calibration works. The “vehicle+wheel+road” longitudinal dynamics control is complicated due to the absence of the required prior information about the control object. Therefore, the control loop becomes an adaptive system, i.e. a self-adjusting monitoring system. Another difficulty is the driver’s perception of the longitudinal dynamics control process in terms of comfort. Traditionally, one doesn’t pay a lot of attention to this issue within active safety systems, and retention of vehicle steerability, controllability and stability in emergency situations are considered to be the quality criteria. This is mainly connected to its operational limits, since it is activated only in critical situations. However, implementation of the longitudinal dynamics control in the AMCS poses another challenge for the developers - providing the driver with comfortable vehicle movement during acceleration and deceleration - while the possible highest safety level in terms of the road grip is provided by the active safety system (ESP). The results of this research are: universal active safety system - AMCS interaction interface; block diagram for the vehicle longitudinal acceleration and deceleration control as one of the active safety system’s integrated functions; ideology of adaptive longitudinal dynamics control, which enables to realize the deceleration and acceleration requested by the AMCS; algorithms synthesised; analytical experiments proving the

  19. Two types of a passive safety containment for a near future BWR with active and passive safety systems

    International Nuclear Information System (INIS)

    Sato, Takashi; Akinaga, Makoto; Kojima, Yoshihiro

    2009-01-01

    The paper presents two types of a passive safety containment for a near future BWR. They are named Mark S and Mark X containment. One of their common merits is very low peak pressure at severe accidents without venting the containment atmosphere to the environment. The PCV pressure can be moderated within the design pressure. Another merit is the capability to submerge the PCV and the RPV above the core level. The third merit is robustness against external events such as a large commercial airplane crash. Both the containments have a passive cooling core catcher that has radial cooling channels. The Mark S containment is made of reinforced concrete and applicable to a large power BWR up to 1830 MWe. The Mark X containment has the steel secondary containment and can be cooled by natural circulation of outside air. It can accommodate a medium power BWR up to 1380 MWe. In both cases the plants have active and passive safety systems constituting in-depth hybrid safety (IDHS). The IDHS provides not only hardware diversity between active and passive safety systems but also more importantly diversity of the ultimate heat sinks between the atmosphere and the sea water. Although the plant concept discussed in the paper uses well-established technology, plant performance including economy is innovatively and evolutionally improved. Nothing is new in the hardware but everything is new in the performance.

  20. Two types of a passive safety containment for a near future BWR with active and passive safety systems

    Energy Technology Data Exchange (ETDEWEB)

    Sato, Takashi [Toshiba Corporation, IEC, Gen-SS, 8, Shinsugita-ho, Isogo-ku, Yokohama (Japan)], E-mail: takashi44.sato@glb.toshiba.co.jp; Akinaga, Makoto; Kojima, Yoshihiro [Toshiba Corporation, IEC, Gen-SS, 8, Shinsugita-ho, Isogo-ku, Yokohama (Japan)

    2009-09-15

    The paper presents two types of a passive safety containment for a near future BWR. They are named Mark S and Mark X containment. One of their common merits is very low peak pressure at severe accidents without venting the containment atmosphere to the environment. The PCV pressure can be moderated within the design pressure. Another merit is the capability to submerge the PCV and the RPV above the core level. The third merit is robustness against external events such as a large commercial airplane crash. Both the containments have a passive cooling core catcher that has radial cooling channels. The Mark S containment is made of reinforced concrete and applicable to a large power BWR up to 1830 MWe. The Mark X containment has the steel secondary containment and can be cooled by natural circulation of outside air. It can accommodate a medium power BWR up to 1380 MWe. In both cases the plants have active and passive safety systems constituting in-depth hybrid safety (IDHS). The IDHS provides not only hardware diversity between active and passive safety systems but also more importantly diversity of the ultimate heat sinks between the atmosphere and the sea water. Although the plant concept discussed in the paper uses well-established technology, plant performance including economy is innovatively and evolutionally improved. Nothing is new in the hardware but everything is new in the performance.

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

    International Nuclear Information System (INIS)

    2009-01-01

    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.

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

    International Nuclear Information System (INIS)

    Frutuoso e Melo, P.F.F.

    1981-01-01

    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) [pt

  3. Safety Systems

    Science.gov (United States)

    Halligan, Tom

    2009-01-01

    Colleges across the country are rising to the task by implementing safety programs, response strategies, and technologies intended to create a secure environment for teachers and students. Whether it is preparing and responding to a natural disaster, health emergency, or act of violence, more schools are making campus safety a top priority. At…

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

    NARCIS (Netherlands)

    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

  5. Benchmarking Promotion and Deployment Activities Regarding Intelligent Vehicle Safety Systems in the European Union

    NARCIS (Netherlands)

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

    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

  6. Comprehensive target populations for current active safety systems using national crash databases.

    Science.gov (United States)

    Kusano, Kristofer D; Gabler, Hampton C

    2014-01-01

    The objective of active safety systems is to prevent or mitigate collisions. A critical component in the design of active safety systems is the identification of the target population for a proposed system. The target population for an active safety system is that set of crashes that a proposed system could prevent or mitigate. Target crashes have scenarios in which the sensors and algorithms would likely activate. For example, the rear-end crash scenario, where the front of one vehicle contacts another vehicle traveling in the same direction and in the same lane as the striking vehicle, is one scenario for which forward collision warning (FCW) would be most effective in mitigating or preventing. This article presents a novel set of precrash scenarios based on coded variables from NHTSA's nationally representative crash databases in the United States. Using 4 databases (National Automotive Sampling System-General Estimates System [NASS-GES], NASS Crashworthiness Data System [NASS-CDS], Fatality Analysis Reporting System [FARS], and National Motor Vehicle Crash Causation Survey [NMVCCS]) the scenarios developed in this study can be used to quantify the number of police-reported crashes, seriously injured occupants, and fatalities that are applicable to proposed active safety systems. In this article, we use the precrash scenarios to identify the target populations for FCW, pedestrian crash avoidance systems (PCAS), lane departure warning (LDW), and vehicle-to-vehicle (V2V) or vehicle-to-infrastructure (V2I) systems. Crash scenarios were derived using precrash variables (critical event, accident type, precrash movement) present in all 4 data sources. This study found that these active safety systems could potentially mitigate approximately 1 in 5 of all severity and serious injury crashes in the United States and 26 percent of fatal crashes. Annually, this corresponds to 1.2 million all severity, 14,353 serious injury (MAIS 3+), and 7412 fatal crashes. In addition

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

    Science.gov (United States)

    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.

  8. Safety Culture Activities of HANARO in 2007

    Energy Technology Data Exchange (ETDEWEB)

    Wu, Jong Sup [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2008-05-15

    One of the important aims of a management system for nuclear facilities is to foster a strong safety culture. The safety culture activities in HANARO have been continuously conducted to enhance its safe operation. The following activities and events on a safety culture were performed last year; - Seminars and lectures on safety for the 'Nuclear Safety Check Day' every month - Development of safety culture indicators - Development of operational SPIs (Safety Performance Indicators) - Preparation of an e-Learning program for safety education. In this paper, the safety culture activities in HANARO of KAERI are described, and the efforts necessary for a safety improvement are presented.

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

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jaekwan; Suh, Yongsuk [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-02-15

    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.

  10. An overview of process instrumentation, protective safety interlocks and alarm system at the JET facilities active gas handling system

    International Nuclear Information System (INIS)

    Skinner, N.; Brennan, P.; Brown, K.; Gibbons, C.; Jones, G.; Knipe, S.; Manning, C.; Perevezentsev, A.; Stagg, R.; Thomas, R.; Yorkshades, J.

    2003-01-01

    The Joint European Torus (JET) Facilities Active Gas Handling System (AGHS) comprises ten interconnected processing sub-systems that supply, process and recover tritium from gases used in the JET Machine. Operations require a diverse range of process instrumentation to carry out a multiplicity of monitoring and control tasks and approximately 500 process variables are measured. The different types and application of process instruments are presented with specially adapted or custom-built versions highlighted. Forming part of the Safety Case for tritium operations, a dedicated hardwired interlock and alarm system provides an essential safety function. In the event of failure modes, each hardwired interlock will back-up software interlocks and shutdown areas of plant to a failsafe condition. Design of the interlock and alarm system is outlined and general methodology described. Practical experience gained during plant operations is summarised and the methods employed for routine functional testing of essential instrument systems explained

  11. System safety education focused on flight safety

    Science.gov (United States)

    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.

  12. Optimisation of active suspension control inputs for improved performance of active safety systems

    Science.gov (United States)

    Čorić, Mirko; Deur, Joško; Xu, Li; Tseng, H. Eric; Hrovat, Davor

    2018-01-01

    A collocation-type control variable optimisation method is used to investigate the extent to which the fully active suspension (FAS) can be applied to improve the vehicle electronic stability control (ESC) performance and reduce the braking distance. First, the optimisation approach is applied to the scenario of vehicle stabilisation during the sine-with-dwell manoeuvre. The results are used to provide insights into different FAS control mechanisms for vehicle performance improvements related to responsiveness and yaw rate error reduction indices. The FAS control performance is compared to performances of the standard ESC system, optimal active brake system and combined FAS and ESC configuration. Second, the optimisation approach is employed to the task of FAS-based braking distance reduction for straight-line vehicle motion. Here, the scenarios of uniform and longitudinally or laterally non-uniform tyre-road friction coefficient are considered. The influences of limited anti-lock braking system (ABS) actuator bandwidth and limit-cycle ABS behaviour are also analysed. The optimisation results indicate that the FAS can provide competitive stabilisation performance and improved agility when compared to the ESC system, and that it can reduce the braking distance by up to 5% for distinctively non-uniform friction conditions.

  13. Reactor system safety assurance

    International Nuclear Information System (INIS)

    Mattson, R.J.

    1984-01-01

    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

  14. Systematic assessment of core assurance activities in a company specific food safety management system

    NARCIS (Netherlands)

    Luning, P.A.; Marcelis, W.J.; Rovira, J.; Spiegel, van der M.; Uyttendaele, M.; Jacxsens, L.

    2009-01-01

    The dynamic environment wherein agri-food companies operate and the high requirements on food safety force companies to critically judge and improve their food safety management system (FSMS) and its performance. The objective of this study was to develop a diagnostic instrument enabling a

  15. Development of a web based monitoring system for safety and activity analysis in operating theatres.

    Science.gov (United States)

    Frosini, Francesco; Miniati, Roberto; Avezzano, Paolo; Cecconi, Giulio; Dori, Fabrizio; Gentili, Guido Biffi; Belardinelli, Andrea

    2016-01-01

    The management and the monitoring of the operating rooms on the part of the general management have the objective of optimizing their use and maximizing the internal safety. The expenses owed to their safe use represent, besides reimbursements coming from the surgical activity, important factors for the analysis of the medical facility. Given that it is not possible to reduce the safety, it is necessary to develop supporting systems with the aim to enhance and optimize the use of the rooms. The developed analysis model of the operating rooms in this study is based on the specific performance indicators and allows the effective monitoring of both the parameters that influence the safety (environmental, microbiological parameters) and those that influence the efficiency of the usage (employment rate, delays, necessary formalities, etc.). This allows you to have a systematic dashboard on hand for all of the OTs and, thus, organize the intervention schedules and more appropriate improvements. A monitoring dashboard has been achieved, accessible from any platform and any device, capable of aggregating hospital information. The undertaken organizational modifications, through the use of the dashboard, have allowed for an average annual savings of 29.52 minutes per intervention and increase the use of the ORs of 5%. The increment of the employment rate and the optimization of the operating room have allowed for savings of around $299,88 for every intervention carried out in 2013, corresponding to an annual savings of $343,362,60. Integration dashboards, as the one proposed in this study as a prototype, represent a governance model of economically sustainable healthcare systems capable of guiding the hospital management in the choices and in the implementation of the most efficient organizational modifications.

  16. Issues and challenges for pedestrian active safety systems based on real world accidents.

    Science.gov (United States)

    Hamdane, Hédi; Serre, Thierry; Masson, Catherine; Anderson, Robert

    2015-09-01

    The purpose of this study was to analyze real crashes involving pedestrians in order to evaluate the potential effectiveness of autonomous emergency braking systems (AEB) in pedestrian protection. A sample of 100 real accident cases were reconstructed providing a comprehensive set of data describing the interaction between the vehicle, the environment and the pedestrian all along the scenario of the accident. A generic AEB system based on a camera sensor for pedestrian detection was modeled in order to identify the functionality of its different attributes in the timeline of each crash scenario. These attributes were assessed to determine their impact on pedestrian safety. The influence of the detection and the activation of the AEB system were explored by varying the field of view (FOV) of the sensor and the level of deceleration. A FOV of 35° was estimated to be required to detect and react to the majority of crash scenarios. For the reaction of a system (from hazard detection to triggering the brakes), between 0.5 and 1s appears necessary. Copyright © 2015 Elsevier Ltd. All rights reserved.

  17. Safety system function trends

    International Nuclear Information System (INIS)

    Johnson, C.

    1989-01-01

    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

  18. Pharmacological activities, mechanisms of action, and safety of salidroside in the central nervous system

    Directory of Open Access Journals (Sweden)

    Zhong ZF

    2018-05-01

    Full Text Available Zhifeng Zhong,1 Jing Han,1 Jizhou Zhang,1 Qing Xiao,1 Juan Hu,1,2 Lidian Chen1,2 1Institute of Materia Medica, Fujian Academy of Traditional Chinese Medicine, Fuzhou, Fujian, People’s Republic of China; 2School of Rehabilitation Medicine, Fujian University of Traditional Chinese Medicine, Fuzhou, Fujian, People’s Republic of China Abstract: The primary objective of this review article was to summarize comprehensive information related to the neuropharmacological activity, mechanisms of action, toxicity, and safety of salidroside in medicine. A number of studies have revealed that salidroside exhibits neuroprotective activities, including anti-Alzheimer’s disease, anti-Parkinson’s disease, anti-Huntington’s disease, anti-stroke, anti-depressive effects, and anti-traumatic brain injury; it is also useful for improving cognitive function, treating addiction, and preventing epilepsy. The mechanisms underlying the potential protective effects of salidroside involvement are the regulation of oxidative stress response, inflammation, apoptosis, hypothalamus-pituitary-adrenal axis, neurotransmission, neural regeneration, and the cholinergic system. Being free of side effects makes salidroside potentially attractive as a candidate drug for the treatment of neurological disorders. It is evident from the available published literature that salidroside has potential use as a beneficial therapeutic medicine with high efficacy and low toxicity to the central nervous system. However, the definite target protein molecules remain unclear, and clinical trials regarding this are currently insufficient; thus, guidance for further research on the molecular mechanisms and clinical applications of salidroside is urgent. Keywords: salidroside, Alzheimer’s disease, Parkinson’s disease, stroke, cognitive impairment, clinical trials

  19. Safety system status monitoring

    International Nuclear Information System (INIS)

    Lewis, J.R.; Morgenstern, M.H.; Rideout, T.H.; Cowley, P.J.

    1984-03-01

    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

  20. Safety system status monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Lewis, J.R.; Morgenstern, M.H.; Rideout, T.H.; Cowley, P.J.

    1984-03-01

    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.

  1. Reactor safety systems

    International Nuclear Information System (INIS)

    Kafka, P.

    1975-01-01

    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.) [de

  2. Planned activities to improve safety

    International Nuclear Information System (INIS)

    1998-01-01

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

  3. Software system safety

    Science.gov (United States)

    Uber, James G.

    1988-01-01

    Software itself is not hazardous, but since software and hardware share common interfaces there is an opportunity for software to create hazards. Further, these software systems are complex, and proven methods for the design, analysis, and measurement of software safety are not yet available. Some past software failures, future NASA software trends, software engineering methods, and tools and techniques for various software safety analyses are reviewed. Recommendations to NASA are made based on this review.

  4. IAEA Safety Standards on Management Systems and Safety Culture

    International Nuclear Information System (INIS)

    Persson, Kerstin Dahlgren

    2007-01-01

    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)

  5. Measuring safety in aviation : empirical results about the relation between safety outcomes and safety management system processes, operational activities and demographic data

    NARCIS (Netherlands)

    Kaspers, Steffen; Karanikas, Nektarios; Piric, Selma; van Aalst, Robbert; de Boer, Robert Jan; Roelen, Alfred

    2017-01-01

    A literature review conducted as part of a research project named “Measuring Safety in Aviation – Developing Metrics for Safety Management Systems” revealed several challenges regarding the safety metrics used in aviation. One of the conclusions was that there is limited empirical evidence about the

  6. Reactor Safety Assessment System

    International Nuclear Information System (INIS)

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

    1987-01-01

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

  7. Reactor safety assessment system

    International Nuclear Information System (INIS)

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

    1987-01-01

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

  8. Safety Information System Guide

    International Nuclear Information System (INIS)

    Bullock, M.G.

    1977-03-01

    This Guide provides guidelines for the design and evaluation of a working safety information system. For the relatively few safety professionals who have already adopted computer-based programs, this Guide may aid them in the evaluation of their present system. To those who intend to develop an information system, it will, hopefully, inspire new thinking and encourage steps towards systems safety management. For the line manager who is working where the action is, this Guide may provide insight on the importance of accident facts as a tool for moving ideas up the communication ladder where they will be heard and acted upon; where what he has to say will influence beneficial changes among those who plan and control his operations. In the design of a safety information system, it is suggested that the safety manager make friends with a computer expert or someone on the management team who has some feeling for, and understanding of, the art of information storage and retrieval as a new and better means for communication

  9. Programmable electronic safety systems

    International Nuclear Information System (INIS)

    Parry, R.R.

    1993-01-01

    Traditionally safety systems intended for protecting personnel from electrical and radiation hazards at particle accelerator laboratories have made extensive use of electromechanical relays. These systems have the advantage of high reliability and allow the designer to easily implement fail-safe circuits. Relay based systems are also typically simple to design, implement, and test. As systems, such as those presently under development at the Superconducting Super Collider Laboratory (SSCL), increase in size, and the number of monitored points escalates, relay based systems become cumbersome and inadequate. The move toward Programmable Electronic Safety Systems is becoming more widespread and accepted. In developing these systems there are numerous precautions the designer must be concerned with. Designing fail-safe electronic systems with predictable failure states is difficult at best. Redundancy and self-testing are prime examples of features that should be implemented to circumvent and/or detect failures. Programmable systems also require software which is yet another point of failure and a matter of great concern. Therefore the designer must be concerned with both hardware and software failures and build in the means to assure safe operation or shutdown during failures. This paper describes features that should be considered in developing safety systems and describes a system recently installed at the Accelerator Systems String Test (ASST) facility of the SSCL

  10. Programmable Electronic Safety Systems

    International Nuclear Information System (INIS)

    Parry, R.

    1993-05-01

    Traditionally safety systems intended for protecting personnel from electrical and radiation hazards at particle accelerator laboratories have made extensive use of electromechanical relays. These systems have the advantage of high reliability and allow the designer to easily implement failsafe circuits. Relay based systems are also typically simple to design, implement, and test. As systems, such as those presently under development at the Superconducting Super Collider Laboratory (SSCL), increase in size, and the number of monitored points escalates, relay based systems become cumbersome and inadequate. The move toward Programmable Electronic Safety Systems is becoming more widespread and accepted. In developing these systems there are numerous precautions the designer must be concerned with. Designing fail-safe electronic systems with predictable failure states is difficult at best. Redundancy and self-testing are prime examples of features that should be implemented to circumvent and/or detect failures. Programmable systems also require software which is yet another point of failure and a matter of great concern. Therefore the designer must be concerned with both hardware and software failures and build in the means to assure safe operation or shutdown during failures. This paper describes features that should be considered in developing safety systems and describes a system recently installed at the Accelerator Systems String Test (ASST) facility of the SSCL

  11. EDA activities related to safety

    International Nuclear Information System (INIS)

    Gordon, C.; Raeder, J.

    2001-01-01

    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

  12. Systems Safety and Engineering Division

    Data.gov (United States)

    Federal Laboratory Consortium — Volpe's Systems Safety and Engineering Division conducts engineering, research, and analysis to improve transportation safety, capacity, and resiliency. We provide...

  13. Safety culture activities in HANARO

    International Nuclear Information System (INIS)

    Lim, I. C.; Park, C.; Hwang, S. R.; Choi, H. Y.; Jeon, B. J.

    2002-01-01

    The yearly operation time and the number of users in HANARO are increasing since its initial criticality has been achieved in 1995. This achievement is partly in debt to the spread of safety culture to operators and reactor users. In this paper, the activities done by the reactor operation organization on safety culture are described, and their further efforts identified to be necessary for the improvement and dissemination of safety culture and are presented

  14. Safety of huge systems

    International Nuclear Information System (INIS)

    Kondo, Jiro.

    1995-01-01

    Recently accompanying the development of engineering technology, huge systems tend to be constructed. The disaster countermeasures of huge cities become large problems as the concentration of population into cities is conspicuous. To make the expected value of loss small, the knowledge of reliability engineering is applied. In reliability engineering, even if a part of structures fails, the safety as a whole system must be ensured, therefore, the design having margin is carried out. The degree of margin is called redundancy. However, such design concept makes the structure of a system complex, and as the structure is complex, the possibility of causing human errors becomes high. At the time of huge system design, the concept of fail-safe is effective, but simple design must be kept in mind. The accident in Mihama No. 2 plant of Kansai Electric Power Co. and the accident in Chernobyl nuclear power station, and the accident of Boeing B737 airliner and the fatigue breakdown are described. The importance of safety culture was emphasized as the method of preventing human errors. Man-system interface and management system are discussed. (K.I.)

  15. Nuclear reactor safety system

    International Nuclear Information System (INIS)

    Ball, R.M.; Roberts, R.C.

    1983-01-01

    The invention provides a safety system for a nuclear reactor which uses a parallel combination of computer type look-up tables each of which receives data on a particular parameter (from transducers located in the reactor system) and each of which produces the functional counterpart of that particular parameter. The various functional counterparts are then added together to form a control signal for shutting down the reactor. The functional counterparts are developed by analysis of experimental thermal and hydraulic data, which are used to form expressions that define safe conditions

  16. Nuclear reactor safety systems

    International Nuclear Information System (INIS)

    Ball, R.M.; Roberts, R.C.

    1980-01-01

    A safety system for shutting down a nuclear reactor under overload conditions is described. The system includes a series of parallel-connected computer memory type look-up tables each of which receives data on a particular reactor parameter and in each of which a precalculated functional value for that parameter is stored indicative of the percentage of maximum reactor load that the parameter contributes. The various functional values corresponding to the actual measured parameters are added together to provide a control signal used to shut down the reactor under overload conditions. (U.K.)

  17. Safety implications of control systems

    International Nuclear Information System (INIS)

    Smith, O.L.

    1983-01-01

    The Safety Implications of Control Systems Program has three major activities in support of USI-A47. The first task is a failure mode and effects analysis of all plant systems which may potentially induce control system disturbance that have safety implications. This task has made a preliminary study of overfill events and recommended cases for further analysis on the hybrid simulator. Work continues on overcooling and undercooling. A detailed investigation of electric power network is in progress. LERs are providing guidance on important failure modes that will provide initial conditions for further simulator studies. The simulator taks is generating a detailed model of the control system supported by appropriate neutronics, hydraulics, and thermodynamics submodels of all other principal plant components. The simulator is in the last stages of development. Checkout calculations are in progress to establish model stability, robustness, and qualitative credibility. Verification against benchmark codes and plant data will follow

  18. Safety assessment for Generation IV nuclear systems

    International Nuclear Information System (INIS)

    Leahy, T.J.

    2012-01-01

    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. Recent RSWG work has focused on the definition of an integrated safety assessment methodology (ISAM) for evaluating the safety of Generation IV systems. ISAM is an integrated 'tool-kit' consisting of 5 analytical techniques that are available and matched to appropriate stages of Generation IV system concept development: 1) qualitative safety features review - QSR, 2) phenomena identification and ranking table - PIRT, 3) objective provision tree - OPT, 4) deterministic and phenomenological analyses - DPA, and 5) probabilistic safety analysis - PSA. 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

  19. Safety activities in small businesses

    Science.gov (United States)

    Sinclair, Raymond C.; Cunningham, Thomas R.

    2015-01-01

    Background Workplace injuries occur at higher rates in smaller firms than in larger firms, and the number of workplace safety activities appear to be inversely associated with those rates. Predictors of safety activities are rarely studied. Methods This study uses data from a national random survey of firms (n = 722) with less than 250 employees conducted in 2002. Results We found that, regardless of firm size or industry, safety activities were more common in 2002 than they were in a similar 1983 study. Having had an OSHA inspection in the last five years and firm size were stronger predictors of safety activities than industry hazardousness and manager’s perceptions of hazardousness. All four variables were significant predictors (β range .19 to .28; R2 = .27). Conclusions Further progress in the prevention of injuries in small firms will require attention to factors likely subsumed within the firm size variable, especially the relative lack of slack resources that might be devoted to safety activities. PMID:26339124

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

    International Nuclear Information System (INIS)

    Beitel, G.A.; Morcos, N.

    1993-01-01

    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

  1. Safety significance evaluation system

    International Nuclear Information System (INIS)

    Lew, B.S.; Yee, D.; Brewer, W.K.; Quattro, P.J.; Kirby, K.D.

    1991-01-01

    This paper reports that the Pacific Gas and Electric Company (PG and E), in cooperation with ABZ, Incorporated and Science Applications International Corporation (SAIC), investigated the use of artificial intelligence-based programming techniques to assist utility personnel in regulatory compliance problems. The result of this investigation is that artificial intelligence-based programming techniques can successfully be applied to this problem. To demonstrate this, a general methodology was developed and several prototype systems based on this methodology were developed. The prototypes address U.S. Nuclear Regulatory Commission (NRC) event reportability requirements, technical specification compliance based on plant equipment status, and quality assurance assistance. This collection of prototype modules is named the safety significance evaluation system

  2. Evaluating safety management system implementation

    International Nuclear Information System (INIS)

    Preuss, M.

    2009-01-01

    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)

  3. The aviation safety reporting system

    Science.gov (United States)

    Reynard, W. D.

    1984-01-01

    The aviation safety reporting system, an accident reporting system, is presented. The system identifies deficiencies and discrepancies and the data it provides are used for long term identification of problems. Data for planning and policy making are provided. The system offers training in safety education to pilots. Data and information are drawn from the available data bases.

  4. Software Quality Assurance for Nuclear Safety Systems

    International Nuclear Information System (INIS)

    Sparkman, D R; Lagdon, R

    2004-01-01

    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: (sm b ullet) Ensures the software processes developed to address nuclear safety in design, operation, construction and maintenance of its facilities are safe (sm b ullet) Considers the larger system that uses the software and its impacts (sm b ullet) 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

  5. Operation safety of complex industrial systems

    International Nuclear Information System (INIS)

    Zwingelstein, G.

    1999-01-01

    Zero fault or zero risk is an unreachable goal in industrial activities like nuclear activities. However, methods and techniques exist to reduce the risks to the lowest possible and acceptable level. The operation safety consists in the recognition, evaluation, prediction, measurement and mastery of technological and human faults. This paper analyses each of these points successively: 1 - evolution of operation safety; 2 - definitions and basic concepts: failure, missions and functions of a system and of its components, basic concepts and operation safety; 3 - forecasting analysis of operation safety: reliability data, data-banks, precautions for the use of experience feedback data; realization of an operation safety study: management of operation safety, quality assurance, critical review and audit of operation safety studies; 6 - conclusions. (J.S.)

  6. Safety logic systems of PFBR

    International Nuclear Information System (INIS)

    Sambasivan, S. Ilango

    2004-01-01

    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

  7. Technical foundations for quality assurance of systems engineering activities for safety assessment

    International Nuclear Information System (INIS)

    Oren, T.I.; Elzas, M.S.

    1987-01-01

    Basic system design axioms and a framework for design and test derivation based on structural design are presented. Over thirty quality assurance issues are elaborated on. New dimensions to quality assurance issues in the artificial intelligence era are discussed. The last part of the article is a sequel of another one titled: ''Mode reliability and software quality assurance in simulation of nuclear fuel waste management systems'' which was published in the Proceedings of the 1985 Waste Management Conference

  8. Aviation Safety Hotline Information System -

    Data.gov (United States)

    Department of Transportation — The Aviation Safety Hotline Information System (ASHIS) collects, stores, and retrieves reports submitted by pilots, mechanics, cabin crew, passengers, or the public...

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

    Science.gov (United States)

    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?

  10. 76 FR 67201 - Information Collection Activities: Oil and Gas Production Safety Systems; Submitted for Office of...

    Science.gov (United States)

    2011-10-31

    ... a total of 62,963 hours. The following chart details the individual components and estimated hour... District Manager approval.. 803(b)(8)(iv); (v) Post diagram of firefighting system; 5 38 190 furnish..., removal, etc; make records available to BSEE. 803(b)(1)(iii), (b)(2)(i) Maintain pressure-recorder charts...

  11. 75 FR 53733 - Pipeline Safety: Information Collection Activities

    Science.gov (United States)

    2010-09-01

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No. PHMSA-2010-0246] Pipeline Safety: Information Collection Activities AGENCY: Pipeline and Hazardous... liquefied natural gas, hazardous liquid, and gas transmission pipeline systems operated by a company. The...

  12. Experimental activities related to safety systems of PWR NPPs (900 MWe). Sump screen plugging issue

    International Nuclear Information System (INIS)

    Vicena, I.; Soltesz, B.; Batalik, J.; Gubco, V.; Liska, M.; Galusekova, D.; Klementova, A.; Mattei, J. M.; Armand, Y.

    2006-01-01

    In this presentation authors present the sump plugging issue - ability of the filtration systems to catch debris (generated during the LOCA accident) to maintain the recirculating water the CSS and the ECCS need. Assessment has been focused upon the CPY series 900 MW e (28 reactors). Typical involved debris is: - the insulation for all the plants is made of glass wool (45 kg/m 3 ). Glass-wool is contained in sheet metal panels using attachment mechanism; - paints; - concrete; -dust. Effect of water chemistry on debris and filtration process ELISA loop is described.

  13. The Evolution of System Safety at NASA

    Science.gov (United States)

    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.

  14. System safety engineering analysis handbook

    Science.gov (United States)

    Ijams, T. E.

    1972-01-01

    The basic requirements and guidelines for the preparation of System Safety Engineering Analysis are presented. The philosophy of System Safety and the various analytic methods available to the engineering profession are discussed. A text-book description of each of the methods is included.

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

    International Nuclear Information System (INIS)

    Mrabit, Khammar; Sadagopan; Geetha

    2003-01-01

    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)

  16. Safety balance: Analysis of safety systems

    International Nuclear Information System (INIS)

    Delage, M.; Giroux, C.

    1990-12-01

    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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1991-07-01

    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.

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

    International Nuclear Information System (INIS)

    1991-01-01

    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

  19. System safety education focused on system management

    Science.gov (United States)

    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. Development of a check sheet for collecting information necessary for occupational safety and health activities and building relevant systems in overseas business places.

    Science.gov (United States)

    Kajiki, Shigeyuki; Kobayashi, Yuichi; Uehara, Masamichi; Nakanishi, Shigemoto; Mori, Koji

    2016-06-07

    This study aimed to develop an information gathering check sheet to efficiently collect information necessary for Japanese companies to build global occupational safety and health management systems in overseas business places. The study group consisted of 2 researchers with occupational physician careers in a foreign-affiliated company in Japan and 3 supervising occupational physicians who were engaged in occupational safety and health activities in overseas business places. After investigating information and sources of information necessary for implementing occupational safety and health activities and building relevant systems, we conducted information acquisition using an information gathering check sheet in the field, by visiting 10 regions in 5 countries (first phase). The accuracy of the information acquired and the appropriateness of the information sources were then verified in study group meetings to improve the information gathering check sheet. Next, the improved information gathering check sheet was used in another setting (3 regions in 1 country) to confirm its efficacy (second phase), and the information gathering check sheet was thereby completed. The information gathering check sheet was composed of 9 major items (basic information on the local business place, safety and health overview, safety and health systems, safety and health staff, planning/implementation/evaluation/improvement, safety and health activities, laws and administrative organs, local medical care systems and public health, and medical support for resident personnel) and 61 medium items. We relied on the following eight information sources: the internet, company (local business place and head office in Japan), embassy/consulate, ISO certification body, university or other educational institutions, and medical institutions (aimed at Japanese people or at local workers). Through multiple study group meetings and a two-phased field survey (13 regions in 6 countries), an information

  1. Systemic study on the safety of immuno-deficient nude mice treated by atmospheric plasma-activated water

    Science.gov (United States)

    Dehui, XU; Qingjie, CUI; Yujing, XU; Bingchuan, WANG; Miao, TIAN; Qiaosong, LI; Zhijie, LIU; Dingxin, LIU; Hailan, CHEN; Michael, G. KONG

    2018-04-01

    Cold atmospheric-pressure plasma is a new technology, widely used in many fields of biomedicine, especially in cancer treatment. Cold plasma can selectively kill a variety of tumor cells, and its biological safety in clinical trials is also very important. In many cases, the patient’s immune level is relatively low, so we first studied the safety assessment of plasma treatment in an immuno-compromised animal model. In this study, we examined the safety of immuno-deficient nude mice by oral lavage treatment of plasma-activated water, and studied the growth status, main organs and blood biochemical indexes. Acute toxicity test results showed that the maximum dose of plasma treatment for 15 min had no lethal effect and other acute toxicity. There were no significant changes in body weight and survival status of mice after 2 min and 4 min of plasma-activated water (PAW) treatment for 2 weeks. After treatment, the major organs, including heart, liver, spleen, lung and kidney, were not significantly changed in organ coefficient and tissue structure. Blood biochemical markers showed that blood neutrophils and mononuclear cells were slightly increased, and the others remained unchanged. Liver function, renal function, electrolytes, glucose metabolism and lipid metabolism were not affected by different doses of PAW treatment. The above results indicate that PAW treatment can be used to treat immuno-deficient nude mice without significant safety problems.

  2. Safety Justification and Safety Case for Safety-critical Software in Digital Reactor Protection System

    Energy Technology Data Exchange (ETDEWEB)

    Kwon, Kee-Choon; Lee, Jang-Soo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Jee, Eunkyoung [KAIST, Daejeon (Korea, Republic of)

    2016-10-15

    Nuclear safety-critical software is under strict regulatory requirements and these regulatory requirements are essential for ensuring the safety of nuclear power plants. The verification & validation (V and V) and hazard analysis of the safety-critical software are required to follow regulatory requirements through the entire software life cycle. In order to obtain a license from the regulatory body through the development and validation of safety-critical software, it is essential to meet the standards which are required by the regulatory body throughout the software development process. Generally, large amounts of documents, which demonstrate safety justification including standard compliance, V and V, hazard analysis, and vulnerability assessment activities, are submitted to the regulatory body during the licensing process. It is not easy to accurately read and evaluate the whole documentation for the development activities, implementation technology, and validation activities. The safety case methodology has been kwon a promising approach to evaluate the level and depth of the development and validation results. A safety case is a structured argument, supported by a body of evidence that provides a compelling, comprehensible, and valid case that a system is safe for a given application in a given operating environment. It is suggested to evaluate the level and depth of the results of development and validation by applying safety case methodology to achieve software safety demonstration. A lot of documents provided as evidence are connected to claim that corresponds to the topic for safety demonstration. We demonstrated a case study in which more systematic safety demonstration for the target system software is performed via safety case construction than simply listing the documents.

  3. Safety Justification and Safety Case for Safety-critical Software in Digital Reactor Protection System

    International Nuclear Information System (INIS)

    Kwon, Kee-Choon; Lee, Jang-Soo; Jee, Eunkyoung

    2016-01-01

    Nuclear safety-critical software is under strict regulatory requirements and these regulatory requirements are essential for ensuring the safety of nuclear power plants. The verification & validation (V and V) and hazard analysis of the safety-critical software are required to follow regulatory requirements through the entire software life cycle. In order to obtain a license from the regulatory body through the development and validation of safety-critical software, it is essential to meet the standards which are required by the regulatory body throughout the software development process. Generally, large amounts of documents, which demonstrate safety justification including standard compliance, V and V, hazard analysis, and vulnerability assessment activities, are submitted to the regulatory body during the licensing process. It is not easy to accurately read and evaluate the whole documentation for the development activities, implementation technology, and validation activities. The safety case methodology has been kwon a promising approach to evaluate the level and depth of the development and validation results. A safety case is a structured argument, supported by a body of evidence that provides a compelling, comprehensible, and valid case that a system is safe for a given application in a given operating environment. It is suggested to evaluate the level and depth of the results of development and validation by applying safety case methodology to achieve software safety demonstration. A lot of documents provided as evidence are connected to claim that corresponds to the topic for safety demonstration. We demonstrated a case study in which more systematic safety demonstration for the target system software is performed via safety case construction than simply listing the documents

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

    Science.gov (United States)

    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.

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

    International Nuclear Information System (INIS)

    Marabit, K.; Sadagopan, G.

    2003-01-01

    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

  6. Task force activity to take the effect of elastic-plastic behaviour into account on the seismic safety evaluation of nuclear piping systems

    International Nuclear Information System (INIS)

    Nakamura, Izumi; Shiratori, Masaki; Morishita, Masaki; Otani, Akihito; Shibutani, Tadahito

    2015-01-01

    According to investigations of several nuclear power plants (NPPs) hit by actual seismic events and a number of experimental researches on the failure behavior of piping systems under seismic loads, it is recognized that piping systems used in NPPs include a large seismic safety margin until boundary failure. Since the stress assessment based on the elastic analysis does not reflect actual seismic capability of piping systems including plastic region, it is necessary to develop a rational procedures to estimate the elastic-plastic behavior of piping systems under a large seismic load. With the aim of establishing a procedure that takes into account the elastic-plastic behavior effect in the seismic safety estimation of nuclear piping systems, a task force activity has been planned. Through the activity, the authors intend to establish guidelines to estimate the elastic-plastic behavior of piping systems rationally and conservatively, and to provide new rational seismic safety criteria taking the effect of elastic-plastic behavior into account. As the first step of making out the analysis guideline, benchmark analyses are conducted for a pipe element test and a piping system test. In this paper, the outline of the research activity and the preliminary results of benchmark analyses are described. (author)

  7. Active pedestrian safety by automatic braking and evasive steering

    NARCIS (Netherlands)

    Keller, C.; Dang, T.; Fritz, H.; Joos, A.; Rabe, C.; Gavrila, D.M.

    2011-01-01

    Active safety systems hold great potential for reducing accident frequency and severity by warning the driver and/or exerting automatic vehicle control ahead of crashes. This paper presents a novel active pedestrian safety system that combines sensing, situation analysis, decision making, and

  8. NASA System Safety Handbook. Volume 2: System Safety Concepts, Guidelines, and Implementation Examples

    Science.gov (United States)

    Dezfuli, Homayoon; Benjamin, Allan; Everett, Christopher; Feather, Martin; Rutledge, Peter; Sen, Dev; Youngblood, Robert

    2015-01-01

    This is the second of two volumes that collectively comprise the NASA System Safety Handbook. Volume 1 (NASASP-210-580) was prepared for the purpose of presenting the overall framework for System Safety and for providing the general concepts needed to implement the framework. Volume 2 provides guidance for implementing these concepts as an integral part of systems engineering and risk management. This guidance addresses the following functional areas: 1.The development of objectives that collectively define adequate safety for a system, and the safety requirements derived from these objectives that are levied on the system. 2.The conduct of system safety activities, performed to meet the safety requirements, with specific emphasis on the conduct of integrated safety analysis (ISA) as a fundamental means by which systems engineering and risk management decisions are risk-informed. 3.The development of a risk-informed safety case (RISC) at major milestone reviews to argue that the systems safety objectives are satisfied (and therefore that the system is adequately safe). 4.The evaluation of the RISC (including supporting evidence) using a defined set of evaluation criteria, to assess the veracity of the claims made therein in order to support risk acceptance decisions.

  9. CERN safety system monitoring - SSM

    International Nuclear Information System (INIS)

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

    2012-01-01

    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)

  10. Safety of mechanical devices. Safety of automation systems

    International Nuclear Information System (INIS)

    Pahl, G.; Schweizer, G.; Kapp, K.

    1985-01-01

    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) [de

  11. Nuclear reactor safety system

    International Nuclear Information System (INIS)

    Sato, Takashi.

    1979-01-01

    Purpose: To allow sufficient removal of radioactive substance released in the reactor containment shell upon loss of coolants accidents thus to sufficiently decrease the exposure dose to human body. Constitution: A clean-up system is provided downstream of a heat exchanger and it is branched into a pipeway to be connected to a spray nozzle and further connected by way of a valve to a reactor container. After the end of sudden transient changes upon loss of coolants accidents, the pool water stored in the pressure suppression chamber is purified in the clean-up system and then sprayed in the dry-well by way of a spray nozzle. The sprayed water dissolves to remove water soluble radioactive substances floating in the dry-well and then returns to the pressure suppression chamber. Since radioactive substances in the dry-well can thus removed rapidly and effectively and the pool water can be reused, public hazard can also be decreased. (Horiuchi, T.)

  12. Spent fuel management systems, burnup credit approach experience in expert activity of State Scientific and Technical Centre for Nuclear and Radiation Safety

    International Nuclear Information System (INIS)

    Kovbasenko, Y.

    2010-01-01

    Implementing new devices and mechanisms, including those developed and manufactured abroad, at enterprises of the Ukrainian power industry makes it necessary to license them in advance by the Ukrainian Regulatory Authority. From time to time, situations occur when these systems or their close analogues have been already used in some countries and have successively passed licensing by the relevant Regulatory Authorities; however, they do not meet the regulatory requirements in force in Ukraine. Preliminary analysis of the regulations in Ukraine concerning nuclear safety of spent nuclear fuel (SNF) management systems shows that some regulatory requirements in force are too conservative in view of current international practice. The extent of conservatism can be reduced, if necessary, only on the base of improving our level of understanding the processes occurring in nuclear dangerous systems and improving our capabilities as regards accuracy, correctness, and reliability in numerical modeling these processes. Such activity is consistent with the state-of-the-art production requirements. This work was intended to demonstrate that the excessive conservatism laid previously into the requirements on nuclear safety in Ukraine due to insufficient development of tools for modeling processes in nuclear fuel can be considerably decreased through using more modern and real modeling fuel systems. If such modeling is performed with the use of state-of-the-art methods, based on more complete understanding the processes in fuel systems, then removal of the excessive conservatism will not reduce the safety of nuclear dangerous systems

  13. The LHC personnel safety system

    International Nuclear Information System (INIS)

    Ninin, P.; Valentini, F.; Ladzinski, T.

    2011-01-01

    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)

  14. Safety in nuclear power systems

    International Nuclear Information System (INIS)

    Myers, L.C.

    1987-05-01

    This paper discusses the issue of safety in complex energy systems and provides brief accounts of some of the most serious reactor accidents that have occurred to date. Details are also provided of Ontario Hydro's problems with Unit 2 at Pickering

  15. Firefighter Safety for PV Systems

    DEFF Research Database (Denmark)

    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 switch...

  16. NASA aviation safety reporting system

    Science.gov (United States)

    1981-01-01

    Aviation safety reports that relate to loss of control in flight, problems that occur as a result of similar sounding alphanumerics, and pilot incapacitation are presented. Problems related to the go around maneuver in air carrier operations, and bulletins (and FAA responses to them) that pertain to air traffic control systems and procedures are included.

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

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

    International Nuclear Information System (INIS)

    Lee, Duk Su; Chang, Woo Hyun; Lee, Nam Young; A. C. D. Wright

    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

  19. Regulatory activities in reactor safety

    International Nuclear Information System (INIS)

    Salvatore, J.E.L.

    1987-01-01

    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.) [pt

  20. The Daresbury personnel safety system

    International Nuclear Information System (INIS)

    Poole, D.E.; Ring, T.

    1989-01-01

    The personnel safety system designed for the SRS at Daresbury is a unified system covering the three accelerators of the source itself, the beamlines and the experimental stations. The system has also been applied to the experimental areas of the Nuclear Structure Facility, and is therefore established as a site standard. A dual guardline interlock module forms a building block for a relay based interlock system completely independent of the machine control system, although comprehensive monitoring of the system status via the control system computer is a feature. An outline of the design criteria adopted for the system is presented together with a more detailed description of the philosophy of the guardline logic and the way this is implemented in a standard modular form. The emphasis is on the design features of a modern microprocessor based variant of the original SRS system. Experience with the original system during build-up and operation of the SRS facility is described. 2 refs., 4 figs

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

    International Nuclear Information System (INIS)

    Wetzel, N.; Scharfe, A.

    1998-01-01

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

  2. System safety education focused on industrial engineering

    Science.gov (United States)

    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.

  3. How could intelligent safety transport systems enhance safety ?

    NARCIS (Netherlands)

    Wiethoff, M. Heijer, T. & Bekiaris, E.

    2017-01-01

    In Europe, many deaths and injured each years are the cost of today's road traffic. Therefore, it is wise to look for possible solutions for enhancing traffic safety. Some Advanced Driver Assistance Systems (ADAS) are expected to increase safety, but they may also evoke new safety hazards. Only

  4. Nuclear power systems: Their safety

    International Nuclear Information System (INIS)

    Myers, L.C.

    1993-01-01

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

  5. Radiation safety systems at the NSLS

    International Nuclear Information System (INIS)

    Dickinson, T.

    1987-04-01

    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

  6. Safety assessment of HLW geological disposal system

    International Nuclear Information System (INIS)

    Naito, Morimasa

    2006-01-01

    that Japan is located in a tectonically active zone. Safety assessment for a disposal system differs from that for other engineered systems such as power stations in terms of: Extremely long timescales must be taken into account. Natural environments, which are heterogeneous and cover large spatial areas, must be evaluated. It is thus impossible to apply conventional engineering approaches, where an entire system is constructed and utilized in such a way as to demonstrate system safety. This is a problem specific to the safety assessment of geological disposal. Taking this into account, this paper describes a general methodology of safety assessment for geological system including presentation of a series of steps for the assessment with examples of JNC's H12 safety assessment. (author)

  7. Integrated therapy safety management system.

    Science.gov (United States)

    Podtschaske, Beatrice; Fuchs, Daniela; Friesdorf, Wolfgang

    2013-09-01

    The aim is to demonstrate the benefit of the medico-ergonomic approach for the redesign of clinical work systems. Based on the six layer model, a concept for an 'integrated therapy safety management' is drafted. This concept could serve as a basis to improve resilience. The concept is developed through a concept-based approach. The state of the art of safety and complexity research in human factors and ergonomics forms the basis. The findings are synthesized to a concept for 'integrated therapy safety management'. The concept is applied by way of example for the 'medication process' to demonstrate its practical implementation. The 'integrated therapy safety management' is drafted in accordance with the six layer model. This model supports a detailed description of specific work tasks, the corresponding responsibilities and related workflows at different layers by using the concept of 'bridge managers'. 'Bridge managers' anticipate potential errors and monitor the controlled system continuously. If disruptions or disturbances occur, they respond with corrective actions which ensure that no harm results and they initiate preventive measures for future procedures. The concept demonstrates that in a complex work system, the human factor is the key element and final authority to cope with the residual complexity. The expertise of the 'bridge managers' and the recursive hierarchical structure results in highly adaptive clinical work systems and increases their resilience. The medico-ergonomic approach is a highly promising way of coping with two complexities. It offers a systematic framework for comprehensive analyses of clinical work systems and promotes interdisciplinary collaboration. © 2013 The Authors. British Journal of Clinical Pharmacology © 2013 The British Pharmacological Society.

  8. Integrated therapy safety management system

    Science.gov (United States)

    Podtschaske, Beatrice; Fuchs, Daniela; Friesdorf, Wolfgang

    2013-01-01

    Aims The aim is to demonstrate the benefit of the medico-ergonomic approach for the redesign of clinical work systems. Based on the six layer model, a concept for an ‘integrated therapy safety management’ is drafted. This concept could serve as a basis to improve resilience. Methods The concept is developed through a concept-based approach. The state of the art of safety and complexity research in human factors and ergonomics forms the basis. The findings are synthesized to a concept for ‘integrated therapy safety management’. The concept is applied by way of example for the ‘medication process’ to demonstrate its practical implementation. Results The ‘integrated therapy safety management’ is drafted in accordance with the six layer model. This model supports a detailed description of specific work tasks, the corresponding responsibilities and related workflows at different layers by using the concept of ‘bridge managers’. ‘Bridge managers’ anticipate potential errors and monitor the controlled system continuously. If disruptions or disturbances occur, they respond with corrective actions which ensure that no harm results and they initiate preventive measures for future procedures. The concept demonstrates that in a complex work system, the human factor is the key element and final authority to cope with the residual complexity. The expertise of the ‘bridge managers’ and the recursive hierarchical structure results in highly adaptive clinical work systems and increases their resilience. Conclusions The medico-ergonomic approach is a highly promising way of coping with two complexities. It offers a systematic framework for comprehensive analyses of clinical work systems and promotes interdisciplinary collaboration. PMID:24007448

  9. The ATLAS Detector Safety System

    CERN Multimedia

    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...

  10. Role of computers in CANDU safety systems

    International Nuclear Information System (INIS)

    Hepburn, G.A.; Gilbert, R.S.; Ichiyen, N.M.

    1985-01-01

    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)

  11. Active gated imaging for automotive safety applications

    Science.gov (United States)

    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.

  12. Regulatory Oversight of Safety Culture in Finland: A Systemic Approach to Safety

    International Nuclear Information System (INIS)

    Oedewald, P.; Väisäsvaara, J.

    2016-01-01

    In Finland the Radiation and Nuclear Safety Authority STUK specifies detailed regulatory requirements for good safety culture. Both the requirements and the practical safety culture oversight activities reflect a systemic approach to safety: the interconnections between the technical, human and organizational factors receive special attention. The conference paper aims to show how the oversight of safety culture can be integrated into everyday oversight activities. The paper also emphasises that the scope of the safety culture oversight is not specific safety culture activities of the licencees, but rather the overall functioning of the licence holder or the new build project organization from safety point of view. The regulatory approach towards human and organizational factors and safety culture has evolved throughout the years of nuclear energy production in Finland. Especially the recent new build projects have highlighted the need to systematically pay attention to the non-technical aspects of safety as it has become obvious how the HOF issues can affect the design processes and quality of construction work. Current regulatory guides include a set of safety culture related requirements. The requirements are binding to the licence holders and they set both generic and specific demands on the licencee to understand, monitor and to develop safety culture of their own organization but also that of their supplier network. The requirements set for the licence holders has facilitated the need to develop the regulator’s safety culture oversight practices towards a proactive and systemic approach.

  13. Recent Activities on Global Nuclear Safety Regime

    International Nuclear Information System (INIS)

    Cho, Kun-Woo; Park, Jeong-Seop; Kim, Do-Hyoung

    2006-01-01

    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

  14. Regulatory Activities for Licensee's Safety Culture

    International Nuclear Information System (INIS)

    Choi, Young Sung; Choi, Kwang Sik

    2008-01-01

    Weaknesses in safety culture have contributed to a number of incidents/accidents in the nuclear and other high hazard sectors worldwide in the past. These events have fostered an increasing awareness of the need for licensees to develop a strong safety culture to support successful and sustainable nuclear safety performance. Regulatory bodies are taking a growing interest in this issue, and several are actively working to develop and implement approaches to maintaining regulatory oversight of licensee safety culture. However, these approaches are not yet well-established, and it was considered prudent to share experiences and developing methodologies in order to disseminate good practices and avoid potential pitfalls. This paper presents the findings, conclusions and recommendations of international meetings and other countries' activities on safety culture and gives some suggestions for regulators to consider when planning regulatory oversight for licensee's safety culture

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

    International Nuclear Information System (INIS)

    Leahy, Timothy J.

    2010-01-01

    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.

  16. Safety performance monitoring of autonomous marine systems

    International Nuclear Information System (INIS)

    Thieme, Christoph A.; Utne, Ingrid B.

    2017-01-01

    The marine environment is vast, harsh, and challenging. Unanticipated faults and events might lead to loss of vessels, transported goods, collected scientific data, and business reputation. Hence, systems have to be in place that monitor the safety performance of operation and indicate if it drifts into an intolerable safety level. This article proposes a process for developing safety indicators for the operation of autonomous marine systems (AMS). The condition of safety barriers and resilience engineering form the basis for the development of safety indicators, synthesizing and further adjusting the dual assurance and the resilience based early warning indicator (REWI) approaches. The article locates the process for developing safety indicators in the system life cycle emphasizing a timely implementation of the safety indicators. The resulting safety indicators reflect safety in AMS operation and can assist in planning of operations, in daily operational decision-making, and identification of improvements. Operation of an autonomous underwater vehicle (AUV) exemplifies the process for developing safety indicators and their implementation. The case study shows that the proposed process leads to a comprehensive set of safety indicators. It is expected that application of the resulting safety indicators consequently will contribute to safer operation of current and future AMS. - Highlights: • Process for developing safety indicators for autonomous marine systems. • Safety indicators based on safety barriers and resilience thinking. • Location of the development process in the system lifecycle. • Case study on AUV demonstrating applicability of the process.

  17. Compartmentalized safety coolant injection system

    International Nuclear Information System (INIS)

    Johnson, F.T.

    1983-01-01

    A safety coolant injection system for nuclear reactors wherein a core reflood tank is provided to afford more reliable reflooding of the reactor core in the event of a break in one of the reactor coolant supply loops. Each reactor coolant supply loop is arranged in a separate compartment in the containment structure to contain and control the flow of spilled coolant so as to permit its use during emergency core cooling procedures. A spillway allows spilled coolant in the compartment to pass into the emergency water storage tank from where it can be pumped back to the reactor vessel. (author)

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

    International Nuclear Information System (INIS)

    Fazio, C.; Rieth, M.; Lindau, R.; Aktaa, J.; Schneider, H-C.; Konys, J.; Yurechko, M.; Mueller, G.; Weisenburger, A.

    2009-01-01

    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

  19. Considerations on nuclear reactor passive safety systems

    International Nuclear Information System (INIS)

    2016-01-01

    After having indicated some passive safety systems present in electronuclear reactors (control bars, safety injection system accumulators, reactor cooling after stoppage, hydrogen recombination systems), this report recalls the main characteristics of passive safety systems, and discusses the main issues associated with the assessment of new passive systems (notably to face a sustained loss of electric supply systems or of cold water source) and research axis to be developed in this respect. More precisely, the report comments the classification of safety passive systems as it is proposed by the IAEA, outlines and comments specific aspects of these systems regarding their operation and performance. The next part discusses the safety approach, the control of performance of safety passive systems, issues related to their reliability, and the expected contribution of R and D (for example: understanding of physical phenomena which have an influence of these systems, capacities of simulation of these phenomena, needs of experimentations to validate simulation codes)

  20. 77 FR 70409 - System Safety Program

    Science.gov (United States)

    2012-11-26

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

  1. Preliminary safety evaluation for CSR1000 with passive safety system

    International Nuclear Information System (INIS)

    Wu, Pan; Gou, Junli; Shan, Jianqiang; Zhang, Bo; Li, Xiang

    2014-01-01

    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

  2. Progress report: 1996 Radiation Safety Systems Division

    International Nuclear Information System (INIS)

    Bhagwat, A.M.; Sharma, D.N.; Abani, M.C.; Mehta, S.K.

    1997-01-01

    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)

  3. Comprehensive Lifecycle for Assuring System Safety

    Science.gov (United States)

    Knight, John C.; Rowanhill, Jonathan C.

    2017-01-01

    CLASS is a novel approach to the enhancement of system safety in which the system safety case becomes the focus of safety engineering throughout the system lifecycle. CLASS also expands the role of the safety case across all phases of the system's lifetime, from concept formation to decommissioning. As CLASS has been developed, the concept has been generalized to a more comprehensive notion of assurance becoming the driving goal, where safety is an important special case. This report summarizes major aspects of CLASS and contains a bibliography of papers that provide additional details.

  4. IAEA activities in the field of research reactors safety

    International Nuclear Information System (INIS)

    Ciuculescu, C.; Boado Magan, H.J.

    2004-01-01

    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)

  5. FOOD SAFETY CONTROL SYSTEM IN CHINA

    Institute of Scientific and Technical Information of China (English)

    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.

  6. 77 FR 22387 - Pipeline Safety: Information Collection Activities, Revision to Gas Transmission and Gathering...

    Science.gov (United States)

    2012-04-13

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No. PHMSA-2012-0024] Pipeline Safety: Information Collection Activities, Revision to Gas Transmission and Gathering Pipeline Systems Annual Report, Gas Transmission and Gathering Pipeline Systems Incident Report...

  7. 77 FR 58616 - Pipeline Safety: Information Collection Activities, Revision to Gas Transmission and Gathering...

    Science.gov (United States)

    2012-09-21

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No. PHMSA-2012-0024] Pipeline Safety: Information Collection Activities, Revision to Gas Transmission and Gathering Pipeline Systems Annual Report, Gas Transmission and Gathering Pipeline Systems Incident Report...

  8. Environmental, Health and Safety Assessment: ATS 7H Program (Phase 3R) Test Activities at the GE Power Systems Gas Turbine Manufacturing Facility, Greenville, SC

    Energy Technology Data Exchange (ETDEWEB)

    None

    1998-11-17

    International Technology Corporation (IT) was contracted by General Electric Company (GE) to assist in the preparation of an Environmental, Health and Safety (HI&3) assessment of the implementation of Phase 3R of the Advanced Turbine System (ATS) 7H program at the GE Gas Turbines facility located in Greenville, South Carolina. The assessment was prepared in accordance with GE's contractual agreement with the U.S. Department of Energy (GE/DOE Cooperative Agreement DE-FC21-95MC3 1176) and supports compliance with the requirements of the National Environmental Policy Act of 1970. This report provides a summary of the EH&S review and includes the following: General description of current site operations and EH&S status, Description of proposed ATS 7H-related activities and discussion of the resulting environmental, health, safety and other impacts to the site and surrounding area. Listing of permits and/or licenses required to comply with federal, state and local regulations for proposed 7H-related activities. Assessment of adequacy of current and required permits, licenses, programs and/or plans.

  9. Safety Management System in Croatia Control Ltd.

    OpenAIRE

    Pavlin, Stanislav; Sorić, Vedran; Bilać, Dragan; Dimnik, Igor; Galić, Daniel

    2009-01-01

    International Civil Aviation Organization and other international aviation organizations regulate the safety in civil aviation. In the recent years the International Civil Aviation Organization has introduced the concept of the safety management system through several documents among which the most important is the 2006 Safety Management Manual. It treats the safety management system in all the segments of civil aviation, from carriers, aerodromes and air traffic control to design, constructi...

  10. System Design and the Safety Basis

    International Nuclear Information System (INIS)

    Ellingson, Darrel

    2008-01-01

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

  11. NEA activities in safety and regulation

    International Nuclear Information System (INIS)

    Stadie, K.B.

    1983-01-01

    The NEA programme on Safety and Regulations is briefly reviewed. It encompasses four main areas - nuclear safety technology; nuclear licensing; radiation protection; and waste management - with three principal objectives: to promote exchanges of technical information in order to enlarge the data base for national decision making; to improve co-ordination of national R and D activities with emphasis on international standard problem exercises, and to promote international projects; to develop common technical, administrative and legal approaches to improve compatibility of safety and regulatory practices

  12. [B-BS and occupational health and safety management systems].

    Science.gov (United States)

    Bacchetta, Adriano Paolo

    2010-01-01

    The objective of a SGSL is the "prevention" agreement as approach of "pro-active" toward the safety at work through the construction of an integrated managerial system in synergic an dynamic way with the business organization, according to continuous improvement principles. Nevertheless the adoption of a SGSL, not could guarantee by itself the obtainment of the full effectiveness than projected and every individual's adhesion to it, must guarantee it's personal involvement in proactive way, so that to succeed to actual really how much hypothesized to systemic level to increase the safety in firm. The objective of a behavioral safety process that comes to be integrated in a SGSL, it has the purpose to succeed in implementing in firm a process of cultural change that raises the workers social group fundamental safety value, producing an ample and full involvement of all in the activities of safety at work development. SGSL = Occupational Health and Safety Management System.

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

    International Nuclear Information System (INIS)

    Yoshikawa, Hidekazu

    2004-01-01

    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. Intermediate probabilistic safety assessment approach for safety critical digital systems

    International Nuclear Information System (INIS)

    Taeyong, Sung; Hyun Gook, Kang

    2001-01-01

    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)

  15. IAEA activities on research reactor safety

    International Nuclear Information System (INIS)

    Alcala-Ruiz, F.

    1995-01-01

    Since its inception in 1957, the International Atomic Energy Agency (IAEA) has included activities in its programme to address aspects of research reactors such as safety, utilization and fuel cycle considerations. These activities were based on statutory functions and responsibilities, and on the current situation of research reactors in operation around the world; they responded to IAEA Member States' general or specific demands. At present, the IAEA activities on research reactors cover the above aspects and respond to specific and current issues, amongst which safety-related are of major concern to Member States. The present IAEA Research Reactor Safety Programme (RRSP) is a response to the current situation of about 300 research reactors in operation in 59 countries around the world. (orig.)

  16. Autonomous system for launch vehicle range safety

    Science.gov (United States)

    Ferrell, Bob; Haley, Sam

    2001-02-01

    The Autonomous Flight Safety System (AFSS) is a launch vehicle subsystem whose ultimate goal is an autonomous capability to assure range safety (people and valuable resources), flight personnel safety, flight assets safety (recovery of valuable vehicles and cargo), and global coverage with a dramatic simplification of range infrastructure. The AFSS is capable of determining current vehicle position and predicting the impact point with respect to flight restriction zones. Additionally, it is able to discern whether or not the launch vehicle is an immediate threat to public safety, and initiate the appropriate range safety response. These features provide for a dramatic cost reduction in range operations and improved reliability of mission success. .

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

    International Nuclear Information System (INIS)

    Kubo, Shigenobu; Shimakawa, Yoshio; Yamano, Hidemasa; Kotake, Shoji

    2011-01-01

    Safety design requirements for JSFR were summarized taking the development targets of the 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, 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 those 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 concept 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, and 8) Design against external events. The current specific requirements for 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 a mixed-oxide-fuelled core. (author)

  18. The PIANC Safety Factor System for Breakwaters

    DEFF Research Database (Denmark)

    Burcharth, H. F.

    2000-01-01

    The paper presents a summary of the recommendations for implementation of safety in breakwater designs given by the PIANC PTC IT Working Group No 12 on Analysis of Rubble Mound Breakwaters with Vertical and Inclined Concrete Walls. The working groups developed for the most important failure modes...... a system of partial safety factors which facilitate design to any target safety level....

  19. Safety

    International Nuclear Information System (INIS)

    1998-01-01

    A brief account of activities carried out by the Nuclear power plants Jaslovske Bohunice in 1997 is presented. These activities are reported under the headings: (1) Nuclear safety; (2) Industrial and health safety; (3) Radiation safety; and Fire protection

  20. 30 CFR 7.103 - Safety system control test.

    Science.gov (United States)

    2010-07-01

    ... Areas of Underground Coal Mines Where Permissible Electric Equipment is Required § 7.103 Safety system... operate immediately when activated and stop the engine within 15 seconds. (6) The total intake air inlet...

  1. Safety-related control air systems

    International Nuclear Information System (INIS)

    Anon.

    1977-01-01

    This Standard applies to those portions of the control air system that furnish air required to support, control, or operate systems or portions of systems that are safety related in nuclear power plants. This Standard relates only to the air supply system(s) for safety-related air operated devices and does not apply to the safety-related air operated device or to air operated actuators for such devices. The objectives of this Standard are to provide (1) minimum system design requirements for equipment, piping, instruments, controls, and wiring that constitute the air supply system; and (2) the system and component testing and maintenance requirements

  2. A philosophy for space nuclear systems safety

    International Nuclear Information System (INIS)

    Marshall, A.C.

    1992-01-01

    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

  3. Lessons learned on digital systems safety

    International Nuclear Information System (INIS)

    Sivertsen, Terje

    2005-06-01

    A decade ago, in 1994, lessons learned from Halden research activities on digital systems safety were summarized in the reports HWR-374 and HWR-375, under the title 'A Lessons Learned Report on Software Dependability'. The reports reviewed all activities made at the Halden Project in this field since 1977. As such, the reports provide a wealth of information on Halden research. At the same time, the lessons learned from the different activities are made more accessible to the reader by being summarized in terms of results, conclusions and recommendations. The present report provides a new lessons learned report, covering the Halden Project research activities in this area from 1994 to medio 2005. As before, the emphasis is on the results, conclusions and recommendations made from these activities, in particular how they can be utilized by different types of organisations, such as licensing authorities, safety assessors, power companies, and software developers. The contents of the report have been edited on the basis of input from a large number of Halden work reports, involving many different authors. Brief summaries of these reports are included in the last part of the report. (Author)

  4. Automation for System Safety Analysis

    Science.gov (United States)

    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.

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

    International Nuclear Information System (INIS)

    1989-09-01

    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

  6. The adaptive safety analysis and monitoring system

    Science.gov (United States)

    Tu, Haiying; Allanach, Jeffrey; Singh, Satnam; Pattipati, Krishna R.; Willett, Peter

    2004-09-01

    The Adaptive Safety Analysis and Monitoring (ASAM) system is a hybrid model-based software tool for assisting intelligence analysts to identify terrorist threats, to predict possible evolution of the terrorist activities, and to suggest strategies for countering terrorism. The ASAM system provides a distributed processing structure for gathering, sharing, understanding, and using information to assess and predict terrorist network states. In combination with counter-terrorist network models, it can also suggest feasible actions to inhibit potential terrorist threats. In this paper, we will introduce the architecture of the ASAM system, and discuss the hybrid modeling approach embedded in it, viz., Hidden Markov Models (HMMs) to detect and provide soft evidence on the states of terrorist network nodes based on partial and imperfect observations, and Bayesian networks (BNs) to integrate soft evidence from multiple HMMs. The functionality of the ASAM system is illustrated by way of application to the Indian Airlines Hijacking, as modeled from open sources.

  7. Architecture Level Safety Analyses for Safety-Critical Systems

    Directory of Open Access Journals (Sweden)

    K. S. Kushal

    2017-01-01

    Full Text Available The dependency of complex embedded Safety-Critical Systems across Avionics and Aerospace domains on their underlying software and hardware components has gradually increased with progression in time. Such application domain systems are developed based on a complex integrated architecture, which is modular in nature. Engineering practices assured with system safety standards to manage the failure, faulty, and unsafe operational conditions are very much necessary. System safety analyses involve the analysis of complex software architecture of the system, a major aspect in leading to fatal consequences in the behaviour of Safety-Critical Systems, and provide high reliability and dependability factors during their development. In this paper, we propose an architecture fault modeling and the safety analyses approach that will aid in identifying and eliminating the design flaws. The formal foundations of SAE Architecture Analysis & Design Language (AADL augmented with the Error Model Annex (EMV are discussed. The fault propagation, failure behaviour, and the composite behaviour of the design flaws/failures are considered for architecture safety analysis. The illustration of the proposed approach is validated by implementing the Speed Control Unit of Power-Boat Autopilot (PBA system. The Error Model Annex (EMV is guided with the pattern of consideration and inclusion of probable failure scenarios and propagation of fault conditions in the Speed Control Unit of Power-Boat Autopilot (PBA. This helps in validating the system architecture with the detection of the error event in the model and its impact in the operational environment. This also provides an insight of the certification impact that these exceptional conditions pose at various criticality levels and design assurance levels and its implications in verifying and validating the designs.

  8. Nuclear Power and Safety Division activity

    International Nuclear Information System (INIS)

    Pazdera, F.

    1991-01-01

    History of the Division is briefly described. Present research is centered on reliability analyses and thermal hydraulic analyses of transients and accidents. Some results of the safety analyses have been applied at nuclear power plants. A characterization is presented of computer codes for analyzing the behavior of fuel in normal and accident conditions. Research activities in the field of water chemistry and corrosion are oriented to the corrosion process at high temperatures and high pressures, and the related mass and radioactivity transfer; the effect of some chemical processes on primary coolant circuit materials; optimization of PWR filtration systems; and the development of the requisite monitoring instrumentation. A computerized operator support system has been developed, and at present it is tested at the Dukovany nuclear power plant. A program of nuclear fuel cycle strategy and economy has been worked out for nuclear fuel performance evaluation. Various options for better fuel exploitation, alternatives for advanced fuelling, and fuel cycle costs are assessed, and out-of-reactor fuel cycle options are compared. (M.D.). 7 refs., 32 refs

  9. Approaches to construction of systems of safety management in airlines

    Directory of Open Access Journals (Sweden)

    2015-01-01

    Full Text Available The article presents three approaches of building a safety management system (SMS in airlines in the framework of implementation of ICAO SARPs that apply methods of risk assessment based on use of operational activity of airline taking into account existing and implementing "protections" or "safety barriers".

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

    International Nuclear Information System (INIS)

    Angeles C, A.; Jimenez D, J.; Reyes L, J.

    1998-09-01

    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)

  11. The Evaluation of the Safety Benefits of Combined Passive and On-Board Active Safety Applications

    Science.gov (United States)

    Page, Yves; Cuny, Sophie; Zangmeister, Tobias; Kreiss, Jens-Peter; Hermitte, Thierry

    2009-01-01

    One of the objectives of the European TRACE project (TRaffic Accident Causation in Europe, 2006–2008) was to estimate the proportion of injury accidents that could be avoided and/or the proportion of injury accidents where the severity could be mitigated for on-the-market safety applications, if 100 % of the car fleet would be equipped with them. We have selected for evaluation the Electronic Stability Control (ESC) and the Emergency Brake Assist (EBA) applications. As for passive safety systems, recent cars are designed to offer overall safety protection. Car structure, load limiters, front airbags, side airbags, knee airbags, pretensioners, padding and non aggressive structures in the door panel, the dashboard, the windshield, the seats, and the head rest also contribute to applying more protection. The whole safety package is very difficult to evaluate separately, one element independently segmented from the others. We decided to consider evaluating the effectivenessof the whole passive safety package, This package,, for the sake of simplicity, was the number of stars awarded at the Euro NCAP testing. The challenges were to compare the effectiveness of some safety configuration SC I, with the effectiveness of a different safety configuration SC II. A safety configuration is understood as a package of safety functions. Ten comparisons have been carried out such as the evaluation of the safety benefit of a fifth star given that the car has four stars and an EBA. The main outcome of this analysis is that any addition of a passive or active safety function selected in this analysis is producing increased safety benefits. For example, if all cars were five stars fitted with EBA and ESC, instead of four stars without ESC and EBA, injury accidents would be reduced by 47.2% for severe injuries and 69.5% for fatal injuries. PMID:20184838

  12. Mental Workload and Situational Awareness Evaluation of APR1400 Engineered Safety Features- Component Control Activation Systems using Augmented Reality

    International Nuclear Information System (INIS)

    Murungi, Mwongeera; Jung, JaeCheon

    2016-01-01

    In the study, an Augmented Reality procedure guidance support system concept was designed and used as a tool for the measurement of mental workload and Situational awareness of an SRO (Senior Reactor Operator). The EOP was chosen as the scenario for testing because it is the one of the critical plant conditions that requires human intervention and it represents (one of the more) conservative approaches to the test scenarios that are possible. The system is expected to realize an improvement in the level of Situational Awareness and mental workload which have been demonstrated by previous studies to be directly linked with the system response to an emergency situation in the MCR. The planning and design of the project adhered to a Systems Engineering approach in order to provide an optimized framework for ensuring the successful implementation of the system design. Previous study and research into this topic has emphasized the importance of situational awareness in determining the human factor performance issues in the nuclear power plant Control Room operations. This paper broadly defined a technique that successfully used the operator’s mental workload (using NASATLX) and Situational Awareness (using SART) as quantifying measures to evaluate the performance of specific ESF-CCS functions based on human factors. These results show that an improvement of the SA/workload could lead to an improvement of the level of certainty that the emergency situation can be brought under control. It is expected that future development work in this area will yield an actualized Augmented Reality system that could incorporate MCR team control and possibly be implemented in the system validation of other I and C systems

  13. Mental Workload and Situational Awareness Evaluation of APR1400 Engineered Safety Features- Component Control Activation Systems using Augmented Reality

    Energy Technology Data Exchange (ETDEWEB)

    Murungi, Mwongeera; Jung, JaeCheon [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2016-10-15

    In the study, an Augmented Reality procedure guidance support system concept was designed and used as a tool for the measurement of mental workload and Situational awareness of an SRO (Senior Reactor Operator). The EOP was chosen as the scenario for testing because it is the one of the critical plant conditions that requires human intervention and it represents (one of the more) conservative approaches to the test scenarios that are possible. The system is expected to realize an improvement in the level of Situational Awareness and mental workload which have been demonstrated by previous studies to be directly linked with the system response to an emergency situation in the MCR. The planning and design of the project adhered to a Systems Engineering approach in order to provide an optimized framework for ensuring the successful implementation of the system design. Previous study and research into this topic has emphasized the importance of situational awareness in determining the human factor performance issues in the nuclear power plant Control Room operations. This paper broadly defined a technique that successfully used the operator’s mental workload (using NASATLX) and Situational Awareness (using SART) as quantifying measures to evaluate the performance of specific ESF-CCS functions based on human factors. These results show that an improvement of the SA/workload could lead to an improvement of the level of certainty that the emergency situation can be brought under control. It is expected that future development work in this area will yield an actualized Augmented Reality system that could incorporate MCR team control and possibly be implemented in the system validation of other I and C systems.

  14. The safety interlocking system at the NAC

    International Nuclear Information System (INIS)

    Visser, K.; Mostert, H.

    1984-01-01

    The central safety interlocking system (CSIS) controls the higher level of interlocking between the various cyclotron subsystems. It ensures the safe operation of the entire cyclotron facility as regards personnel safety and proper instrument operation. The system consists of a micro-processor with a ROM-based safety interlocking program, relay output modules providing ''safety OK'' instructions to all interlocked apparatus, alarm input modules connected to transducers providing binary alarm status signals and an interface to the central control computer. All solid state electronic components of the system are situated in a low level radiation area and are interfaced to cyclotron equipment by means of 24 V relays

  15. Meeting the maglev system's safety requirements

    Energy Technology Data Exchange (ETDEWEB)

    Pierick, K

    1983-12-01

    The author shows how the safety requirements of the maglev track system derive from the general legal conditions for the safety of tracked transport. It is described how their compliance beyond the so-called ''development-accompanying'' and ''acceptance-preparatory'' safety work can be assured for the Transrapid test layout (TVE) now building in Emsland and also for later application as public transport system in Germany within the meaning of the General Railway Act.

  16. PSA in design of passive/active safety reactors

    International Nuclear Information System (INIS)

    Sato, T.; Tanabe, A.; Kondo, S.

    1995-01-01

    PSAs in the design of advanced reactors are applied mainly in level 1 PSA areas. However, even in level 1 PSA, there are certain areas where special care must be taken depending on plant design concepts. This paper identifies these areas both for passive and active safety reactor concepts. For example, 'long-term PSA' and shutdown PSA are very important for a passive safety reactor concept from the standpoint of effectiveness of a grace period and passive safety systems. External events are also important for an active safety reactor concept. These kinds of special PSAs are difficult to conduct precisely in a conceptual design stage. This paper shows methods of conducting these kinds of special PSAs simply and conveniently and the use of acquired insights for the design of advanced reactors. This paper also clarifies the meaning or definition of a grace period from the standpoint of PSA

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

    Science.gov (United States)

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

    2011-01-01

    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

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

    Science.gov (United States)

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

    2002-12-01

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

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

    International Nuclear Information System (INIS)

    Kwon, Kee-Choon; Park, Gee-Yong; Kim, Jang-Yeol; Lee, Jang-Soo

    2013-01-01

    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)

  20. Safety Verification for Probabilistic Hybrid Systems

    DEFF Research Database (Denmark)

    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 o...... on a number of case studies, tackled using a prototypical implementation....

  1. Ergonomics in the context of system safety

    International Nuclear Information System (INIS)

    Donnelly, K.E.

    1984-01-01

    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

  2. Technical self reliance of digital safety systems

    Energy Technology Data Exchange (ETDEWEB)

    Kwon, Kee Choon; Lee, Dong Young [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Kim, Kook Hun [Doosan Heavy Industries and Construction, Changwon (Korea, Republic of); Choi, Seung Gap [POSCON, Pohang (Korea, Republic of)

    2009-04-15

    This paper summarizes the development results of the Korea Nuclear Instrumentation and Control System (KNICS) project sponsored by the Korean government. In this project, Man Machine Interface System (MMIS) architecture, two digital platforms, and several control systems are developed. One platform is a programmable Logic Controller (PLC) for a safety system and another platform is a Distributed Control System (DCS) for a non safety system. With the POSAFE Q PLC, a Reactor Protection System (RPS) and an Engineered Safety Feature Component Control System (ESF CCS) are developed. A Power Control System (PCS) is developed based on the DCS. The safety grade platform and the digital safety systems obtained approval for the Topical Report from the Korean regulatory body in February of 2009. Also a Korean utility and a vendor company determined KNICS results to apply them to the planned Nuclear Power Plant (NPP) in March 2009. This paper introduces the technical self reliance experiences of the safety grade platform and the digital safety systems developed in the KNICS R and D project.

  3. Systems Thinking and Patient Safety

    National Research Council Canada - National Science Library

    Schyve, Paul M

    2005-01-01

    Patient safety is a prominent theme in health care delivery today. This should come as no surprise, given that "first, do no harm" has been the ethical watchword throughout the history of medicine, nursing, and pharmacy...

  4. Safety-critical Java for embedded systems

    DEFF Research Database (Denmark)

    Schoeberl, Martin; Dalsgaard, Andreas Engelbredt; Hansen, René Rydhof

    2016-01-01

    This paper presents the motivation for and outcomes of an engineering research project on certifiable Javafor embedded systems. The project supports the upcoming standard for safety-critical Java, which defines asubset of Java and libraries aiming for development of high criticality systems....... The outcome of this projectinclude prototype safety-critical Java implementations, a time-predictable Java processor, analysis tools formemory safety, and example applications to explore the usability of safety-critical Java for this applicationarea. The text summarizes developments and key contributions...

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

    OpenAIRE

    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...

  6. SBO simulations for Integrated Passive Safety System (IPSS) using MARS

    International Nuclear Information System (INIS)

    Kim, Sang Ho; Jeong, Sung Yeop; Chang, Soon Heung

    2012-01-01

    The current nuclear power plants have lots of active safety systems with some passive safety systems. The safety of current and future nuclear power plants can be enhanced by the application of additional passive safety systems for the ultimate safety. It is helpful to install the passive safety systems on current nuclear power plants without the design change for the licensibility. For solving the problem about the system complexity shown in the Fukushima accidents, the current nuclear power plants are needed to be enhanced by an additional integrated and simplified system. As a previous research, the integrated passive safety system (IPSS) was proposed to solve the safety issues related with the decay heat removal, containment integrity and radiation release. It could be operated by natural phenomena like gravity, natural circulation and pressure difference without AC power. The five main functions of IPSS are: (a) Passive decay heat removal, (b) Passive emergency core cooling, (c) Passive containment cooling, (d) Passive in vessel retention and ex-vessel cooling, and (e) Filtered venting and pressure control. The purpose of this research is to analyze the performances of each function by using MARS code. The simulated accident scenarios were station black out (SBO) and the additional accidents accompanied by SBO

  7. OBTAINING FOOD SAFETY BY APPLYING HACCP SYSTEM

    Directory of Open Access Journals (Sweden)

    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.

  8. Technical features of ABWR safety systems

    International Nuclear Information System (INIS)

    Sugisaki, Toshihiko; Tominaga, Kenji; Horiuchi, Tetsuo

    1986-01-01

    The engineering safety facilities of ABWRs have been disigned so as to have many excellent characteristics such as safety, reliability and economy, reflecting the merit of adopting new technology such as internal pumps and new control rod driving mechanism, and coupled with the safety peculiar to BWRs. In this paper, about ECCS, containment vessels and others which compose the engineering safety facilities of ABWRs, the characteristics related to the safety owing to the adoption of internal pumps and others, and the evaluation of the performance at the time of various accidents are discussed. As the results of safety evaluation, it was clarified that due to the safety peculiar to ABWRs and the characteristics of the safety facilities, the large increases of safety, reliability and economy have been planned in the ABWRs, and for example, core flooding can be maintained even at the time of a hypothetical loss of coolant accident. BWRs have the simple system constitution, good self controllability, large natural circulation ability, simple operation control method and excellent ability of confining heat and radioactivity. BWRs have three safety functions to stop reactors, to remove heat from reactors, and to confine radioactive substances. These functions of ABWRs were evaluated, and very high safety was confirmed. (Kako, I.)

  9. Software reliability and safety in nuclear reactor protection systems

    International Nuclear Information System (INIS)

    Lawrence, J.D.

    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

  10. Software reliability and safety in nuclear reactor protection systems

    Energy Technology Data Exchange (ETDEWEB)

    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.

  11. Adoption of digital safety protection system in Japan

    International Nuclear Information System (INIS)

    Ogiso, Z.

    1998-01-01

    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)

  12. A study on an establishment for collaboration system with the OECD/NEA by means of the analysis of its main activities related to nuclear safety

    International Nuclear Information System (INIS)

    Song, J. H.; Kim, M. C.; Park, J. S.; Jeong, J. W.; Oh, C. W.

    2005-12-01

    The OECD Nuclear Energy Agency (NEA) was established on 1st February 1958 under the name of the OEEC European Nuclear Energy Agency. It received its present designation on 20th April 1972, when Japan became its first non-European full member. NEA membership today consists of 28 OECD member countries: Australia, Austria, Belgium, Canada, the Czech Republic, Denmark, Finland, France, Germany, Greece, Hungary, Iceland, Ireland, Italy, Japan, Luxembourg, Mexico, the Netherlands, Norway, Portugal, the Republic of Korea, the Slovak Republic, Spain, Sweden, Switzerland, Turkey, the United Kingdom and the United States. The Commission of the European Communities also takes part in the work of the Agency. The mission of the NEA is: o to assist its member countries in maintaining and further developing, through international cooperation, the scientific, technological and legal bases required for a safe, environmentally friendly and economical use of nuclear energy for peaceful purposes, as well as o to provide authoritative assessments and to forge common understandings on key issues, as input to government decisions on nuclear energy policy and to broader OECD policy analyses in areas such as energy and sustainable development. OECD Nuclear Energy Agency performs the work putting emphasis on safety enhancement and regulatory safety. Having Analyzed activities areas of Nuclear Development Committee (NDC), Committee on the Safety of Nuclear Installations (CSNI), Committee on Nuclear Regulatory Activities (CNRA) and drew out cooperation methods relating to nuclear safety regulation with them, it will be helpful economically and technically in meeting with improvement of nuclear safety efficiently

  13. Safety features of subcritical fluid fueled systems

    International Nuclear Information System (INIS)

    Bell, C.R.

    1995-01-01

    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 is 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

  14. Safety features of subcritical fluid fueled systems

    International Nuclear Information System (INIS)

    Bell, C.R.

    1994-01-01

    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

  15. Safety features of subcritical fluid fueled systems

    Energy Technology Data Exchange (ETDEWEB)

    Bell, C.R. [Los Alamos National Laboratory, NM (United States)

    1995-10-01

    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 is 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.

  16. Integrating system safety into the basic systems engineering process

    Science.gov (United States)

    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.

  17. Safety management system needs assessment.

    Science.gov (United States)

    2016-04-01

    The safety of the traveling public is critical as each year there are approximately 200 highway fatalities in Nebraska and numerous crash injuries. The objective of this research was to conduct a needs assessment to identify the requirements of a sta...

  18. Safety standards of IAEA for management systems

    International Nuclear Information System (INIS)

    Vincze, P.

    2005-01-01

    IAEA has developed a new series of safety standards which are assigned for constitution of the conditions and which give the instruction for setting up the management systems that integrate the aims of safety, health, life environment and quality. The new standard shall replace IAEA 50-C-Q - Requirements for security of the quality for safety in nuclear power plants and other nuclear facilities as well as 14 related safety instructions mentioned in the Safety series No. 50-C/SG-Q (1996). When developing of this complex, integrated set of requirements for management systems, the IAEA requirements 50-C-Q (1996) were taken into consideration as well as the publications developed within the International organisation for standardization (ISO) ISO 9001:2000 and ISO14001: 1996. The experience of European Union member states during the development, implementation and improvement of the management systems were also taken into consideration

  19. Reliability analysis of Angra I safety systems

    International Nuclear Information System (INIS)

    Oliveira, L.F.S. de; Soto, J.B.; Maciel, C.C.; Gibelli, S.M.O.; Fleming, P.V.; Arrieta, L.A.

    1980-07-01

    An extensive reliability analysis of some safety systems of Angra I, are presented. The fault tree technique, which has been successfully used in most reliability studies of nuclear safety systems performed to date is employed. Results of a quantitative determination of the unvailability of the accumulator and the containment spray injection systems are presented. These results are also compared to those reported in WASH-1400. (E.G.) [pt

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

    International Nuclear Information System (INIS)

    Tsuchiya, T.

    2007-01-01

    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 C 3 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 C 3 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

  1. Information systems in food safety management.

    Science.gov (United States)

    McMeekin, T A; Baranyi, J; Bowman, J; Dalgaard, P; Kirk, M; Ross, T; Schmid, S; Zwietering, M H

    2006-12-01

    Information systems are concerned with data capture, storage, analysis and retrieval. In the context of food safety management they are vital to assist decision making in a short time frame, potentially allowing decisions to be made and practices to be actioned in real time. Databases with information on microorganisms pertinent to the identification of foodborne pathogens, response of microbial populations to the environment and characteristics of foods and processing conditions are the cornerstone of food safety management systems. Such databases find application in: Identifying pathogens in food at the genus or species level using applied systematics in automated ways. Identifying pathogens below the species level by molecular subtyping, an approach successfully applied in epidemiological investigations of foodborne disease and the basis for national surveillance programs. Predictive modelling software, such as the Pathogen Modeling Program and Growth Predictor (that took over the main functions of Food Micromodel) the raw data of which were combined as the genesis of an international web based searchable database (ComBase). Expert systems combining databases on microbial characteristics, food composition and processing information with the resulting "pattern match" indicating problems that may arise from changes in product formulation or processing conditions. Computer software packages to aid the practical application of HACCP and risk assessment and decision trees to bring logical sequences to establishing and modifying food safety management practices. In addition there are many other uses of information systems that benefit food safety more globally, including: Rapid dissemination of information on foodborne disease outbreaks via websites or list servers carrying commentary from many sources, including the press and interest groups, on the reasons for and consequences of foodborne disease incidents. Active surveillance networks allowing rapid dissemination

  2. NASA Aviation Safety Reporting System (ASRS)

    Science.gov (United States)

    Connell, Linda J.

    2017-01-01

    The NASA Aviation Safety Reporting System (ASRS) collects, analyzes, and distributes de-identified safety information provided through confidentially submitted reports from frontline aviation personnel. Since its inception in 1976, the ASRS has collected over 1.4 million reports and has never breached the identity of the people sharing their information about events or safety issues. From this volume of data, the ASRS has released over 6,000 aviation safety alerts concerning potential hazards and safety concerns. The ASRS processes these reports, evaluates the information, and provides selected de-identified report information through the online ASRS Database at http:asrs.arc.nasa.gov. The NASA ASRS is also a founding member of the International Confidential Aviation Safety Systems (ICASS) group which is a collection of other national aviation reporting systems throughout the world. The ASRS model has also been replicated for application to improving safety in railroad, medical, fire fighting, and other domains. This presentation will discuss confidential, voluntary, and non-punitive reporting systems and their advantages in providing information for safety improvements.

  3. LOFT integral test system final safety analysis report

    International Nuclear Information System (INIS)

    1974-03-01

    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)

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

    International Nuclear Information System (INIS)

    Mrabit, K.; Sadagopan, G.

    2004-01-01

    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 S trategic 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 State' 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. (Author)

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

    International Nuclear Information System (INIS)

    Marbit, K.; Sadagopan, G.

    2005-01-01

    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

  6. A Reliability Assessment Method for the VHTR Safety Systems

    International Nuclear Information System (INIS)

    Lee, Hyung Sok; Jae, Moo Sung; Kim, Yong Wan

    2011-01-01

    The Passive safety system by very high temperature reactor which has attracted worldwide attention in the last century is the reliability safety system introduced for the improvement in the safety of the next generation nuclear power plant design. The Passive system functionality does not rely on an external source of energy, but on an intelligent use of the natural phenomena, such as gravity, conduction and radiation, which are always present. Because of these features, it is difficult to evaluate the passive safety on the risk analysis methodology having considered the existing active system failure. Therefore new reliability methodology has to be considered. In this study, the preliminary evaluation and conceptualization are tried, applying the concept of the load and capacity from the reliability physics model, designing the new passive system analysis methodology, and the trial applying to paper plant.

  7. Safety aspect of digital reactor protection system in Japan

    International Nuclear Information System (INIS)

    Ogiso, Zen-Ichi

    1998-01-01

    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)

  8. Safety status system for operating room devices.

    Science.gov (United States)

    Guédon, Annetje C P; Wauben, Linda S G L; Overvelde, Marlies; Blok, Joleen H; van der Elst, Maarten; Dankelman, Jenny; van den Dobbelsteen, John J

    2014-01-01

    Since the increase of the number of technological aids in the operating room (OR), equipment-related incidents have come to be a common kind of adverse events. This underlines the importance of adequate equipment management to improve the safety in the OR. A system was developed to monitor the safety status (periodic maintenance and registered malfunctions) of OR devices and to facilitate the notification of malfunctions. The objective was to assess whether the system is suitable for use in an busy OR setting and to analyse its effect on the notification of malfunctions. The system checks automatically the safety status of OR devices through constant communication with the technical facility management system, informs the OR staff real-time and facilitates notification of malfunctions. The system was tested for a pilot period of six months in four ORs of a Dutch teaching hospital and 17 users were interviewed on the usability of the system. The users provided positive feedback on the usability. For 86.6% of total time, the localisation of OR devices was accurate. 62 malfunctions of OR devices were reported, an increase of 12 notifications compared to the previous year. The safety status system was suitable for an OR complex, both from a usability and technical point of view, and an increase of reported malfunctions was observed. The system eases monitoring the safety status of equipment and is a promising tool to improve the safety related to OR devices.

  9. Aviation Safety Reporting System: Process and Procedures

    Science.gov (United States)

    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.

  10. Proactive Management of Aviation System Safety Risk

    Data.gov (United States)

    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 was...

  11. Safety considerations for compressed hydrogen storage systems

    International Nuclear Information System (INIS)

    Gleason, D.

    2006-01-01

    An overview of the safety considerations for various hydrogen storage options, including stationary, vehicle storage, and mobile refueling technologies. Indications of some of the challenges facing the industry as the demand for hydrogen fuel storage systems increases. (author)

  12. A new radiation safety control system for Ganil

    International Nuclear Information System (INIS)

    Saint Jores, P. De; Luong, T.T.; Martina, L.; Vega, G.

    1991-01-01

    A second generation radiation safety control system has been installed to upgrade the initial system which was not flexible enough to support new ion beams and new experimental conditions required by the accelerator operation. The main reasons which necessitated the improvement of the safety control system are presented. The new system which controls the Ganil accelerator from the first quarter of 1990 is described. It uses a star structured architecture, VME standard processors and front-end modules activated by pDOS operating system and high level language (C and Fortran) tasks, associated with enhanced resolution color displays for real time synoptics. (R.P.) 4 refs., 4 figs

  13. Cost benefit analysis of reactor safety systems

    International Nuclear Information System (INIS)

    Maurer, H.A.

    1984-01-01

    Cost/benefit analysis of reactor safety systems is a possibility appropriate to deal with reactor safety. The Commission of the European Communities supported a study on the cost-benefit or cost effectiveness of safety systems installed in modern PWR nuclear power plants. The following systems and their cooperation in emergency cases were in particular investigated in this study: the containment system (double containment), the leakage exhaust and control system, the annulus release exhaust system and the containment spray system. The benefit of a safety system is defined according to its contribution to the reduction of the radiological consequences for the environment after a LOCA. The analysis is so far performed in two different steps: the emergency core cooling system is considered to function properly, failure of the emergency core cooling system is assumed (with the possible consequence of core melt-down) and the results may demonstrate the evidence that striving for cost-effectiveness can produce a safer end result than the philosophy of safety at any cost. (orig.)

  14. COMPRESS - a computerized reactor safety system

    International Nuclear Information System (INIS)

    Vegh, E.

    1986-01-01

    The computerized reactor safety system, called COMPRESS, provides the following services: scram initiation; safety interlockings; event recording. The paper describes the architecture of the system and deals with reliability problems. A self-testing unit checks permanently the correct operation of the independent decision units. Moreover the decision units are tested by short pulses whether they can initiate a scram. The self-testing is described in detail

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

    International Nuclear Information System (INIS)

    ElBaradei, M.

    1998-01-01

    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

  16. Safety research activities on radioactive waste management in JNES

    International Nuclear Information System (INIS)

    Otsuka, Ichiro; Aoki, Hiroomi; Suko, Takeshi; Onishi, Yuko; Masuda, Yusuke; Kato, Masami

    2010-01-01

    Research activities in safety regulation of radioactive waste management are presented. Major activities are as follows. As for the geological disposal, major research areas are, developing 'safety indicators' to judge the adequacy of site investigation results presented by an implementer (NUMO), compiling basic requirements of safety design and safety assessment needed to make a safety review of the license application and developing an independent safety assessment methodology. In proceeding research, JNES, Japan Atomic Energy Agency (JAEA) and the National Institute of Advanced Industrial Science and Technology (AIST) signed an agreement of cooperative study on geological disposal in 2007. One of the ongoing joint studies under this agreement has been aimed at investigating regional-scale hydrogeological modeling using JAEA's Horonobe Underground Research Center. In the intermediate depth disposal, JNES conducted example analysis of reference facility and submitted the result to Nuclear Safety Commission of Japan (NSC). JNES is also listing issues to be addressed in the safety review of the license application and tries to make criteria of the review. Furthermore, JNES is developing analysis tool to evaluate long term safety of the facility and conducting an experiment to investigate long term behavior of engineered barrier system. In the near surface disposal of waste package, it must be confirmed by a regulatory inspector whether each package meets safety requirements. JNES continuously updates the confirmation methodology depending on new processing technologies. The clearance system was established in 2005. Two stages of regulatory involvement were adapted, 1) approval for measurement and judgment methods developed by the nuclear operator and 2) confirmation of measurement and judgment results based on approved methods. JNES is developing verification methodology for each stage. As for decommissioning, based on the regulatory needs and a research program

  17. Strategy to safety grade systems replacements

    International Nuclear Information System (INIS)

    Stimler, M.; Sullivan, K.E.; Trebincevic, I.

    1993-01-01

    The introduction of digital instrumentation and control systems in nuclear power plants is characterized by the need to satisfy the requirements of safety, reliability and man-machine ergonomics. Today digital instrumentation and control systems meet these requirements and the trend in Europe is towards full digital based nuclear power plant control systems. This paper describes Siemens (KWU) experience in nuclear power plants and development in trends within Europe. Topics which are the subject of major concern to NPP operators addressed in this paper are: human performance factors - man-machine interface; operating philosophy; safety, availability and reliability. Other aspects addressed are: Siemens open-quotes defense in depthclose quotes concept, description of Siemens digital I ampersand C systems, safety requirements and systems, I ampersand C qualification, control room ergonomics, information systems and retrofitting experience

  18. Safety and interlock system for Tristan

    International Nuclear Information System (INIS)

    Takeda, S.; Kudo, K.; Katoh, T.; Akiyama, A.

    1987-01-01

    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

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

    International Nuclear Information System (INIS)

    Almen, A.; Lundh, C.

    2015-01-01

    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 containing a safety disk

    International Nuclear Information System (INIS)

    Schupp, W.

    1975-01-01

    The safety element is not overdimensioned at pressures between 2 and 150 atmospheric excess pressure. Therefore the flat bursting disc is mounted within a supporting and stopping holding and the rated breaking point is covered by a supporting body. Its outer diameter sufficiently overlaps the recesses on both sides of the rated breaking point. It absorbs the total load given by the operating pressure. Only a release mechanism with slide wedge, eccentric disc, magnet, and rocker arm releases the supporting body, e.g. if the blow-down pressure is reached, so that the operating pressure may work on the bursting disc. An insulated copper wire layed in the breaking region within the bursting disc in case of shearing off signalizes the instant of failing of the breaking point because of current interruption. (DG) [de

  1. Safety of emerging nuclear energy systems

    International Nuclear Information System (INIS)

    Novikov, V.M.; Slesarev, I.S.

    1989-01-01

    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

  2. Personnel Risks in Ensuring Safety of Medical Activity

    Directory of Open Access Journals (Sweden)

    O. L. Zadvornaya

    2017-01-01

    Full Text Available Purpose: modern strategies of management of the organization require the formation of special management approaches based on the analysis of the mechanisms and processes of the organization of medical activities related to possible risks in activity of medical personnel. Based on international experience and own research the authors have identified features of a system of management of personnel risk in medical activities, examined approaches showing the sequence and contents of the main practical activities of the formation, maintenance and development of the system of management of personnel risks. Emphasized is the need for further research and implementation of the system of management of personnel risk in health care organizations. Study and assessment of personnel risks affecting the security of medical activities aimed at the development of the system of personnel risk management, development of a system of identification and monitoring of HR risk indicators with a purpose to improve institutional management and increase efficiency of activity of medical organizations. Methods: in the present study, the following methods were used: systemic approach, content analysis, methods of social diagnosis (questionnaires, interviews, comparative analysis, method of expert evaluations, method of statistical processing of information. Results: approaches to predict the occurrence and development of personnel risks have been reviewed and proposed. Conclusions and Relevance: patient safety is a global issue affecting countries at all levels of development. Each year, the WHO identifies a number of systemic and technical aspects and trends in the field of patient safety related to actions of medical workers. Existing imbalances in the staffing of the health system of the Russian Federation increase the probability of potential risks in medical practice. The personnel policy of healthcare of the Russian Federation requires further improvement and

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

    International Nuclear Information System (INIS)

    SEMMENS, L.S.

    1999-01-01

    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

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

  5. Classification of Aeronautics System Health and Safety Documents

    Data.gov (United States)

    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...

  6. System Safety in an IT Service Organization

    Science.gov (United States)

    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.

  7. Upgrading safety systems of industrial irradiation facilities

    International Nuclear Information System (INIS)

    Gomes, R.S.; Gomes, J.D.R.L.; Costa, E.L.C.; Costa, M.L.L.; Thomé, Z.D.

    2017-01-01

    The first industrial irradiation facility in operation in Brazil was designed in the 70s. Nowadays, twelve commercial and research facilities are in operation and two already decommissioned. Minor modifications and upgrades, as sensors replacement, have been introduced in these facilities, in order to reduce the technological gap in the control and safety systems. The safety systems are designed in agreement with the codes and standards at the time. Since then, new standards, codes and recommendations, as well as lessons learned from accidents, have been issued by various international committees or regulatory bodies. The rapid advance of the industry makes the safety equipment used in the original construction become obsolete. The decreasing demand for these older products means that they are no longer produced, which can make it impossible or costly to obtain spare parts and the expansion of legacy systems to include new features. This work aims to evaluate existing safety systems at Brazilian irradiation facilities, mainly the oldest facilities, taking into account the recommended IAEA's design requirements. Irrespective of the fact that during its operational period no event with victims have been recorded in Brazilian facilities, and that the regulatory inspections do not present any serious deviations regarding the safety procedures, it is necessary an assessment of safety system with the purpose of bringing their systems to 'the state of the art', avoiding their rapid obsolescence. This study has also taken into account the knowledge, concepts and solutions developed to upgrading safety system in irradiation facilities throughout the world. (author)

  8. Upgrading safety systems of industrial irradiation facilities

    Energy Technology Data Exchange (ETDEWEB)

    Gomes, R.S.; Gomes, J.D.R.L.; Costa, E.L.C.; Costa, M.L.L., E-mail: rogeriog@cnen.gov.br, E-mail: jlopes@cnen.gov.br, E-mail: evaldo@cnen.gov.br, E-mail: mara@cnen.gov.br [Comissão Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil). Diretoria de Radioproteção e Segurança Nuclear; Thomé, Z.D., E-mail: zielithome@gmail.com [Instituto Militar de Engenharia (IME), Rio de Janeiro, RJ (Brazil). Seção de Engenharia Nuclear

    2017-07-01

    The first industrial irradiation facility in operation in Brazil was designed in the 70s. Nowadays, twelve commercial and research facilities are in operation and two already decommissioned. Minor modifications and upgrades, as sensors replacement, have been introduced in these facilities, in order to reduce the technological gap in the control and safety systems. The safety systems are designed in agreement with the codes and standards at the time. Since then, new standards, codes and recommendations, as well as lessons learned from accidents, have been issued by various international committees or regulatory bodies. The rapid advance of the industry makes the safety equipment used in the original construction become obsolete. The decreasing demand for these older products means that they are no longer produced, which can make it impossible or costly to obtain spare parts and the expansion of legacy systems to include new features. This work aims to evaluate existing safety systems at Brazilian irradiation facilities, mainly the oldest facilities, taking into account the recommended IAEA's design requirements. Irrespective of the fact that during its operational period no event with victims have been recorded in Brazilian facilities, and that the regulatory inspections do not present any serious deviations regarding the safety procedures, it is necessary an assessment of safety system with the purpose of bringing their systems to 'the state of the art', avoiding their rapid obsolescence. This study has also taken into account the knowledge, concepts and solutions developed to upgrading safety system in irradiation facilities throughout the world. (author)

  9. Formation of maintenance economic safety enterprise system

    Directory of Open Access Journals (Sweden)

    N. A. Serebryakova

    2016-01-01

    Full Text Available The article examines the issues of economic security. The operation of enterprises is being implemented in a volatile market environment, which requires a comprehensive assessment of not only the individual factors affecting the operation of the enterprise, but also encourages the need to develop a comprehensive system for the enterprise to ensure economic security. The purpose of this study is to examine the theoretical and methodological approaches to assessing and ensuring the economic security of the enterprise, the development of a mechanism to ensure the economic security of the enterprise. Measures to ensure the safety of personnel suggest preventive work with the personnel, training personnel of the security services division, formation of personnel reserve of security personnel, the organization of work with new employees, reducing staff turnover. Preventive measures to minimize include activities not directly related to the activities of security units, but to minimize losses of commercial enterprise in the course of maintenance operations: control of inventories; control document; scheduled and unscheduled inspections during the reception of the goods; selection and organization of the movement control risk goods. Development of guidelines and regulations involves the planning of a clear legal regulation of all processes for the operation of commercial facility, potentially dangerous from the point of view of any commercial activity or threats to the security risks. The success of the activities is largely determined by the speed and accuracy of enterprise responses to emerging threats, where a key determinant of the effectiveness of business, is to create a system to ensure the economic security of the enterprise.

  10. Safety assessment of high consequence robotics system

    International Nuclear Information System (INIS)

    Robinson, D.G.; Atcitty, C.B.

    1996-01-01

    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

  11. Instructional games and activities for criticality safety training

    International Nuclear Information System (INIS)

    Bullard, B.; McBride, J.

    1993-01-01

    During the past several years, the Training and Management Systems Division (TMSD) staff of Oak Ridge Institute for Science and Education (ORISE) has designed and developed nuclear criticality safety (NCS) training programs that focus on high trainee involvement through the use of instructional games and activities. This paper discusses the instructional game, initial considerations for developing games, advantages and limitations of games, and how games may be used in developing and implementing NCS training. It also provides examples of the various instructional games and activities used in separate courses designed for Martin Marietta Energy Systems (MMES's) supervisors and U.S. Nuclear Regulatory Commission (NRC) fuel facility inspectors

  12. Active and intelligent packaging: The indication of quality and safety.

    Science.gov (United States)

    Janjarasskul, Theeranun; Suppakul, Panuwat

    2018-03-24

    The food industry has been under growing pressure to feed an exponentially increasing world population and challenged to meet rigorous food safety law and regulation. The plethora of media consumption has provoked consumer demand for safe, sustainable, organic, and wholesome products with "clean" labels. The application of active and intelligent packaging has been commercially adopted by food and pharmaceutical industries as a solution for the future for extending shelf life and simplifying production processes; facilitating complex distribution logistics; reducing, if not eliminating the need for preservatives in food formulations; enabling restricted food packaging applications; providing convenience, improving quality, variety and marketing features; as well as providing essential information to ensure consumer safety. This chapter reviews innovations of active and intelligent packaging which advance packaging technology through both scavenging and releasing systems for shelf life extension, and through diagnostic and identification systems for communicating quality, tracking and brand protection.

  13. Understanding Nuclear Safety Culture: A Systemic Approach

    International Nuclear Information System (INIS)

    Afghan, A.N.

    2016-01-01

    The Fukushima accident was a systemic failure (Report by Director General IAEA on the Fukushima Daiichi Accident). Systemic failure is a failure at system level unlike the currently understood notion which regards it as the failure of component and equipment. Systemic failures are due to the interdependence, complexity and unpredictability within systems and that is why these systems are called complex adaptive systems (CAS), in which “attractors” play an important role. If we want to understand the systemic failures we need to understand CAS and the role of these attractors. The intent of this paper is to identify some typical attractors (including stakeholders) and their role within complex adaptive system. Attractors can be stakeholders, individuals, processes, rules and regulations, SOPs etc., towards which other agents and individuals are attracted. This paper will try to identify attractors in nuclear safety culture and influence of their assumptions on safety culture behavior by taking examples from nuclear industry in Pakistan. For example, if the nuclear regulator is an attractor within nuclear safety culture CAS then how basic assumptions of nuclear plant operators and shift in-charges about “regulator” affect their own safety behavior?

  14. Safety parameter display system for Kalinin NPP

    International Nuclear Information System (INIS)

    Andreev, V.I.; Videneev, E.N.; Tissot, J.C.; Joonekindt, D.; Davidenko, N.N.; Shaftan, G.I.; Dounaev, V.G.; Neboyan, V.T.

    1995-01-01

    The paper discusses the safety parameter display system (SPDS), which is being designed for Kalinin NPP. The assessment of the safety status of the plant is done by the continuous monitoring of six critical safety functions and the corresponding status trees. Besides, a number of additional functions are realized within the scope of KlnNPP, aimed at providing the operator and the safety engineer in the main control room with more detailed information in accidental situation as well as during the normal operation. In particular, these functions are: archiving, data logs and alarm handling, safety actions monitoring, mnemonic diagrams indicating the state of main technological equipment and basic plant parameters, reference data, etc. As compared with the traditional scope of functions of this kind of systems, the functionality of KlnNPP SPDS is significantly expanded due to the inclusion in it the operator support function ''computerized procedures''. The basic SPDS implementation platform is ADACS of SEMA GROUP design. The system architecture includes two workstations in the main control room: one is for reactor operator and the other one for safety engineer. Every station has two CRT screens which ensures computerized procedures implementation and provides for extra services for the operator. Also, the information from the SPDS is transmitted to the local crisis center and to the crisis center of the State utility organization concern ''Rosenergoatom''. (author). 3 refs, 6 figs, 1 tab

  15. Quantitative risk assessment of digitalized safety systems

    Energy Technology Data Exchange (ETDEWEB)

    Shin, Sung Min; Lee, Sang Hun; Kang, Hym Gook [KAIST, Daejeon (Korea, Republic of); Lee, Seung Jun [UNIST, Ulasn (Korea, Republic of)

    2016-05-15

    A report published by the U.S. National Research Council indicates that appropriate methods for assessing reliability are key to establishing the acceptability of digital instrumentation and control (I and C) systems in safety-critical plants such as NPPs. Since the release of this issue, the methodology for the probabilistic safety assessment (PSA) of digital I and C systems has been studied. However, there is still no widely accepted method. Kang and Sung found three critical factors for safety assessment of digital systems: detection coverage of fault-tolerant techniques, software reliability quantification, and network communication risk. In reality the various factors composing digitalized I and C systems are not independent of each other but rather closely connected. Thus, from a macro point of view, a method that can integrate risk factors with different characteristics needs to be considered together with the micro approaches to address the challenges facing each factor.

  16. RSAS: a Reactor Safety Assessment System

    International Nuclear Information System (INIS)

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

    1985-01-01

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

  17. Food safety performance indicators to benchmark food safety output of food safety management systems.

    Science.gov (United States)

    Jacxsens, L; Uyttendaele, M; Devlieghere, F; Rovira, J; Gomez, S Oses; Luning, P A

    2010-07-31

    There is a need to measure the food safety performance in the agri-food chain without performing actual microbiological analysis. A food safety performance diagnosis, based on seven indicators and corresponding assessment grids have been developed and validated in nine European food businesses. Validation was conducted on the basis of an extensive microbiological assessment scheme (MAS). The assumption behind the food safety performance diagnosis is that food businesses which evaluate the performance of their food safety management system in a more structured way and according to very strict and specific criteria will have a better insight in their actual microbiological food safety performance, because food safety problems will be more systematically detected. The diagnosis can be a useful tool to have a first indication about the microbiological performance of a food safety management system present in a food business. Moreover, the diagnosis can be used in quantitative studies to get insight in the effect of interventions on sector or governmental level. Copyright 2010 Elsevier B.V. All rights reserved.

  18. Expert systems and nuclear safety

    International Nuclear Information System (INIS)

    Beltracchi, L.

    1990-01-01

    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

  19. Safety Analysis of Stochastic Dynamical Systems

    DEFF Research Database (Denmark)

    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...... that shows how the p-safe initial set is computed numerically....

  20. Safety analysis of accident localization system

    International Nuclear Information System (INIS)

    1999-01-01

    A complex safety analysis of accident localization system of Ignalina NPP was performed. Calculation results obtained, results of non-destruct ing testing and experimental data of reinforced concrete testing of buildings does not revealed deficiencies of buildings of accident localization system at unit 1 of Ignalina NPP. Calculations were performed using codes NEPTUNE, ALGOR, CONTAIN

  1. Research reactor management. Safety improvement activities in HANARO

    International Nuclear Information System (INIS)

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

    2012-01-01

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

  2. Safety parameter display system: an operator support system for enhancement of safety in Indian PHWRs

    International Nuclear Information System (INIS)

    Subramaniam, K.; Biswas, T.

    1994-01-01

    Ensuring operational safety in nuclear power plants is important as operator errors are observed to contribute significantly to the occurrence of accidents. Computerized operator support systems, which process and structure information, can help operators during both normal and transient conditions, and thereby enhance safety and aid effective response to emergency conditions. An important operator aid being developed and described in this paper, is the safety parameter display system (SPDS). The SPDS is an event-independent, symptom-based operator aid for safety monitoring. Knowledge-based systems can provide operators with an improved quality of information. An information processing model of a knowledge based operator support system (KBOSS) developed for emergency conditions using an expert system shell is also presented. The paper concludes with a discussion of the design issues involved in the use of a knowledge based systems for real time safety monitoring and fault diagnosis. (author). 8 refs., 4 figs., 1 tab

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

    International Nuclear Information System (INIS)

    Woodhouse, P.A.

    1995-01-01

    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

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

  5. A study of software safety analysis system for safety-critical software

    International Nuclear Information System (INIS)

    Chang, H. S.; Shin, H. K.; Chang, Y. W.; Jung, J. C.; Kim, J. H.; Han, H. H.; Son, H. S.

    2004-01-01

    The core factors and requirements for the safety-critical software traced and the methodology adopted in each stage of software life cycle are presented. In concept phase, Failure Modes and Effects Analysis (FMEA) for the system has been performed. The feasibility evaluation of selected safety parameter was performed and Preliminary Hazards Analysis list was prepared using HAZOP(Hazard and Operability) technique. And the check list for management control has been produced via walk-through technique. Based on the evaluation of the check list, activities to be performed in requirement phase have been determined. In the design phase, hazard analysis has been performed to check the safety capability of the system with regard to safety software algorithm using Fault Tree Analysis (FTA). In the test phase, the test items based on FMEA have been checked for fitness guided by an accident scenario. The pressurizer low pressure trip algorithm has been selected to apply FTA method to software safety analysis as a sample. By applying CASE tool, the requirements traceability of safety critical system has been enhanced during all of software life cycle phases

  6. From Safe Systems to Patient Safety

    DEFF Research Database (Denmark)

    Aarts, J.; Nøhr, C.

    2010-01-01

    for the 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...... 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 safety......This volume presents the papers from the fourth International Conference on Information Technology in Health Care: Socio-technical Approaches held in Aalborg, Denmark in June 2010. In 2001 the first conference was held in Rotterdam, The Netherlands with the theme: Sociotechnical' approaches...

  7. Recent advances in systems safety and security

    CERN Document Server

    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.

  8. The passive safety systems of the Swr 1000

    International Nuclear Information System (INIS)

    Neumann, D.

    2001-01-01

    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)

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

    International Nuclear Information System (INIS)

    Khazanov, A.L.

    2005-01-01

    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)

  10. Plant air systems safety study: Portsmouth Gaseous Diffusion Plant

    International Nuclear Information System (INIS)

    1982-05-01

    The Portsmouth Gaseous Diffusion Plant Air System facilities and operations are reviewed for potential safety problems not covered by standard industrial safety procedures. Information is presented under the following section headings: facility and process description (general); air plant equipment; air distribution system; safety systems; accident analysis; plant air system safety overview; and conclusion

  11. [Fundamental role of the workers' representative in preventive safety activity].

    Science.gov (United States)

    Ossicini, A; Bindi, L; Casale, M C

    2003-01-01

    With the arrival of Legislative Decree 626/94 which brought into Italian law the EU directives on workers' health and safety at the workplace, our country has also introduced rules that make a break with the past in this area, with the creation of new professional roles. The workers' safety representative takes on a fundamentally important role in the management of prevention, safety and health for workers in their place of employment in accordance with article 19. In fact, before the introduction of this Legislative Decree, the "protection" of workers' health was essentially based on rules and regulations the application of which was left to the exclusive and direct responsibility of the relationship between the employer and doctor, leaving out any participation by the worker. Whereas in the past workers could only be considered the final receivers of instructions about the security measures to apply, with Law 626 the workers themselves became active participants in the assessment of risks at work and consequently in the implementing of all the safety and hygiene measures contributing to the reduction of risk levels. The new regulations now in force assign important tasks to the workers' safety representative; all tasks and responsibilities associated with that role are examined and discussed, especially those relating to rights to information and training, consultation and participation in the process of designing and promoting safety measures. The job of workers' representative today takes on a fundamentally important meaning and role in a self-regulating system of work safety, where he or she has a proper area responsibility, so becoming a reference point for the workers generally.

  12. DESIGN PACKAGE 1E SYSTEM SAFETY ANALYSIS

    Energy Technology Data Exchange (ETDEWEB)

    M. Salem

    1995-06-23

    The purpose of this analysis is to systematically identify and evaluate hazards related to the Yucca Mountain Project Exploratory Studies Facility (ESF) Design Package 1E, Surface Facilities, (for a list of design items included in the package 1E system safety analysis see section 3). This process is an integral part of the systems engineering process; whereby safety is considered during planning, design, testing, and construction. A largely qualitative approach was used since a radiological System Safety Analysis is not required. The risk assessment in this analysis characterizes the accident scenarios associated with the Design Package 1E structures/systems/components(S/S/Cs) in terms of relative risk and includes recommendations for mitigating all identified risks. The priority for recommending and implementing mitigation control features is: (1) Incorporate measures to reduce risks and hazards into the structure/system/component design, (2) add safety devices and capabilities to the designs that reduce risk, (3) provide devices that detect and warn personnel of hazardous conditions, and (4) develop procedures and conduct training to increase worker awareness of potential hazards, on methods to reduce exposure to hazards, and on the actions required to avoid accidents or correct hazardous conditions.

  13. Development of the Digital Reactor Safety System

    International Nuclear Information System (INIS)

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

    2008-04-01

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

  14. Safety system for reactor container

    International Nuclear Information System (INIS)

    Shimizu, Miwako; Seki, Osamu; Mano, Takio.

    1995-01-01

    A slanted structure is formed below a reactor core where there is a possibility that molten reactor core materials are dropped, and above a water level of a pool which is formed by coolants flown from a reactor recycling system and accumulated on the inner bottom of the reactor container, to prevent molten fuels from dropping at once in the form of a large amount of lump. The molten materials are provisionally received on the structure, gradually formed into small pieces and then dropped. Further, the molten materials are dropped and received provisionally on a group of coolant-flowing pipelines below the structure, to lower the temperature of the molten materials, and then the reactor core molten materials are gradually formed into small pieces and dropped into the pool water. Since they are not dropped directly into the pool water but dropped gradually into the pool water as small droplets, occurrence of steam explosion can be reduced. The occurrence of steam explosion due to dropped molten reactor core material and pool water is suppressed, and the molten materials are kept in the pool water, thereby enabling to maintain the integrity of the reactor container more effectively. (N.H.)

  15. Software qualification for digital safety system in KNICS project

    International Nuclear Information System (INIS)

    Kwon, Kee-Choon; Lee, Dong-Young; Choi, Jong-Gyun

    2012-01-01

    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)

  16. An approach for assessing ALWR passive safety system reliability

    International Nuclear Information System (INIS)

    Hake, T.M.

    1991-01-01

    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

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

    International Nuclear Information System (INIS)

    Omoto, Akira

    2001-01-01

    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

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

    International Nuclear Information System (INIS)

    Hashim Muhammad; Yoshikawa, Hidekazu; Yang Ming

    2013-01-01

    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)

  19. Analysis and design on airport safety information management system

    Directory of Open Access Journals (Sweden)

    Yan Lin

    2017-01-01

    Full Text Available Airport safety information management system is the foundation of implementing safety operation, risk control, safety performance monitor, and safety management decision for the airport. The paper puts forward the architecture of airport safety information management system based on B/S model, focuses on safety information processing flow, designs the functional modules and proposes the supporting conditions for system operation. The system construction is helpful to perfecting the long effect mechanism driven by safety information, continually increasing airport safety management level and control proficiency.

  20. Advanced reactor systems: safety and regulatory aspects

    International Nuclear Information System (INIS)

    Gopalakrishnan, A.

    1994-01-01

    Safety features which are desirable in futuristic reactor systems have been the subject of several studies over the past decade by different expert groups. When one discusses this subject, therefore, in a somewhat non-specific and qualitative manner, it is best to make use of the already available collective wisdom and literature on the matter. (author). 3 refs

  1. 76 FR 14592 - Safety Management System; Withdrawal

    Science.gov (United States)

    2011-03-17

    ...), Federal Aviation Administration, 800 Independence Avenue, SW., Washington, DC 20591; telephone (202) 494...). The FAA also chartered the Safety Management System Aviation Rulemaking Committee (ARC) (Order No..., including the ANPRM. On March 31, 2010, the ARC submitted its report to the FAA. As a result of the...

  2. Maintenance of radiation safety information system

    Energy Technology Data Exchange (ETDEWEB)

    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.

  3. 77 FR 11120 - Patient Safety Organizations: Voluntary Relinquishment From UAB Health System Patient Safety...

    Science.gov (United States)

    2012-02-24

    ... Organizations: Voluntary Relinquishment From UAB Health System Patient Safety Organization AGENCY: Agency for... notification of voluntary relinquishment from the UAB Health System Patient Safety Organization of its status as a Patient Safety Organization (PSO). The Patient Safety and Quality Improvement Act of 2005...

  4. Current activities on safety improvement at Ukrainian NPPs

    International Nuclear Information System (INIS)

    Stovbun, V.V.

    2000-01-01

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

  5. IAEA safety requirements for safety assessment of fuel cycle facilities and activities

    International Nuclear Information System (INIS)

    Jones, G.

    2013-01-01

    The IAEA's Statute authorises the Agency to establish standards of safety for protection of health and minimisation of danger to life and property. In that respect, the IAEA has established a Safety Fundamentals publication which contains ten safety principles for ensuring the protection of workers, the public and the environment from the harmful effects of ionising radiation. A number of these principles require safety assessments to be carried out as a means of evaluating compliance with safety requirements for all nuclear facilities and activities and to determine the measures that need to be taken to ensure safety. The safety assessments are required to be carried out and documented by the organisation responsible for operating the facility or conducting the activity, are to be independently verified and are to be submitted to the regulatory body as part of the licensing or authorisation process. In addition to the principles of the Safety Fundamentals, the IAEA establishes requirements that must be met to ensure the protection of people and the environment and which are governed by the principles in the Safety Fundamentals. The IAEA's Safety Requirements publication 'Safety Assessment for Facilities and Activities', establishes the safety requirements that need to be fulfilled in conducting and maintaining safety assessments for the lifetime of facilities and activities, with specific attention to defence in depth and the requirement for a graded approach to the application of these safety requirements across the wide range of fuel cycle facilities and activities. Requirements for independent verification of the safety assessment that needs to be carried out by the operating organisation, including the requirement for the safety assessment to be periodically reviewed and updated are also covered. For many fuel cycle facilities and activities, environmental impact assessments and non-radiological risk assessments will be required. The

  6. INTEGRATED SAFETY MANAGEMENT SYSTEM IN AIR TRAFFIC SERVICES

    Directory of Open Access Journals (Sweden)

    Volodymyr Kharchenko

    2014-06-01

    Full Text Available The article deals with the analysis of the researches conducted in the field of safety management systems.Safety management system framework, methods and tools for safety analysis in Air Traffic Control have been reviewed.Principles of development of Integrated safety management system in Air Traffic Services have been proposed.

  7. Security for safety critical space borne systems

    Science.gov (United States)

    Legrand, Sue

    1987-01-01

    The Space Station contains safety critical computer software components in systems that can affect life and vital property. These components require a multilevel secure system that provides dynamic access control of the data and processes involved. A study is under way to define requirements for a security model providing access control through level B3 of the Orange Book. The model will be prototyped at NASA-Johnson Space Center.

  8. Passive components of NPP safety-related systems

    International Nuclear Information System (INIS)

    Ionaytis Romuald, R.; Bubnova Tatyana, A.

    2005-01-01

    This paper presents a new passive components with having drives: fast-response cutoff valves; modular actuators with opposite cocking pneumatic drives and actuation spring drives; voting electromagnetic valve units for control of pneumatic drives; passive initiators of actuation; visual diagnostics . All these devices have been developed and tested at mock-ups. This paper presents also the following direct-action passive safety components: modular pressure-relief safety valves; pilot safety valves with passive action; check valves with remote position indicator and after-tightening; modular inserts for limiting emergency coolant flow; vortex rectifier; critical weld fasteners; gas-liquid valves; fast-removable seal assembly; seal spring loaders; grooves for increasing hydraulic resistance. Replacement of active safety system components for passive ones improves the general reliability NPP by 1.5 or 2 orders of magnitudes. (authors)

  9. Annual activity report of Ignalina NPP Safety Analysis Group for 1995 year

    International Nuclear Information System (INIS)

    Ushpuras, E.; Augutis, J.; Bubelis, E.

    1995-01-01

    The main results of Ignalina NPP Safety Analysis Group (ISAG) investigations for 1995 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. 18 refs., 9 tabs., 110 figs

  10. Annual activity report of Ignalina NPP Safety Analysis Group for the year 1997

    International Nuclear Information System (INIS)

    Ushpuras, E.; Augutis, J.; Bubelis, E.; Kaliatka, A

    1998-01-01

    The main results of Ignalina NPP Safety Analysis Group (ISAG) investigations for the year 1997 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

  11. Using system dynamics simulation for assessment of hydropower system safety

    Science.gov (United States)

    King, L. M.; Simonovic, S. P.; Hartford, D. N. D.

    2017-08-01

    Hydropower infrastructure systems are complex, high consequence structures which must be operated safely to avoid catastrophic impacts to human life, the environment, and the economy. Dam safety practitioners must have an in-depth understanding of how these systems function under various operating conditions in order to ensure the appropriate measures are taken to reduce system vulnerability. Simulation of system operating conditions allows modelers to investigate system performance from the beginning of an undesirable event to full system recovery. System dynamics simulation facilitates the modeling of dynamic interactions among complex arrangements of system components, providing outputs of system performance that can be used to quantify safety. This paper presents the framework for a modeling approach that can be used to simulate a range of potential operating conditions for a hydropower infrastructure system. Details of the generic hydropower infrastructure system simulation model are provided. A case study is used to evaluate system outcomes in response to a particular earthquake scenario, with two system safety performance measures shown. Results indicate that the simulation model is able to estimate potential measures of system safety which relate to flow conveyance and flow retention. A comparison of operational and upgrade strategies is shown to demonstrate the utility of the model for comparing various operational response strategies, capital upgrade alternatives, and maintenance regimes. Results show that seismic upgrades to the spillway gates provide the largest improvement in system performance for the system and scenario of interest.

  12. Instrumentation and control systems important to safety in nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2005-01-01

    This Safety Guide was prepared under the IAEA programme for establishing safety standards for nuclear power plants. It supplements Safety Standards Series No. NS-R-1: Safety of Nuclear Power Plants: Design (the Requirements for Design), which establishes the design requirements for ensuring the safety of nuclear power plants. This Safety Guide describes how the requirements should be met for instrumentation and control (I and C) systems important to safety. This publication is a revision and combination of two previous Safety Guides: Safety Series Nos 50-SG-D3 and 50-SG-D8, which are superseded by this new Safety Guide. The revision takes account of developments in I and C systems important to safety since the earlier Safety Guides were published in 1980 and 1984, respectively. The objective of this Safety Guide is to provide guidance on the design of I and C systems important to safety in nuclear power plants, including all I and C components, from the sensors allocated to the mechanical systems to the actuated equipment, operator interfaces and auxiliary equipment. This Safety Guide deals mainly with design requirements for those I and C systems that are important to safety. It expands on paragraphs of Ref in the area of I and C systems important to safety. This publication is intended for use primarily by designers of nuclear power plants and also by owners and/or operators and regulators of nuclear power plants. This Safety Guide provides general guidance on I and C systems important to safety which is broadly applicable to many nuclear power plants. More detailed requirements and limitations for safe operation specific to a particular plant type should be established as part of the design process. The present guidance is focused on the design principles for systems important to safety that warrant particular attention, and should be applied to both the design of new I and C systems and the modernization of existing systems. Guidance is provided on how design

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

    International Nuclear Information System (INIS)

    Ushpuras, E.; Augutis, J.; Bubelis, E.

    1997-03-01

    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

  14. Status of the EU test blanket systems safety studies

    International Nuclear Information System (INIS)

    Panayotov, Dobromir; Poitevin, Yves; Ricapito, Italo; Zmitko, Milan

    2015-01-01

    Highlights: • TBS safety demonstration files. • Safety functions and related design features – detailed TBS components classifications. • Nuclear analyses, radiation shielding and protection. • TBS radiological waste management strategy and categorization. • Selection and definition of reference accidents scenarios and accidents analyses. - Abstract: The European joint undertaking for ITER and the development of fusion energy (‘Fusion for Energy’ – F4E) provides the European contributions to the ITER international fusion energy research project. Among others it includes also the development, design, technological demonstration and implementation of the European test blanket systems (TBS) in ITER. Currently two EU TBS designs are in the phase of conceptual design – helium-cooled lithium-lead (HCLL) and helium-cooled pebble-bed (HCPB). Safety demonstration is an important part of the work devoted to the achievement of the next key project milestone the conceptual design review. The paper reveals the details of the work on EU TBS safety performed in the last couple of years: update of the TBS safety demonstration files; safety functions and related design features; detailed TBS components classifications; nuclear analyses, radiation shielding and protection; TBS radiological waste management strategy and categorization; selection and definition of reference accidents scenarios, and accidents analyses. Finally the authors share the information on on-going and planned future EU TBS safety activities.

  15. Status of the EU test blanket systems safety studies

    Energy Technology Data Exchange (ETDEWEB)

    Panayotov, Dobromir, E-mail: dobromir.panayotov@f4e.europa.eu; Poitevin, Yves; Ricapito, Italo; Zmitko, Milan

    2015-10-15

    Highlights: • TBS safety demonstration files. • Safety functions and related design features – detailed TBS components classifications. • Nuclear analyses, radiation shielding and protection. • TBS radiological waste management strategy and categorization. • Selection and definition of reference accidents scenarios and accidents analyses. - Abstract: The European joint undertaking for ITER and the development of fusion energy (‘Fusion for Energy’ – F4E) provides the European contributions to the ITER international fusion energy research project. Among others it includes also the development, design, technological demonstration and implementation of the European test blanket systems (TBS) in ITER. Currently two EU TBS designs are in the phase of conceptual design – helium-cooled lithium-lead (HCLL) and helium-cooled pebble-bed (HCPB). Safety demonstration is an important part of the work devoted to the achievement of the next key project milestone the conceptual design review. The paper reveals the details of the work on EU TBS safety performed in the last couple of years: update of the TBS safety demonstration files; safety functions and related design features; detailed TBS components classifications; nuclear analyses, radiation shielding and protection; TBS radiological waste management strategy and categorization; selection and definition of reference accidents scenarios, and accidents analyses. Finally the authors share the information on on-going and planned future EU TBS safety activities.

  16. Safety of the medical gas pipeline system

    Directory of Open Access Journals (Sweden)

    Sushmita Sarangi

    2018-01-01

    Full Text Available Medical gases are nowadays being used for a number of diverse clinical applications and its piped delivery is a landmark achievement in the field of patient care. Patient safety is of paramount importance in the design, installation, commissioning, and operation of medical gas pipeline systems (MGPS. The system has to be operational round the clock, with practically zero downtime and its failure can be fatal if not restored at the earliest. There is a lack of awareness among the clinicians regarding the medico-legal aspect involved with the MGPS. It is a highly technical field; hence, an in-depth knowledge is a must to ensure safety with the system.

  17. ACP Facility Safety Surveillance System Installation

    International Nuclear Information System (INIS)

    You, Gil Sung; Kook, D. H.; Choung, W. M.; Ku, J. H.; Cho, I. J.; You, G. S.; Kwon, K. C.; Lee, W. K.; Lee, E. P.

    2006-10-01

    The Advanced spent fuel Conditioning Process is under development for effective management of spent fuel by converting UO 2 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

    International Nuclear Information System (INIS)

    Eisgruber, H.; Stadelmann, W.

    1991-01-01

    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.) [de

  19. The NASA Aviation Safety Reporting System

    Science.gov (United States)

    1983-01-01

    This is the fourteenth in a series of reports based on safety-related incidents submitted to the NASA Aviation Safety Reporting System by pilots, controllers, and, occasionally, other participants in the National Aviation System (refs. 1-13). ASRS operates under a memorandum of agreement between the National Aviation and Space Administration and the Federal Aviation Administration. The report contains, first, a special study prepared by the ASRS Office Staff, of pilot- and controller-submitted reports related to the perceived operation of the ATC system since the 1981 walkout of the controllers' labor organization. Next is a research paper analyzing incidents occurring while single-pilot crews were conducting IFR flights. A third section presents a selection of Alert Bulletins issued by ASRS, with the responses they have elicited from FAA and others concerned. Finally, the report contains a list of publications produced by ASRS with instructions for obtaining them.

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

    International Nuclear Information System (INIS)

    Adams, D.M.; Rohrdanz, R.R.

    1982-01-01

    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

  1. Passive safety systems for integral reactors

    International Nuclear Information System (INIS)

    Kuul, V.S.; Samoilov, O.B.

    1996-01-01

    In this paper, a wide range of passive safety systems intended for use on integral reactors is considered. The operation of these systems relies on natural processes and does not require external power supplies. Using these systems, there is the possibility of preventing serious consequences for all classes of accidents including reactivity, loss-of-coolant and loss of heat sink as well as severe accidents. Enhancement of safety system reliability has been achieved through the use of self-actuating devices, capable of providing passive initiation of protective and isolation systems, which respond immediately to variations in the physical parameters of the fluid in the reactor or in a guard vessel. For beyond design base accidents accompanied by complete loss of heat removal capability, autonomous self-actuated ERHR trains have been proposed. These trains are completely independent of the secondary loops and need no action to isolate them from the steam turbine plant. Passive safety principles have been consistently implemented in AST-500, ATETS-200 and VPBER 600 which are new generation NPPs developed by OKBM. Their main characteristic is enhanced stability over a wide range of internal and external emergency initiators. (author). 10 figs

  2. Passive safety systems for integral reactors

    Energy Technology Data Exchange (ETDEWEB)

    Kuul, V S; Samoilov, O B [OKB Mechanical Engineering (Russian Federation)

    1996-12-01

    In this paper, a wide range of passive safety systems intended for use on integral reactors is considered. The operation of these systems relies on natural processes and does not require external power supplies. Using these systems, there is the possibility of preventing serious consequences for all classes of accidents including reactivity, loss-of-coolant and loss of heat sink as well as severe accidents. Enhancement of safety system reliability has been achieved through the use of self-actuating devices, capable of providing passive initiation of protective and isolation systems, which respond immediately to variations in the physical parameters of the fluid in the reactor or in a guard vessel. For beyond design base accidents accompanied by complete loss of heat removal capability, autonomous self-actuated ERHR trains have been proposed. These trains are completely independent of the secondary loops and need no action to isolate them from the steam turbine plant. Passive safety principles have been consistently implemented in AST-500, ATETS-200 and VPBER 600 which are new generation NPPs developed by OKBM. Their main characteristic is enhanced stability over a wide range of internal and external emergency initiators. (author). 10 figs.

  3. Software Safety Life cycle and Method of POSAFE-Q System

    International Nuclear Information System (INIS)

    Lee, Jang-Soo; Kwon, Kee-Choon

    2006-01-01

    This paper describes the relationship between the overall safety life cycle and the software safety life cycle during the development of the software based safety systems of Nuclear Power Plants. This includes the design and evaluation activities of components as well as the system. The paper also compares the safety life cycle and planning activities defined in IEC 61508 with those in IEC 60880, IEEE 7-4.3.2, and IEEE 1228. Using the KNICS project as an example, software safety life cycle and safety analysis methods applied to the POSAFE-Q are demonstrated. KNICS software safety life cycle is described by comparing to the software development, testing, and safety analysis process with international standards. The safety assessment of the software for POSAFE-Q is a joint Korean German project. The assessment methods applied in the project and the experiences gained from this project are presented

  4. Nuclear safety regulation on nuclear safety equipment activities in relation to human and organizational factors

    International Nuclear Information System (INIS)

    Li Tianshu

    2013-01-01

    Based on years of knowledge in nuclear safety supervision and experience of investigating and dealing with violation events in repair welding of DFHM, this paper analyzes major faults in manufacturing and maintaining activities of nuclear safety equipment in relation to human and organizational factors. It could be deducted that human and organizational factors has definitely become key features in the development of nuclear energy and technology. Some feasible measures to reinforce supervision on nuclear safety equipment activities have also been proposed. (author)

  5. Safety objectives for nuclear activities in Canada

    International Nuclear Information System (INIS)

    1982-04-01

    This report by the Advisory Committee on Nuclear Safety presents a concise statement of the basic safety objectives which the Committee considers underlie, or should underlie, the regulations and the licensing and compliance practices of the Atomic Energy Control Board. The report also includes a number of general criteria for achieving these objectives

  6. Guidelines for implementation of RCM on safety systems

    International Nuclear Information System (INIS)

    Kim, Tae Woon; Brijendra Singh.

    1996-04-01

    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

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

    OpenAIRE

    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 ...

  8. Industrial Personal Computer based Display for Nuclear Safety System

    International Nuclear Information System (INIS)

    Kim, Ji Hyeon; Kim, Aram; Jo, Jung Hee; Kim, Ki Beom; Cheon, Sung Hyun; Cho, Joo Hyun; Sohn, Se Do; Baek, Seung Min

    2014-01-01

    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

  9. Industrial Personal Computer based Display for Nuclear Safety System

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Ji Hyeon; Kim, Aram; Jo, Jung Hee; Kim, Ki Beom; Cheon, Sung Hyun; Cho, Joo Hyun; Sohn, Se Do; Baek, Seung Min [KEPCO, Youngin (Korea, Republic of)

    2014-08-15

    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.

  10. Nuclear safety considerations with emphasis on instrumentation and control systems

    International Nuclear Information System (INIS)

    Beare, J.W.

    1978-01-01

    The conceptual model of a nuclear power plant in Canada is that it consists basically of two kinds of systems. The first kind is the process systems, that is, those structures and components associated with the production of nuclear energy and its conversion to other forms of energy. The second kind is the special safety systems, whose purpose it is to protect the public in the event of a serious failure in the process systems which might otherwise lead to unacceptable radiological consequences. Quantitative limits are set on the unavailability of the special safety systems. These limits are low enough to be consistent with low overall risk and yet can be demonstrated by test during operation of the plant. Low unavailability is an important but not the only condition required for low unrealiability for the special safety systems. The special safety systems minimize the chance of a cross-linked failure particularly under the conditions experienced as a result of the more severe types of postulated serious process failures. Nuclear power plants must also withstand, without a major hazard to the public, certain rare events associated with natural phenomena or man-made activities off-site and also certain in-plant events such as fire or break-up of a turbine-generator which might have a cross-linking effect on process and safety systems. In the latest designs, Canadian nuclear power plants have emergency systems to deal with such events. The emergency systems have an enhanced degree of physical and functional separation from other plant systems. (author)

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

    Science.gov (United States)

    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. Copyright © 2013 Elsevier Ltd. All rights reserved.

  12. An approach for assessing ALWR passive safety system reliability

    International Nuclear Information System (INIS)

    Hake, T.M.

    1991-01-01

    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

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

    International Nuclear Information System (INIS)

    Forsberg, C.W.

    1989-01-01

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

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

    International Nuclear Information System (INIS)

    Battle, Ronald E.; DeVan, B.; Munro, John K. Jr.

    2006-01-01

    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

  15. Performance scorecard for occupational safety and health management systems

    Directory of Open Access Journals (Sweden)

    Hernâni Veloso Neto

    2012-06-01

    Full Text Available The pro-active and systematic search for best performances should be the two assumptions of any management system, so safety and health management in organizations must also be guided by these same precepts. However, the scientific production evidences that the performance evaluation processes in safety and health continue to be guided, in their essence, by intermittency, reactivity and negativity, which are not consistent with the assumptions referenced above. Therefore, it is essential that health and safety at work management systems (HSW MS are structured from an active and positive viewpoint, focusing on continuous improvement. This implies considering performance evaluation processes that incorporate, on the one hand, monitoring, measuring and verification procedures, and on the other hand, structured matrixes of results that capture the key factors of success, by mobilizing both reactive and proactive indicators. One of the instruments that can fulfill these precepts of health and safety performance evaluation is the SafetyCard, a performance scorecard for HSW MS that we developed and will seek to outline and demonstrate over this paper.

  16. Monitoring System For Improving Radiation Safety Management

    International Nuclear Information System (INIS)

    Osovizky, A.; Paran, J.; Tal, N.; Ankry, N.; Ashkenazi, B.; Tirosh, D.; Marziano, R.; Chisin, R.

    1999-01-01

    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

  17. Nuclear safety activities in SR Slovenia in 1985

    International Nuclear Information System (INIS)

    1986-09-01

    Currently Yugoslavia has one 632 MWe nuclear power plant of PWR design, located at Krsko in the Socialist Republic of Slovenia. NPP Krsko, which is a two-loop plant, started power operation in 1981. In general, reactor safety activities in SR Slovenia are mostly related to upgrading the safety of our NPP Krsko and to develop capabilities to be used for the future units. This report presents safety related organizations in SR Slovenia and their activities performed in 1985. (author)

  18. Nuclear safety activities in SR Slovenia in 1985

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1986-09-15

    Currently Yugoslavia has one 632 MWe nuclear power plant of PWR design, located at Krsko in the Socialist Republic of Slovenia. NPP Krsko, which is a two-loop plant, started power operation in 1981. In general, reactor safety activities in SR Slovenia are mostly related to upgrading the safety of our NPP Krsko and to develop capabilities to be used for the future units. This report presents safety related organizations in SR Slovenia and their activities performed in 1985. (author)

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

    International Nuclear Information System (INIS)

    Maeda, Yukimoto; Kashimura, Youichi; Suzuki, Toshiaki; Isozaki, Kazunori; Hoshiba, Hideaki; Kitamura, Ryoichi; Nakano, Tomoyuki; Takamatsu, Misao; Sekine, Takashi

    2005-02-01

    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)

  20. Qualitative safety analysis in accelerator based systems

    International Nuclear Information System (INIS)

    Sarkar, P.K.; Chowdhury, Lekha M.

    2006-01-01

    In recent developments connected to high energy and high current accelerators, the accelerator driven systems (ADS) and the Radioactive Ion Beam (RIB) facilities come in the forefront of application. For medical and industrial applications high current accelerators often need to be located in populated areas. These facilities pose significant radiological hazard during their operation and accidental situations. We have done a qualitative evaluation of radiological safety analysis using the probabilistic safety analysis (PSA) methods for accelerator-based systems. The major contribution to hazard comes from a target rupture scenario in both ADS and RIB facilities. Other significant contributors to hazard in the facilities are also discussed using fault tree and event tree methodologies. (author)

  1. A Microbial Assessment Scheme to measure microbial performance of Food Safety Management Systems

    NARCIS (Netherlands)

    Jacxsens, L.; Kussaga, J.; Luning, P.A.; Spiegel, van der M.; Devlieghere, F.; Uyttendaele, M.

    2009-01-01

    A Food Safety Management System (FSMS) implemented in a food processing industry is based on Good Hygienic Practices (GHP), Hazard Analysis Critical Control Point (HACCP) principles and should address both food safety control and assurance activities in order to guarantee food safety. One of the

  2. Optimized Evaluation System to Athletic Food Safety

    OpenAIRE

    Shanshan Li

    2015-01-01

    This study presented a new method of optimizing evaluation function in athletic food safety information programming by particle swarm optimization. The process of food information evaluation function is to automatically adjust these parameters in the evaluation function by self-optimizing method accomplished through competition, which is a food information system plays against itself with different evaluation functions. The results show that the particle swarm optimization is successfully app...

  3. Autonomous Highway Systems Safety and Security

    OpenAIRE

    Sajjad, Imran

    2017-01-01

    Automated vehicles are getting closer each day to large-scale deployment. It is expected that self-driving cars will be able to alleviate traffic congestion by safely operating at distances closer than human drivers are capable of and will overall improve traffic throughput. In these conditions, passenger safety and security is of utmost importance. When multiple autonomous cars follow each other on a highway, they will form what is known as a cyber-physical system. In a general setting, t...

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

    International Nuclear Information System (INIS)

    Perrotta, J.A.; Boado Magan, H.J.

    2003-01-01

    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)

  5. Safer Systems: A NextGen Aviation Safety Strategic Goal

    Science.gov (United States)

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

    2008-01-01

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

  6. Occupational Safety and Health Management System (OSHMS)

    International Nuclear Information System (INIS)

    Shyen, A.K.S.; Mohd Khairul Hakimin; Manisah Saedon

    2011-01-01

    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)

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

    DEFF Research Database (Denmark)

    Andkjær, Søren; Arvidsen, Jan

    2015-01-01

    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...... 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 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 boat...

  8. THE FORMATION OF THE CONTOUR OF THE DOCUMENTED AND REAL FLIGHT SAFETY IN THE SYSTEM OF THE INFORMATION PROVISION OF SAFETY OF FLIGHTS

    Directory of Open Access Journals (Sweden)

    B. I. Bachkalo

    2015-01-01

    Full Text Available The article discusses the principles and mechanisms of formation of the contour of the real safety of flights and contour of the documented safety, allowing us to obtain information to control fligh safety. The proposed approach can be used in the algorithms of active on-board flight safety management system for the implementation of information support to the crew in flight and automatic control of flight safety.

  9. The Management System for Nuclear Installations Safety Guide

    International Nuclear Information System (INIS)

    2009-01-01

    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

  10. The Management System for Nuclear Installations. Safety Guide (Spanish Edition)

    International Nuclear Information System (INIS)

    2017-01-01

    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

  11. A tool to diagnose context riskiness in view of food safety activities and microbiological safety output

    NARCIS (Netherlands)

    Luning, P.A.; Marcelis, W.J.; Boekel, van M.A.J.S.; Rovira, J.; Uyttendaele, M.; Jacxsens, L.

    2011-01-01

    Stakeholders entail increasing demands on food safety management systems (FSMS) stimulating ongoing efforts of companies to progress to more advanced systems. However, the actual microbiological food safety (FS) output is not only a result of the performance of an FSMS, but it also depends on the

  12. ESSAA: Embedded system safety analysis assistant

    Science.gov (United States)

    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.

  13. Home electrical system safety in Italy

    Energy Technology Data Exchange (ETDEWEB)

    Auditor,

    1990-06-01

    Italy, amongst the industrialized countries, has the highest mortality rate due to accidents associated with the improper use or maintenance of home electrical systems. The increasing use of domestic electrical appliances has raised the risk of accidents, especially in homes equipped with out-dated, low-capacity electrical plants and worn wiring. Within this context, this paper reports on the results of survey to establish the worthiness and type of electrical systems in use in a sample of 1,000 residential buildings. The paper then assesses the efficacy of recent normatives designed to increase the safety and efficiency of home electrical installations.

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

    International Nuclear Information System (INIS)

    Wahlstroem, B.; Gunsell, L.

    1998-03-01

    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)

  15. Safety testing for LHC access system

    CERN Document Server

    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.

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

    International Nuclear Information System (INIS)

    Susnik, J.

    1987-06-01

    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)

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

    Energy Technology Data Exchange (ETDEWEB)

    Susnik, J [Inst. Jozef Stefan, Ljubljana (Slovenia)

    1987-06-15

    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)

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

    Science.gov (United States)

    Hill, Janice; Victor, Daniel

    2008-01-01

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

  19. Examining the Relationship Between Safety Management System Implementation and Safety Culture in Collegiate Flight Schools

    OpenAIRE

    Robertson, Michael F

    2018-01-01

    Safety management systems (SMS) are becoming the industry standard for safety management throughout the aviation industry. As the Federal Aviation Administration continues to mandate SMS for different segments, the assessment of an organization’s safety culture becomes more important. An SMS can facilitate the development of a strong aviation safety culture. This study describes how safety culture and SMS are integrated. The purpose of this study was to examine the relationship between an ...

  20. Total Quality Management and the System Safety Secretary

    Science.gov (United States)

    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.

  1. Integrated environment, safety, and health management system description

    International Nuclear Information System (INIS)

    Zoghbi, J. G.

    2000-01-01

    The Integrated Environment, Safety, and Health Management System Description that is presented in this document describes the approach and management systems used to address integrated safety management within the Richland Environmental Restoration Project

  2. Development of Safety Assessment Information System (SAIS)

    Energy Technology Data Exchange (ETDEWEB)

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

    2007-10-15

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

  3. Development of Safety Assessment Information System (SAIS)

    International Nuclear Information System (INIS)

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

    2007-01-01

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

  4. Selection and verification of safety parameters in safety parameter display system for nuclear power plants

    International Nuclear Information System (INIS)

    Zhang Yuangfang

    1992-02-01

    The method and results for safety parameter selection and its verification in safety parameter display system of nuclear power plants are introduced. According to safety analysis, the overall safety is divided into six critical safety functions, and a certain amount of safety parameters which can represent the integrity degree of each function and the causes of change are strictly selected. The verification of safety parameter selection is carried out from the view of applying the plant emergency procedures and in the accident man oeuvres on a full scale nuclear power plant simulator

  5. 75 FR 42818 - Agency Information Collection; Activity Under OMB Review; Collection of Safety Culture Data for...

    Science.gov (United States)

    2010-07-22

    ... Collection; Activity Under OMB Review; Collection of Safety Culture Data for Program Evaluation AGENCY... . SUPPLEMENTARY INFORMATION: Title: Collection of Safety Culture Data for Program Evaluation. Type of Request... data on the nation's transportation system is an important component of BTS' responsibility to the...

  6. Benefits of a systematic approach to maintenance for safety and safety related systems

    International Nuclear Information System (INIS)

    Dam, R.F.; Ayazzudin, S.; Nickerson, J.H.

    2003-01-01

    integration of component maintenance, surveillance, and inspection (MSI) strategies. These strategies can be tailored to mitigate risk in combination with the most optimal operational approach. This becomes particularly valuable when considering the operation of redundant components, such as normally found in safety systems. The optimal approach is not always obvious. The answer lies in understanding the relative risk of different options and the cost of applying the strategy. The relative risk is by definition related to the ultimate reliability of the component. This paper considers the application of Systematic Assessment of Maintenance (SAM) to standby safety and safety related systems. Recently completed studies provide useful insight into the important value added of the systematic assessment approach for these systems. The paper considers how the results of the SAM process 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 with a well integrated plant culture. (author)

  7. SAFETY

    CERN Multimedia

    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...

  8. Safety Analysis for Power Reactor Protection System

    International Nuclear Information System (INIS)

    Eisawy, E.A.; Sallam, H.

    2012-01-01

    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.

  9. Socio-technological study for establishing comprehensive nuclear safety system

    International Nuclear Information System (INIS)

    Furuta, Kazuo; Kanno, Taro; Yagi, Ekou; Shuto, Yuki

    2003-01-01

    This paper presents an overview and preliminary results of a research project on social-technology for nuclear safety, which started in October 2001. In particular, emergency response preparedness against nuclear disaster and consensus development will be discussed. The architecture of an emergency response simulator will be given, which is for assessing design of disaster prevention systems. A conceptual model of evacuation behavior of a resident has been constructed from analysis of past disaster cases. As for consensus development, deliberation spaces of actual committee meetings were constructed by analyzing transcripts of the meetings based on an opinion schema. A model of consensus development process has been proposed from the traces of participants' opinions over the deliberation spaces. Such a socio-technological approach will be useful not only for nuclear safety but also for safety of non-nuclear domains and human activities of a high hazard potential; it is expected to contribute to establishing risk-aware society of the future. (author)

  10. Development of Network Protocol for the Integrated Safety System

    Energy Technology Data Exchange (ETDEWEB)

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

    2007-06-15

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

  11. Development of Network Protocol for the Integrated Safety System

    International Nuclear Information System (INIS)

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

    2007-06-01

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

  12. Safety program considerations for space nuclear reactor systems

    International Nuclear Information System (INIS)

    Cropp, L.O.

    1984-08-01

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

  13. Safety systems and safety analysis of the Qinshan phase III CANDU nuclear power plant

    International Nuclear Information System (INIS)

    Cai Jianping; Shen Sen; Barkman, N.

    1999-01-01

    The author introduces the Canadian nuclear reactor safety philosophy and the Qinshan Phase III CANDU NPP safety systems and safety analysis, which are designed and performed according to this philosophy. The concept of 'defence-in-depth' is a key element of the Canadian nuclear reactor safety philosophy. The design concepts of redundancy, diversity, separation, equipment qualification, quality assurance, and use of appropriate design codes and standards are adopted in the design. Four special safety systems as well as a set of reliable safety support systems are incorporated in the design of Qinshan phase III CANDU for accident mitigation. The assessment results for safety systems performance show that the fundamental safety criteria for public dose, and integrity of fuel, channels and the reactor building, are satisfied

  14. A review of the nuclear safety activities in Italy

    International Nuclear Information System (INIS)

    Merelli, A.

    1989-01-01

    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

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

    Science.gov (United States)

    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.

  16. FURNAS activities in safety and quality assurance

    International Nuclear Information System (INIS)

    Dezordi, W.L.; Correa Filho, S.M.; Sacco, W.; Morais, L.H.G. de

    1980-01-01

    The aspects involved in the quality assurance performed by FURNAS for Nuclear Power Plant - Angra Unit I, are shown. Furnas' responsabilities in the licensing regarding reactor safety are also discussed. A summary of the computer codes used in the licensing process is given. (e.G.) [pt

  17. Status of generic actions items and safety analysis system of PHWR

    Energy Technology Data Exchange (ETDEWEB)

    Park, Joo Hwan; Min, Byung Joo

    2001-05-01

    This report described the review results of a GAIs(Generic Action Item) currently issued on safety analysis of PHWR(Pressurized Heavy Water Reactor) and the research activities and positions to solve the GAIs in each country which possess PHWRs. eviewing the Final Safety Analysis Report for Wolsong-2/3/4 Units, the safety analysis methodology, classification for accident scenarios, safety analysis codes, their interface, etc.. were described. From the present review report, it is intended to establish the CANDU safety analysis system by providing the better understandings and development plans for the safety analysis of PHWR. esults.

  18. Study on 'Safety qualification of process computers used in safety systems of nuclear power plants'

    International Nuclear Information System (INIS)

    Bertsche, K.; Hoermann, E.

    1991-01-01

    The study aims at developing safety standards for hardware and software of computer systems which are increasingly used also for important safety systems in nuclear power plants. The survey of the present state-of-the-art of safety requirements and specifications for safety-relevant systems and, additionally, for process computer systems has been compiled from national and foreign rules. In the Federal Republic of Germany the KTA safety guides and the BMI/BMU safety criteria have to be observed. For the design of future computer-aided systems in nuclear power plants it will be necessary to apply the guidelines in [DIN-880] and [DKE-714] together with [DIN-192]. With the aid of a risk graph the various functions of a system, or of a subsystem, can be evaluated with regard to their significance for safety engineering. (orig./HP) [de

  19. System code improvements for modelling passive safety systems and their validation

    Energy Technology Data Exchange (ETDEWEB)

    Buchholz, Sebastian; Cron, Daniel von der; Schaffrath, Andreas [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH, Garching (Germany)

    2016-11-15

    GRS has been developing the system code ATHLET over many years. Because ATHLET, among other codes, is widely used in nuclear licensing and supervisory procedures, it has to represent the current state of science and technology. New reactor concepts such as Generation III+ and IV reactors and SMR are using passive safety systems intensively. The simulation of passive safety systems with the GRS system code ATHLET is still a big challenge, because of non-defined operation points and self-setting operation conditions. Additionally, the driving forces of passive safety systems are smaller and uncertainties of parameters have a larger impact than for active systems. This paper addresses the code validation and qualification work of ATHLET on the example of slightly inclined horizontal heat exchangers, which are e. g. used as emergency condensers (e. g. in the KERENA and the CAREM) or as heat exchanger in the passive auxiliary feed water systems (PAFS) of the APR+.

  20. JRC-IE's research of safety of Gen IV systems

    International Nuclear Information System (INIS)

    Tsige-Tamirat, H.; Ranguelova, V.; Feutterer, M.; Ammirabile, L.; Carlsson, J.; D'Agata, E.; Laurie, M.; Magallon, D.

    2010-01-01

    The Institute for Energy (IE), one of the seven scientific Institutes of the Joint Research Centre (JRC) of the European Commission, has the mission to provide scientific and technical support for the conception, development, implementation and monitoring of community policies related to energy. To accomplish its mission, IE performs research in the areas of renewable energies, safety and sustainability of nuclear energy for current and future reactor systems, energy technic/economic assessment, and security of energy supply. The Generation IV International Forum (GIF) is a cooperative international endeavour organized to carry out R and D needed to establish the feasibility and performance capabilities of the next generation nuclear energy systems and support the progress towards their realization. The EU, represented by EURATOM and with the JRC as implementing agent, is working together with other GIF partners to perform pre-competitive R and D on key technologies to be implemented in future nuclear systems. IE is engaged in experimental research, simulation and modeling, scientific, feasibility and engineering studies on innovative nuclear reactor systems needed to support the EURATOM contribution to GEN IV initiative, in particular in assessment of innovative fuels and materials, development of new reactor core concepts and safety solutions and knowledge management and preservation. IE's research activities on Generation IV reactor systems are focused on the assessment of the potential of such systems to meet long term EU energy needs with respect to economical advantages, enhanced safety, sustainability, and proliferation resistance. IE participates in international collaborations and has bilateral research cooperation both with European and non-European partners. This paper gives an overview of IE's current research activities on the Gen IV reactor systems related to safety. (authors)

  1. A reliability assessment methodology for the VHTR passive safety system

    International Nuclear Information System (INIS)

    Lee, Hyungsuk; Jae, Moosung

    2014-01-01

    The passive safety system of a VHTR (Very High Temperature Reactor), which has recently attracted worldwide attention, is currently being considered for the design of safety improvements for the next generation of nuclear power plants in Korea. The functionality of the passive system does not rely on an external source of an electrical support system, but on the intelligent use of natural phenomena. Its function involves an ultimate heat sink for a passive secondary auxiliary cooling system, especially during a station blackout such as the case of the Fukushima Daiichi reactor accidents. However, it is not easy to quantitatively evaluate the reliability of passive safety for the purpose of risk analysis, considering the existing active system failure since the classical reliability assessment method cannot be applied. Therefore, we present a new methodology to quantify the reliability based on reliability physics models. This evaluation framework is then applied to of the conceptually designed VHTR in Korea. The Response Surface Method (RSM) is also utilized for evaluating the uncertainty of the maximum temperature of nuclear fuel. The proposed method could contribute to evaluating accident sequence frequency and designing new innovative nuclear systems, such as the reactor cavity cooling system (RCCS) in VHTR to be designed and constructed in Korea.

  2. Quality and safety implications of emergency department information systems.

    Science.gov (United States)

    Farley, Heather L; Baumlin, Kevin M; Hamedani, Azita G; Cheung, Dickson S; Edwards, Michael R; Fuller, Drew C; Genes, Nicholas; Griffey, Richard T; Kelly, John J; McClay, James C; Nielson, Jeff; Phelan, Michael P; Shapiro, Jason S; Stone-Griffith, Suzanne; Pines, Jesse M

    2013-10-01

    The Health Information Technology for Economic and Clinical Health Act of 2009 and the Centers for Medicare & Medicaid Services "meaningful use" incentive programs, in tandem with the boundless additional requirements for detailed reporting of quality metrics, have galvanized hospital efforts to implement hospital-based electronic health records. As such, emergency department information systems (EDISs) are an important and unique component of most hospitals' electronic health records. System functionality varies greatly and affects physician decisionmaking, clinician workflow, communication, and, ultimately, the overall quality of care and patient safety. This article is a joint effort by members of the Quality Improvement and Patient Safety Section and the Informatics Section of the American College of Emergency Physicians. The aim of this effort is to examine the benefits and potential threats to quality and patient safety that could result from the choice of a particular EDIS, its implementation and optimization, and the hospital's or physician group's approach to continuous improvement of the EDIS. Specifically, we explored the following areas of potential EDIS safety concerns: communication failure, wrong order-wrong patient errors, poor data display, and alert fatigue. Case studies are presented that illustrate the potential harm that could befall patients from an inferior EDIS product or suboptimal execution of such a product in the clinical environment. The authors have developed 7 recommendations to improve patient safety with respect to the deployment of EDISs. These include ensuring that emergency providers actively participate in selection of the EDIS product, in the design of processes related to EDIS implementation and optimization, and in the monitoring of the system's ongoing success or failure. Our recommendations apply to emergency departments using any type of EDIS: custom-developed systems, best-of-breed vendor systems, or enterprise systems

  3. Does perceived neighborhood walkability and safety mediate the association between education and meeting physical activity guidelines?

    Science.gov (United States)

    Pratt, Michael; Yin, Shaoman; Soler, Robin; Njai, Rashid; Siegel, Paul Z; Liao, Youlian

    2015-04-09

    The role of neighborhood walkability and safety in mediating the association between education and physical activity has not been quantified. We used data from the 2010 and 2012 Communities Putting Prevention to Work Behavioral Risk Factor Surveillance System and structural equation modeling to estimate how much of the effect of education level on physical activity was mediated by perceived neighborhood walkability and safety. Neighborhood walkability accounts for 11.3% and neighborhood safety accounts for 6.8% of the effect. A modest proportion of the important association between education and physical activity is mediated by perceived neighborhood walkability and safety, suggesting that interventions focused on enhancing walkability and safety could reduce the disparity in physical activity associated with education level.

  4. Safety-Critical Java for Embedded Systems

    DEFF Research Database (Denmark)

    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...

  5. Investigation of the operatability of safety systems

    International Nuclear Information System (INIS)

    Riedle, K.

    1982-01-01

    The requirements to the safety systems of a nuclear power plant result from the protective aims and the postulated incidents. These requirements are satisfied also during an accident if they are laid out for that load case. The evidence (by analyses or experiments or combination of both) consists of the steps determination of the load, determination of the resulting stress of the components, and comparison with the permitted limiting values. The author gives several examples for typical evidences of operationability. (orig./HP) [de

  6. The WIPP transportation system: Dedicated to safety

    International Nuclear Information System (INIS)

    Ward, T.; McFadden, M.

    1993-01-01

    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''

  7. Intelligent monitoring-based safety system of massage robot

    Institute of Scientific and Technical Information of China (English)

    胡宁; 李长胜; 王利峰; 胡磊; 徐晓军; 邹雲鹏; 胡玥; 沈晨

    2016-01-01

    As an important attribute of robots, safety is involved in each link of the full life cycle of robots, including the design, manufacturing, operation and maintenance. The present study on robot safety is a systematic project. Traditionally, robot safety is defined as follows: robots should not collide with humans, or robots should not harm humans when they collide. Based on this definition of robot safety, researchers have proposed ex ante and ex post safety standards and safety strategies and used the risk index and risk level as the evaluation indexes for safety methods. A massage robot realizes its massage therapy function through applying a rhythmic force on the massage object. Therefore, the traditional definition of safety, safety strategies, and safety realization methods cannot satisfy the function and safety requirements of massage robots. Based on the descriptions of the environment of massage robots and the tasks of massage robots, the present study analyzes the safety requirements of massage robots; analyzes the potential safety dangers of massage robots using the fault tree tool; proposes an error monitoring-based intelligent safety system for massage robots through monitoring and evaluating potential safety danger states, as well as decision making based on potential safety danger states; and verifies the feasibility of the intelligent safety system through an experiment.

  8. Remote mobile communication in safety support system

    International Nuclear Information System (INIS)

    Inagaki, Kanji; Kobayashi, Hiroyuki; Hatanaka, Takahiro; Sakuma, Akira; Fukumoto, Akira; Ikeda, Jun

    1999-01-01

    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)

  9. Reliability of thermal-hydraulic passive safety systems

    International Nuclear Information System (INIS)

    D'Auria, F.; Araneo, D.; Pierro, F.; Galassi, G.

    2014-01-01

    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

  10. Software for computer based systems important to safety in nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2004-01-01

    Computer based systems are of increasing importance to safety in nuclear power plants as their use in both new and older plants is rapidly increasing. They are used both in safety related applications, such as some functions of the process control and monitoring systems, as well as in safety critical applications, such as reactor protection or actuation of safety features. The dependability of computer based systems important to safety is therefore of prime interest and should be ensured. With current technology, it is possible in principle to develop computer based instrumentation and control systems for systems important to safety that have the potential for improving the level of safety and reliability with sufficient dependability. However, their dependability can be predicted and demonstrated only if a systematic, fully documented and reviewable engineering process is followed. Although a number of national and international standards dealing with quality assurance for computer based systems important to safety have been or are being prepared, internationally agreed criteria for demonstrating the safety of such systems are not generally available. It is recognized that there may be other ways of providing the necessary safety demonstration than those recommended here. The basic requirements for the design of safety systems for nuclear power plants are provided in the Requirements for Design issued in the IAEA Safety Standards Series.The IAEA has issued a Technical Report to assist Member States in ensuring that computer based systems important to safety in nuclear power plants are safe and properly licensed. The report provides information on current software engineering practices and, together with relevant standards, forms a technical basis for this Safety Guide. The objective of this Safety Guide is to provide guidance on the collection of evidence and preparation of documentation to be used in the safety demonstration for the software for computer based

  11. Software for computer based systems important to safety in nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2005-01-01

    Computer based systems are of increasing importance to safety in nuclear power plants as their use in both new and older plants is rapidly increasing. They are used both in safety related applications, such as some functions of the process control and monitoring systems, as well as in safety critical applications, such as reactor protection or actuation of safety features. The dependability of computer based systems important to safety is therefore of prime interest and should be ensured. With current technology, it is possible in principle to develop computer based instrumentation and control systems for systems important to safety that have the potential for improving the level of safety and reliability with sufficient dependability. However, their dependability can be predicted and demonstrated only if a systematic, fully documented and reviewable engineering process is followed. Although a number of national and international standards dealing with quality assurance for computer based systems important to safety have been or are being prepared, internationally agreed criteria for demonstrating the safety of such systems are not generally available. It is recognized that there may be other ways of providing the necessary safety demonstration than those recommended here. The basic requirements for the design of safety systems for nuclear power plants are provided in the Requirements for Design issued in the IAEA Safety Standards Series.The IAEA has issued a Technical Report to assist Member States in ensuring that computer based systems important to safety in nuclear power plants are safe and properly licensed. The report provides information on current software engineering practices and, together with relevant standards, forms a technical basis for this Safety Guide. The objective of this Safety Guide is to provide guidance on the collection of evidence and preparation of documentation to be used in the safety demonstration for the software for computer based

  12. Software for computer based systems important to safety in nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2000-01-01

    Computer based systems are of increasing importance to safety in nuclear power plants as their use in both new and older plants is rapidly increasing. They are used both in safety related applications, such as some functions of the process control and monitoring systems, as well as in safety critical applications, such as reactor protection or actuation of safety features. The dependability of computer based systems important to safety is therefore of prime interest and should be ensured. With current technology, it is possible in principle to develop computer based instrumentation and control systems for systems important to safety that have the potential for improving the level of safety and reliability with sufficient dependability. However, their dependability can be predicted and demonstrated only if a systematic, fully documented and reviewable engineering process is followed. Although a number of national and international standards dealing with quality assurance for computer based systems important to safety have been or are being prepared, internationally agreed criteria for demonstrating the safety of such systems are not generally available. It is recognized that there may be other ways of providing the necessary safety demonstration than those recommended here. The basic requirements for the design of safety systems for nuclear power plants are provided in the Requirements for Design issued in the IAEA Safety Standards Series.The IAEA has issued a Technical Report to assist Member States in ensuring that computer based systems important to safety in nuclear power plants are safe and properly licensed. The report provides information on current software engineering practices and, together with relevant standards, forms a technical basis for this Safety Guide. The objective of this Safety Guide is to provide guidance on the collection of evidence and preparation of documentation to be used in the safety demonstration for the software for computer based

  13. Inspirations from Dupont Safety Management System

    Institute of Scientific and Technical Information of China (English)

    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.

  14. Modelling safety of multistate systems with ageing components

    Energy Technology Data Exchange (ETDEWEB)

    Kołowrocki, Krzysztof; Soszyńska-Budny, Joanna [Gdynia Maritime University, Department of Mathematics ul. Morska 81-87, Gdynia 81-225 Poland (Poland)

    2016-06-08

    An innovative approach to safety analysis of multistate ageing systems is presented. Basic notions of the ageing multistate systems safety analysis are introduced. The system components and the system multistate safety functions are defined. The mean values and variances of the multistate systems lifetimes in the safety state subsets and the mean values of their lifetimes in the particular safety states are defined. The multi-state system risk function and the moment of exceeding by the system the critical safety state are introduced. Applications of the proposed multistate system safety models to the evaluation and prediction of the safty characteristics of the consecutive “m out of n: F” is presented as well.

  15. Modelling safety of multistate systems with ageing components

    International Nuclear Information System (INIS)

    Kołowrocki, Krzysztof; Soszyńska-Budny, Joanna

    2016-01-01

    An innovative approach to safety analysis of multistate ageing systems is presented. Basic notions of the ageing multistate systems safety analysis are introduced. The system components and the system multistate safety functions are defined. The mean values and variances of the multistate systems lifetimes in the safety state subsets and the mean values of their lifetimes in the particular safety states are defined. The multi-state system risk function and the moment of exceeding by the system the critical safety state are introduced. Applications of the proposed multistate system safety models to the evaluation and prediction of the safty characteristics of the consecutive “m out of n: F” is presented as well.

  16. Development of digital safety system logic and control

    International Nuclear Information System (INIS)

    Nishikawa, H.; Sakamoto, H.

    1995-01-01

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

  17. Addressing firefighter safety around solar PV systems

    Energy Technology Data Exchange (ETDEWEB)

    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.

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

    Directory of Open Access Journals (Sweden)

    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.

  19. Appraisal of Fire Safety Management Systems at Educational Buildings

    Directory of Open Access Journals (Sweden)

    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.

  20. Man as a safety problem in technical systems

    International Nuclear Information System (INIS)

    Compes, P.C.; Wolff, H.A.

    1980-01-01

    Safety engineering derives its justification from the success achieved in maintaining and enlarging safety, more precisely, from activities aimed at avoiding or preventing damage caused by accidents. Man is not only affected by accidents but is also the cause of accidents, either directly or indirectly, and thus is to be regarded as the actual cause or preventer of accidents. The Second International Summer Symposium of the Society for Safety Engineering (GfS) which was held at Duesseldorf in 1980 brought into focus this aspect and the importance to be attached to the individual man and the whole mankind in the field of accident prevention. 'Man as a safety problem in technical systems' - a great and weighty field of problems, the large extent of which and the complex content of which was to be discussed by the programme with its many different contributions, on the one hand by presenting an outline as completely as possible, and on the other hand by finding further-reaching solutions for at least some problems. This was the purpose of the dialogues held between theory and practice on the one hand, and between safety engineering and, in this case, the human sciences on the other hand. (orig./RW) [de

  1. System design for shaft safety and productivity

    Energy Technology Data Exchange (ETDEWEB)

    Owen, D.; Parsons, R.; Ward, R.

    1988-03-01

    The aim of this paper is to describe the process of designing a system to improve safety and productivity in shafts. The objectives and constraints for the design were set out in official reports following a shaft accident at Markham Colliery in 1973. The problems to be solved were: to enable the shaftsmen to transfer the existing statutory code of signals efficiently from, or on top of, a conveyance anywhere in the shaft to the winding engineman and banksman at the surface: to detect the existence of slack rope or to detect that conditions have arisen that slack rope could be created and transmit this information to where action can be taken; and to allow conversations between winding engineman, banksman and shaftsman making allowances for the high level of acoustic noise in shafts. The approach adopted for slack rope monitoring was to monitor the tension in the cage suspension gear, thus measuring a first order effect. The three problems have a common element: information must be transferred through the shaft. This particular problem was solved with guided radio, using the winding rope as the transmission medium. The radio signal is coupled into the winding rope by means of fixed toroid encircling it at the cage and fixed magnetic antennas at the surface. The design of a digital transmission system for signalling and tension data is discussed. The 'top down' modular approach used in the design enabled full advantage to be taken of the opportunities for building a more reliable, safer and flexible system presented by technologies new to the shaft environment. The resultant system, the Safecom Shaft Signalling Communication and Winder Safety Monitoring System type S100, is in regular use at over 20 installations. 3 refs., 4 figs., 1 tab.

  2. Design for safety: theoretical framework of the safety aspect of BIM system to determine the safety index

    Directory of Open Access Journals (Sweden)

    Ai Lin Evelyn Teo

    2016-12-01

    Full Text Available Despite the safety improvement drive that has been implemented in the construction industry in Singapore for many years, the industry continues to report the highest number of workplace fatalities, compared to other industries. The purpose of this paper is to discuss the theoretical framework of the safety aspect of a proposed BIM System to determine a Safety Index. An online questionnaire survey was conducted to ascertain the current workplace safety and health situation in the construction industry and explore how BIM can be used to improve safety performance in the industry. A safety hazard library was developed based on the main contributors to fatal accidents in the construction industry, determined from the formal records and existing literature, and a series of discussions with representatives from the Workplace Safety and Health Institute (WSH Institute in Singapore. The results from the survey suggested that the majority of the firms have implemented the necessary policies, programmes and procedures on Workplace Safety and Health (WSH practices. However, BIM is still not widely applied or explored beyond the mandatory requirement that building plans should be submitted to the authorities for approval in BIM format. This paper presents a discussion of the safety aspect of the Intelligent Productivity and Safety System (IPASS developed in the study. IPASS is an intelligent system incorporating the buildable design concept, theory on the detection, prevention and control of hazards, and the Construction Safety Audit Scoring System (ConSASS. The system is based on the premise that safety should be considered at the design stage, and BIM can be an effective tool to facilitate the efforts to enhance safety performance. IPASS allows users to analyse and monitor key aspects of the safety performance of the project before the project starts and as the project progresses.

  3. Safety Culture Improvement Activities of YGN 3 and 4

    International Nuclear Information System (INIS)

    Cho, Il Hoon

    2006-01-01

    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)

  4. The detector safety system for LHC experiments

    CERN Document Server

    Schmeling, Sascha; Lüders, S; Morpurgo, Giulio

    2004-01-01

    The Detector Safety System (DSS), currently being developed at CERN under the auspices of the Joint Controls Project (JCOP), will be responsible for assuring the protection of equipment for the four Large Hadron Collider (LHC)**1 experiments. Thus, the DSS will require a high degree of both availability and reliability. After evaluation of various possible solutions, a prototype is being built based on a redundant Siemens PLC**2 front-end, to which the safety- critical part of the DSS task is delegated. This is then supervised by a PVSS**3 SCADA**4 system via an OPC**5 server. The PLC front-end is capable of running autonomously and of automatically taking predefined protective actions whenever required. The supervisory layer provides the operator with a status display and with limited online reconfiguration capabilities. Configuration of the code running in the PLCs will be completely data driven via the contents of a "configuration database." Thus, the DSS can easily adapt to the different and constantly ev...

  5. The safety activities of the ICAO and the IAEA

    International Nuclear Information System (INIS)

    Franzen, L.F.; Iansiti, E.

    1983-01-01

    The article presents a comparative analysis of the safety activities of the IAEA and the International Civil Aviation Organization (ICAO), from which possible solutions for the problems faced by the nuclear community are suggested

  6. Developing and maintaining national food safety control systems ...

    African Journals Online (AJOL)

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

  7. 49 CFR 659.19 - System safety program plan: contents.

    Science.gov (United States)

    2010-10-01

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

  8. Model-based safety architecture framework for complex systems

    NARCIS (Netherlands)

    Schuitemaker, Katja; Rajabali Nejad, Mohammadreza; Braakhuis, J.G.; Podofillini, Luca; Sudret, Bruno; Stojadinovic, Bozidar; Zio, Enrico; Kröger, Wolfgang

    2015-01-01

    The shift to transparency and rising need of the general public for safety, together with the increasing complexity and interdisciplinarity of modern safety-critical Systems of Systems (SoS) have resulted in a Model-Based Safety Architecture Framework (MBSAF) for capturing and sharing architectural

  9. 23 CFR 973.212 - Indian lands safety management system (SMS).

    Science.gov (United States)

    2010-04-01

    ... implementation of public information and education activities on safety needs, programs, and countermeasures... 23 Highways 1 2010-04-01 2010-04-01 false Indian lands safety management system (SMS). 973.212... HIGHWAYS MANAGEMENT SYSTEMS PERTAINING TO THE BUREAU OF INDIAN AFFAIRS AND THE INDIAN RESERVATION ROADS...

  10. Safety Oversight of Decommissioning Activities at DOE Nuclear Sites

    International Nuclear Information System (INIS)

    Zull, Lawrence M.; Yeniscavich, William

    2008-01-01

    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

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

    Energy Technology Data Exchange (ETDEWEB)

    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

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

    International Nuclear Information System (INIS)

    Haapanen, P.; Korhonen, J.; Pulkkinen, U.

    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. Many of the

  13. Examining the Relationship between Safety Management System Implementation and Safety Culture in Collegiate Flight Schools

    Science.gov (United States)

    Robertson, Mike Fuller

    2017-01-01

    Safety Management Systems (SMS) are becoming the industry standard for safety management throughout the aviation industry. As the Federal Aviation Administration (FAA) continues to mandate SMS for different segments, the assessment of an organization's safety culture becomes more important. An SMS can facilitate the development of a strong…

  14. IAEA activity related to safety of nuclear desalination

    International Nuclear Information System (INIS)

    Gasparini, M.

    2000-01-01

    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)

  15. Research on Integration of NPP Operational Safety Management Performance Systems

    International Nuclear Information System (INIS)

    Chi, Miao; Shi, Liping

    2014-01-01

    The operational safety management of Nuclear Power Plants demands systematic planning and integrated control. NPPs are following the well-developed safety indicator systems proposed by IAEA Operational Safety Performance Indicator Programme, NRC Reactor Oversight Process or the other institutions. Integration of the systems is proposed to benefiting from the advantages of both systems and avoiding improper application into the real world. The authors analyzed the possibility and necessity for system integration, and propose an indicator system integrating method

  16. CEC activities in the field of LMFBR safety

    International Nuclear Information System (INIS)

    Balz, W.; Finzi, S.; Klersy, R.

    1976-01-01

    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

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

    International Nuclear Information System (INIS)

    Shi Jin; Chen Song; Liu Jingquan

    2013-01-01

    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)

  18. Advanced safety management systems for maintenance of pipeline integrity

    International Nuclear Information System (INIS)

    Borysiewicz, M.; Potempski, S.

    2005-01-01

    One of the duties of the pipeline's operator is to introduce means for protection of human safety and the environment. This should be reflected in preparation of comprehensive Risk Management System with its key element Activity Programme for Management of Pipeline Integrity. In the paper such programme has been described taking into account law regulations and practical activities undertaken in technologically advanced countries (mainly USA and EU), where such solutions are implemented in routine operations. Possible solutions of realization of all elements of the programme, as well as information on utilization of computer aided support have been also included. (authors)

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

    International Nuclear Information System (INIS)

    Kato, S.

    2001-01-01

    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)

  20. Assessment of Safety Standards for Automotive Electronic Control Systems

    Science.gov (United States)

    2016-06-01

    This report summarizes the results of a study that assessed and compared six industry and government safety standards relevant to the safety and reliability of automotive electronic control systems. These standards include ISO 26262 (Road Vehicles - ...

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

    International Nuclear Information System (INIS)

    Fukui, Hirokazu; Sugiman, Toshio

    2007-01-01

    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)

  2. Does Perceived Neighborhood Walkability and Safety Mediate the Association Between Education and Meeting Physical Activity Guidelines?

    OpenAIRE

    Pratt, Michael; Yin, Shaoman; Soler, Robin; Njai, Rashid; Siegel, Paul Z.; Liao, Youlian

    2015-01-01

    The role of neighborhood walkability and safety in mediating the association between education and physical activity has not been quantified. We used data from the 2010 and 2012 Communities Putting Prevention to Work Behavioral Risk Factor Surveillance System and structural equation modeling to estimate how much of the effect of education level on physical activity was mediated by perceived neighborhood walkability and safety. Neighborhood walkability accounts for 11.3% and neighborhood safet...

  3. Probabilistic safety assessment activities at Ignalina NPP

    International Nuclear Information System (INIS)

    Bagdonas, A.

    1999-01-01

    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

  4. Safety Evaluation Approach with Security Controls for Safety I and C Systems on Nuclear Power Plants

    International Nuclear Information System (INIS)

    Kim, D. H.; Jeong, S. Y.; Kim, Y. M.; Park, H. S.; Lee, M. S.; Kim, T. H.

    2016-01-01

    This paper addresses concepts of safety and security and relations between them for assessing effects of security features in safety systems. Also, evaluation approach for avoiding confliction with safety requirements and cyber security features which may be adopted in safety-related digital I and C system will be described. In this paper, safety-security life cycle model based confliction avoidance method was proposed to evaluate the effects when the cyber security control features are implemented in the safety I and C system. Also, safety effect evaluation results using the proposed evaluation method were described. In case of technical security controls, many of them are expected to conflict with safety requirements, otherwise operational and managerial controls are not relatively. Safety measures and cyber security measures for nuclear power plants should be implemented not to conflict with one another. Where safety function and security features are both required within the systems, and also where security features are implemented within safety systems, they should be justified

  5. Safety Evaluation Approach with Security Controls for Safety I and C Systems on Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Kim, D. H.; Jeong, S. Y.; Kim, Y. M.; Park, H. S. [KINS, Daejeon (Korea, Republic of); Lee, M. S.; Kim, T. H. [Formal Works Inc., Seoul (Korea, Republic of)

    2016-05-15

    This paper addresses concepts of safety and security and relations between them for assessing effects of security features in safety systems. Also, evaluation approach for avoiding confliction with safety requirements and cyber security features which may be adopted in safety-related digital I and C system will be described. In this paper, safety-security life cycle model based confliction avoidance method was proposed to evaluate the effects when the cyber security control features are implemented in the safety I and C system. Also, safety effect evaluation results using the proposed evaluation method were described. In case of technical security controls, many of them are expected to conflict with safety requirements, otherwise operational and managerial controls are not relatively. Safety measures and cyber security measures for nuclear power plants should be implemented not to conflict with one another. Where safety function and security features are both required within the systems, and also where security features are implemented within safety systems, they should be justified.

  6. Innovation research on the safety supervision system of nuclear and radiation safety in Jiangsu province

    International Nuclear Information System (INIS)

    Zhang Qihong; Lu Jigen; Zhang Ping; Wang Wanping; Dai Xia

    2012-01-01

    As the rapid development of nuclear technology, the safety supervision of nuclear and radiation becomes very important. The safety radiation frame system should be constructed, the safety super- vision ability for nuclear and radiation should be improved. How to implement effectively above mission should be a new subject of Provincial environmental protection department. Through investigating the innovation of nuclear and radiation supervision system, innovation of mechanism, innovation of capacity, innovation of informatization and so on, the provincial nuclear and radiation safety supervision model is proposed, and the safety framework of nuclear and radiation in Jiangsu is elementally established in the paper. (authors)

  7. Safety in wastewater treatment: the pure oxygen system

    International Nuclear Information System (INIS)

    Giagnoni, L.

    1998-01-01

    Though the active sludge process represent, nowadays, the main reference system referring to installations for wastewater treatments, nevertheless systems that exploit the pure oxygen properties constitute an alternative method to the traditional cycle. The following essay is divided into two parts: the first one deals with the fundamental concepts related to the active sludge process and to the alternative system proposed, mentioned before, and includes a short account of the functional characteristics and a brief comparison with traditional methods; the second part represents the head corpus of the work and deals with the problems related to the safety with particular reference to the risk of an explosion meanwhile the process. Moreover, it's drawn attention to the fundamental role of security systems that, nowadays, get frequently used in such kind of installations. On this subject, furthermore, it's pointed out the great importance of the whole preliminary treatments in the planning phase, with particular reference to the processes used for stripping [it

  8. Stakeholder Safety in Information Systems Research

    Directory of Open Access Journals (Sweden)

    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.

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

    International Nuclear Information System (INIS)

    Dahll, Gustav; Liwang, Bo; Wainwright, Norman

    2006-01-01

    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 questions (Q) and a

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

    Energy Technology Data Exchange (ETDEWEB)

    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

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

    International Nuclear Information System (INIS)

    1986-01-01

    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

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

  13. Short course on system safety analysis

    International Nuclear Information System (INIS)

    Sudmann, R.H.

    1992-01-01

    This course provides and introduction to methods generally used in safety analysis and accident investigation. It is a non-mathematical approach, directed toward a casual user. The participant will learn techniques allowing them to dissect a system or incident in order identify real or potential safety problems. These techniques will be applied to analyze events which have occurred within DOE facilities. As a manager or staff person with general oversight responsibilities, the participant should gain an awareness of the big picture and not just ''dig for facts.'' This can be accomplished by being alert and responsive to the atmosphere and condition of the plant; mood and impression of the worker and the behavioral climate. The techniques taught in the course can be used to identify critical areas or indicators. These indicators will signal problems before the ''facts'' will. Analysis techniques taught are used to gauge the breadth of the ''forest'' and not necessarily to identify the trees. For this course includes a technical background with experience in a chemical processing operations and a knowledge of basic chemistry and engineering is desirable. The course should help in a present or future assignment in an oversight role

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

    Science.gov (United States)

    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. Copyright © 2015 Elsevier Ltd. All rights reserved.

  15. Monitoring circuit for reactor safety systems

    Science.gov (United States)

    Keefe, Donald J.

    1976-01-01

    The ratio between the output signals of a pair of reactor safety channels is monitored. When ratio falls outside of a predetermined range, it indicates that one or more of the safety channels has malfunctioned.

  16. Monitoring circuit for reactor safety systems

    International Nuclear Information System (INIS)

    Keefe, D.J.

    1976-01-01

    The ratio between the output signals of a pair of reactor safety channels is monitored. When ratio falls outside of a predetermined range, it indicates that one or more of the safety channels has malfunctioned. 3 claims, 2 figures

  17. 78 FR 29392 - Embedded Digital Devices in Safety-Related Systems, Systems Important to Safety, and Items Relied...

    Science.gov (United States)

    2013-05-20

    ... NUCLEAR REGULATORY COMMISSION [NRC-2013-0098] Embedded Digital Devices in Safety-Related Systems, Systems Important to Safety, and Items Relied on for Safety AGENCY: Nuclear Regulatory Commission. ACTION... (NRC) is issuing for public comment Draft Regulatory Issue Summary (RIS) 2013-XX, ``Embedded Digital...

  18. The new active driving safety system ESP (Electronic Stability Program) developed by Mercedes Benz; Das neue aktive Fahrsicherheitssystem ESP (Elektronisches-Stabilitaets-Programm) von Mercedes-Benz

    Energy Technology Data Exchange (ETDEWEB)

    Paul, J. [Mercedes-Benz AG, Stuttgart (Germany); Klinkner, W. [Mercedes-Benz AG, Stuttgart (Germany); Mueller, A. [Mercedes-Benz AG, Stuttgart (Germany)

    1995-12-31

    The new electronic stability program (ESP) offered by Mercedes-Benz as a world novelty in March 1995 is the consequent further development of the anti-lock braking system and the anti-slip control. An improved assessment of the handling properties by a steering wheel sensor, a yaw velocity sensor, a brake pressure sensor and a hydraulic system that brakes each wheel individually and is controlled by a complex logic allow the supervision and the active control of the cross-dynamic handling properties up to limiting ranges. The handling of the vehicle in critical situations (e.g. strong oversteering or understeering) has been considerably improved. (orig.) [Deutsch] Das neue elektronische-Stabilitaets-Programm (ESP), von Mercedes-Benz ab Maerz 1995 als Weltneuheit angeboten, stellt eine konsequente Weiterentwicklung des Antiblockier-Bremssystems (ABS) und der Antriebsschlupfregelung (ASR) dar. Eine erweiterte Fahrzustandserfassung durch Lenkradwinkel-, Giergeschwindigkeit- und Bremsdrucksensor, eine Hydraulik, die jedes Rad individuell abbremsen kann, angesteuert durch eine komplexe Regelungslogik, erlauben erstmals eine Ueberwachung und aktive Regelung des querdynamischen Fahrzustands bis in den Grenzbereich. Die Beherrschbarkeit des Fahrzeugs wird in kritischen Situationen (z.B. starkes Ueber- oder Untersteuern) entscheidend verbessert. (orig.)

  19. System and safety studies of accelerator driven systems for transmutation. Annual report 2007

    International Nuclear Information System (INIS)

    Arzhanov, Vasily; Fokau, Andrei; Persson, Calle; Runevall, Odd; Sandberg, Nils; Tesinsky, Milan; Wallenius, Janne; Youpeng Zhang

    2008-05-01

    Within the project 'System and safety studies of accelerator driven systems for transmutation', research on design and safety of sub-critical reactors for recycling of minor actinides is performed. During 2007, the reactor physics division at KTH has calculated safety parameters for EFIT-400 with cermet fuel, permitting to start the transient safety analysis. The accuracy of different reactivity meters applied to the YALINA facility was assessed and neutron detection studies were performed. A model to address deviations from point kinetic behaviour was developed. Studies of basic radiation damage physics included calculations of vacancy formation and activation enthalpies in bcc niobium. In order to predict the oxygen potential of inert matrix fuels, a thermo-chemical model for mixed actinide oxides was implemented in a phase equilibrium code

  20. System and safety studies of accelerator driven systems for transmutation. Annual report 2007

    Energy Technology Data Exchange (ETDEWEB)

    Arzhanov, Vasily; Fokau, Andrei; Persson, Calle; Runevall, Odd; Sandberg, Nils; Tesinsky, Milan; Wallenius, Janne; Youpeng Zhang (Div. of Reactor Physics, Royal Institute of Technology, Stockholm (Sweden))

    2008-05-15

    Within the project 'System and safety studies of accelerator driven systems for transmutation', research on design and safety of sub-critical reactors for recycling of minor actinides is performed. During 2007, the reactor physics division at KTH has calculated safety parameters for EFIT-400 with cermet fuel, permitting to start the transient safety analysis. The accuracy of different reactivity meters applied to the YALINA facility was assessed and neutron detection studies were performed. A model to address deviations from point kinetic behaviour was developed. Studies of basic radiation damage physics included calculations of vacancy formation and activation enthalpies in bcc niobium. In order to predict the oxygen potential of inert matrix fuels, a thermo-chemical model for mixed actinide oxides was implemented in a phase equilibrium code

  1. 76 FR 65778 - Pipeline Safety: Information Collection Activities

    Science.gov (United States)

    2011-10-24

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No...: 12,120. Frequency of Collection: On occasion. 2. Title: Recordkeeping for Natural Gas Pipeline... investigating incidents. Affected Public: Operators of natural gas pipeline systems. Annual Reporting and...

  2. 77 FR 74275 - Pipeline Safety: Information Collection Activities

    Science.gov (United States)

    2012-12-13

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No.... These regulations require operators of hazardous liquid pipelines and gas pipelines to develop and... control room. Affected Public: Operators of both natural gas and hazardous liquid pipeline systems. Annual...

  3. A study on LAN applications in nuclear safety systems

    International Nuclear Information System (INIS)

    Kim, Sung; Lee, Young Ryul; Koo, Jun Mo; Han, Jai Bok

    1995-01-01

    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

  4. Formal specifications for safety grade systems

    International Nuclear Information System (INIS)

    Chisholm, G.H.; Smith, B.T.; Wojcik, A.S.

    1992-01-01

    The authors describe the findings of a study into the application of formal methods to the specification of a safety system for an operating nuclear reactor. They developed a formal specification that is used to verify and validate that no unsafe condition will result from action or inaction of the system. For this reason, the specification must facilitate thinking about, talking about, and implementing the system. In fact, the specification must provide a bridge between people (designers, engineers, policy makers) and diverse implementations (hardware, software, sensors, power supplies) at all levels. For a specification to serve as an effective linkage, it must have the following properties: (1) completeness, (2) conciseness, (3) unambiguity, and (4) communicativeness. In this paper they describe the development of a specification that has three properties. This development is based on the use of formal methods, i.e., methods that add mathematical rigor to the development, analysis and operation of computer systems and to applications based thereon (Neumann). They demonstrate that a specification derived from a formal basis facilitates development of the design and its subsequent verification

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

    International Nuclear Information System (INIS)

    2009-01-01

    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

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

    International Nuclear Information System (INIS)

    2009-01-01

    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 UF 6 ; (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

    International Nuclear Information System (INIS)

    2010-01-01

    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

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

    International Nuclear Information System (INIS)

    2009-01-01

    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

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

    International Nuclear Information System (INIS)

    Silver, R.; Langwell, G.; Thomas, C.; Coffing, S.

    1996-01-01

    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. Status of Safety and Environmental Activities for Inertial Fusion Energy

    International Nuclear Information System (INIS)

    Latkowski, J.F.; Reyes, S.; Cadwallader, L.C.; Sharpe, J.P.; Marshall, T.D.; Merrill, B.J.; Moore, R.L.; Petti, D.A.; Falquina, R.; Rodriguez, A.; Sanz, J.; Cabellos, O.

    2003-01-01

    Over the past several years, significant progress has been made in the analysis of safety and environmental (S and E) issues for inertial fusion energy (IFE). Detailed safety assessments have been performed for the baseline power plant concepts, as well as for a conceptual target fabrication facility. Safety analysis results are helping to drive the agenda for experiments. A survey of the S and E characteristics - both radiological and chemical - of candidate target materials has been completed. Accident initiating events have been identified and incorporated into master logic diagrams, which will be essential to the detailed safety analyses that will be needed in the future. Studies of aerosol generation and transport will have important safety implications. A Monte Carlo-based uncertainty analysis procedure has been developed for use in neutron activation calculations. Finally, waste management issues are receiving increased attention and are deserving of further discussion

  11. In vitro antitumour activity, safety testing and subcellular distribution of two poly[oxyethylene(aminophosphonate-co-H-phosphonate]s in Ehrlich ascites carcinoma and BALB/c 3T3 cell culture systems

    Directory of Open Access Journals (Sweden)

    Ani Georgieva

    2016-01-01

    Full Text Available Two polyphosphoesters containing anthracene-derived aminophosphonate and hydrophilic H-phosphonate repeating units, poly[oxyethylene(aminophosphonate-co-H-phosphonate]s (1 and 2, were tested for the in vitro antitumour activity on cell cultures derived from ascitic form of Ehrlich mammary adenocarcinoma by 3-(4,5-dimethylthiazol-2-yl-2,5-diphenyltetrazolium bromide (MTT-dye reduction assay. The in vitro safety testing of the copolymers was performed by BALB/c 3T3 neutral red uptake assay. A study on their uptake and subcellular distribution in non-tumourigenic and tumour cells was performed by means of fluorescence microscopy. Both copolymers showed significant antitumour activity towards Ehrlich ascites carcinoma (EAC cells. However, the in vitro safety testing revealed significant toxicity of polymer 2 to BALB/c 3T3 mouse embryo cells. In contrast, polymer 1 showed complete absence of cytotoxicity to BALB/c 3T3 cells. The fluorescent studies showed that the substances were diffusely distributed in the cytoplasm in both cell culture systems. As opposed to BALB/c 3T3 cells, in EAC cells, intense fluorescent signal was observed in the nuclei and in the perinuclear region. The tested polyphosphoesters are expected to act under physiological conditions as prodrugs of aminophosphonates.

  12. Role of systems safety in maintaining affordable safety in the 1980's

    International Nuclear Information System (INIS)

    Hollister, H.; Trauth, C.A. Jr.

    1979-01-01

    Historically, the Department of Energy and its predecessors have used and supported the development of systems safety programs, practices, and principles, finding them by and large adequate, effective, and managerially efficient. Today, attempts are bing made to resolve increasingly complex environmental, safety, and health problems by turning to increasingly complex and detailed regulation as the primary governmental answer. It is increasingly doubtful that such an approach will provide management of these issues and problems that is either effective or efficient. Challenge is issued to those in systems safety to develop and apply systems safety principles and practices more broadly to total operational systems and not just to hardware and to environmental and health protection and not just to safety, so that the total universe of environmental, safety, and health can be managed effectively and efficiently with encouragement of innovation and creativity, using a relatively brief and concise, but adequate, regulatory base

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

    International Nuclear Information System (INIS)

    Johanson, Gunnar; Holmberg, J.

    1994-01-01

    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

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

    International Nuclear Information System (INIS)

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

    2004-01-01

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

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

    International Nuclear Information System (INIS)

    Oliva, A.F.; Balog, G.; Parkinson, D.G.; Archinoff, G.H.

    1991-01-01

    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

  16. Passive safety systems reliability and integration of these systems in nuclear power plant PSA

    International Nuclear Information System (INIS)

    La Lumia, V.; Mercier, S.; Marques, M.; Pignatel, J.F.

    2004-01-01

    Innovative nuclear reactor concepts could lead to use passive safety features in combination with active safety systems. A passive system does not need active component, external energy, signal or human interaction to operate. These are attractive advantages for safety nuclear plant improvements and economic competitiveness. But specific reliability problems, linked to physical phenomena, can conduct to stop the physical process. In this context, the European Commission (EC) starts the RMPS (Reliability Methods for Passive Safety functions) program. In this RMPS program, a quantitative reliability evaluation of the RP2 system (Residual Passive heat Removal system on the Primary circuit) has been realised, and the results introduced in a simplified PSA (Probabilistic Safety Assessment). The scope is to get out experience of definition of characteristic parameters for reliability evaluation and PSA including passive systems. The simplified PSA, using event tree method, is carried out for the total loss of power supplies initiating event leading to a severe core damage. Are taken into account: failures of components but also failures of the physical process involved (e.g. natural convection) by a specific method. The physical process failure probabilities are assessed through uncertainty analyses based on supposed probability density functions for the characteristic parameters of the RP2 system. The probabilities are calculated by MONTE CARLO simulation coupled to the CATHARE thermalhydraulic code. The yearly frequency of the severe core damage is evaluated for each accident sequence. This analysis has identified the influence of the passive system RP2 and propose a re-dimensioning of the RP2 system in order to satisfy the safety probabilistic objectives for reactor core severe damage. (authors)

  17. Driver monitoring system for automotive safety

    Science.gov (United States)

    Lörincz, A. E.; Risteiu, M. N.; Ionica, A.; Leba, M.

    2018-01-01

    The lifestyle of a person is a very active one from all points of view. He travels great distance every day, with car or on foot. Tiredness and stress is found in every person. These can cause major problems when driving up and driving in small or big distances by car. A system developed to prevent the dangers we are prone to in these situations is very useful. System that can be used and implemented both in the production of current cars and the use of those not equipped with this system.

  18. Plutonium finishing plant safety systems and equipment list

    International Nuclear Information System (INIS)

    Bergquist, G.G.

    1995-01-01

    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

  19. Activities of the PNC Nuclear Safety Working Group

    International Nuclear Information System (INIS)

    Kato, W.Y.

    1991-01-01

    The Nuclear Safety Working Group of the Pacific Nuclear Council promotes nuclear safety cooperation among its members. Status of safety research, emergency planning, development of lists of technical experts, severe accident prevention and mitigation have been the topics of discussion in the NSWG. This paper reviews and compares the severe accident prevention and mitigation program activities in some of the areas of the Pacific Basin region based on papers presented at a special session organized by the NSWG at an ANS Topical Meeting as well as papers from other sources

  20. Nuclear power reactor safety research activities in CIAE

    International Nuclear Information System (INIS)

    Pu Shendi; Huang Yucai; Xu Hanming; Zhang Zhongyue

    1994-01-01

    The power reactor safety research activities in CIAE are briefly reviewed. The research work performed in 1980's and 1990's is mainly emphasised, which is closely related to the design, construction and licensing review of Qinshan Nuclear Power Plant and the safety review of Guangdong Nuclear Power Station. Major achievements in the area of thermohydraulics, nuclear fuel, probabilistic safety assessment and severe accident researches are summarized. The foreseeable research plan for the near future, relating to the design and construction of 600 MWe PWR NPP at Qinshan Site (phase II development) is outlined

  1. Development of web-based safety review advisory system

    International Nuclear Information System (INIS)

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

    2002-01-01

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

  2. Development of safety review advisory system for nuclear power plants

    International Nuclear Information System (INIS)

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

    2001-01-01

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

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

    International Nuclear Information System (INIS)

    Silva, R.A. da; Thome Filho, Z.D.; Schirru, R.; Martinez, A.S.; Oliveira, L.F.S. de

    1986-01-01

    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.) [pt

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

    International Nuclear Information System (INIS)

    McGuinness, Edgar; Utne, Ingrid B.

    2014-01-01

    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

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

    Science.gov (United States)

    2016-02-15

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

  6. Safety-related control air systems - approved 1977

    International Nuclear Information System (INIS)

    Anon.

    1978-01-01

    This standard applies to those portions of the control air system that furnish air required to support, control, or operate systems or portions of systems that are safety related in nuclear power plants. This standard relates only to the air supply system(s) for safety-related air operated devices and does not apply to the safety-related air operated device or to air operated actuators for such devices. The objectives of this standard are to provide (1) minimum system design requirements for equipment, piping, instruments, controls, and wiring that constitute the air supply system; and (2) the system and component testing and maintenance requirements

  7. System theory and safety models in Swedish, UK, Dutch and Australian road safety strategies.

    Science.gov (United States)

    Hughes, B P; Anund, A; Falkmer, T

    2015-01-01

    Road safety strategies represent interventions on a complex social technical system level. An understanding of a theoretical basis and description is required for strategies to be structured and developed. Road safety strategies are described as systems, but have not been related to the theory, principles and basis by which systems have been developed and analysed. Recently, road safety strategies, which have been employed for many years in different countries, have moved to a 'vision zero', or 'safe system' style. The aim of this study was to analyse the successful Swedish, United Kingdom and Dutch road safety strategies against the older, and newer, Australian road safety strategies, with respect to their foundations in system theory and safety models. Analysis of the strategies against these foundations could indicate potential improvements. The content of four modern cases of road safety strategy was compared against each other, reviewed against scientific systems theory and reviewed against types of safety model. The strategies contained substantial similarities, but were different in terms of fundamental constructs and principles, with limited theoretical basis. The results indicate that the modern strategies do not include essential aspects of systems theory that describe relationships and interdependencies between key components. The description of these strategies as systems is therefore not well founded and deserves further development. Copyright © 2014 Elsevier Ltd. All rights reserved.

  8. Safety climate and culture: Integrating psychological and systems perspectives.

    Science.gov (United States)

    Casey, Tristan; Griffin, Mark A; Flatau Harrison, Huw; Neal, Andrew

    2017-07-01

    Safety climate research has reached a mature stage of development, with a number of meta-analyses demonstrating the link between safety climate and safety outcomes. More recently, there has been interest from systems theorists in integrating the concept of safety culture and to a lesser extent, safety climate into systems-based models of organizational safety. Such models represent a theoretical and practical development of the safety climate concept by positioning climate as part of a dynamic work system in which perceptions of safety act to constrain and shape employee behavior. We propose safety climate and safety culture constitute part of the enabling capitals through which organizations build safety capability. We discuss how organizations can deploy different configurations of enabling capital to exert control over work systems and maintain safe and productive performance. We outline 4 key strategies through which organizations to reconcile the system control problems of promotion versus prevention, and stability versus flexibility. (PsycINFO Database Record (c) 2017 APA, all rights reserved).

  9. Plant assessment system and safety culture

    International Nuclear Information System (INIS)

    Chun, Chuyoung

    1996-01-01

    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

  10. Operation safety of complex industrial systems. Main concepts

    International Nuclear Information System (INIS)

    Zwingelstein, G.

    2009-01-01

    Operation safety consists in knowing, evaluating, foreseeing, measuring and mastering the technological system and human failures in order to avoid their impacts on health and people's safety, on productivity, and on the environment, and to preserve the Earth's resources. This article recalls the main concepts of operation safety: 1 - evolutions in the domain; 2 - failures, missions and functions of a system and of its components: functional failure, missions and functions, industrial processes, notions of probability; 3 - basic concepts and operation safety: reliability, unreliability, failure density, failure rate, relations between them, availability, maintainability, safety. (J.S.)

  11. Decision support systems and expert systems for risk and safety analysis

    International Nuclear Information System (INIS)

    Baybutt, P.

    1986-01-01

    During the last 1-2 years, rapid developments have occurred in the development of decision support systems and expert systems to aid in decision making related to risk and safety of industrial plants. These activities are most noteworthy in the nuclear industry where numerous systems are under development with implementation often being made on personal computers. An overview of some of these developments is provided, and an example of one recently developed decision support system is given. This example deals with CADET, a system developed to aid the U.S. Nuclear Regulatory Commission in making decisions related to the topical issue of source terms resulting from degraded core accidents in light water reactors. The paper concludes with some comments on the likely directions of future developments in decision support systems and expert systems to aid in the management of risk and safety in industrial plants. (author)

  12. Systems engineering applied to integrated safety management for high consequence facilities

    International Nuclear Information System (INIS)

    Barter, R; Morais, B.

    1998-01-01

    Integrated Safety Management is a concept that is being actively promoted by the U.S. Department of Energy as a means of assuring safe operation of its facilities. The concept involves the integration of safety precepts into work planning rather than adjusting for safe operations after defining the work activity. The system engineering techniques used to design an integrated safety management system for a high consequence research facility are described. An example is given to show how the concepts evolved with the system design

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

    International Nuclear Information System (INIS)

    Khair, H. O. M.

    2012-06-01

    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)

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

    Data.gov (United States)

    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 of...

  15. Safety regulations concerning instrumentation and control systems for research reactors

    International Nuclear Information System (INIS)

    El-Shanshoury, A.I.

    2009-01-01

    A brief study on the safety and reliability issues related to instrumentation and control systems in nuclear reactor plants is performed. In response, technical and strategic issues are used to accomplish instrumentation and control systems safety. For technical issues there are ; systems aspects of digital I and C technology, software quality assurance, common-mode software, failure potential, safety and reliability assessment methods, and human factors and human machine interfaces. The strategic issues are the case-by-case licensing process and the adequacy of the technical infrastructure. The purpose of this work was to review the reliability of the safety systems related to these technical issues for research reactors

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

    Science.gov (United States)

    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.

  17. Qualification of FPGA-Based Safety-Related PRM System

    International Nuclear Information System (INIS)

    Miyazaki, Tadashi; Oda, Naotaka; Goto, Yasushi; Hayashi, Toshifumi

    2011-01-01

    Toshiba has developed Non-rewritable (NRW) Field Programmable Gate Array (FPGA)-based safety-related Instrumentation and Control (I and C) system. Considering application to safety-related systems, nonvolatile and non-rewritable FPGA which is impossible to be changed after once manufactured has been adopted in Toshiba FPGA-based system. FPGA is a device which consists only of basic logic circuits, and FPGA performs defined processing which is configured by connecting the basic logic circuit inside the FPGA. FPGA-based system solves issues existing both in the conventional systems operated by analog circuits (analog-based system) and the systems operated by central processing unit (CPU-based system). The advantages of applying FPGA are to keep the long-life supply of products, improving testability (verification), and to reduce the drift which may occur in analog-based system. The system which Toshiba developed this time is Power Range Neutron Monitor (PRM). Toshiba is planning to expand application of FPGA-based technology by adopting this development process to the other safety-related systems such as RPS from now on. Toshiba developed a special design process for NRW-FPGA-based safety-related I and C systems. The design process resolves issues for many years regarding testability of the digital system for nuclear safety application. Thus, Toshiba NRW-FPGA-based safety-related I and C systems has much advantage to be a would standard of the digital systems for nuclear safety application. (author)

  18. Performance Evaluation of SMART Passive Safety System for Small Break LOCA Using MARS Code

    International Nuclear Information System (INIS)

    Chun, Ji Han; Lee, Guy Hyung; Bae, Kyoo Hwan; Chung, Young Jong; Kim, Keung Koo

    2013-01-01

    SMART has significantly enhanced safety by reducing its core damage frequency to 1/10 that of a conventional nuclear power plant. KAERI is developing a passive safety injection system to replace the active safety injection pump in SMART. It consists of four trains, each of which includes gravity-driven core makeup tank (CMT) and safety injection tank (SIT). This system is required to meet the passive safety performance requirements, i.e., the capability to maintain a safe shutdown condition for a minimum of 72 hours without an AC power supply or operator action in the case of design basis accidents (DBAs). The CMT isolation valve is opened by the low pressurizer pressure signal, and the SIT isolation valve is opened at 2 MPa. Additionally, two stages of automatic depressurization systems are used for rapid depressurization. Preliminary safety analysis of SMART passive safety system in the event of a small-break loss-of-coolant accident (SBLOCA) was performed using MARS code. In this study, the safety analysis results of a guillotine break of safety injection line which was identified as the limiting SBLOCA in SMART are given. The preliminary safety analysis of a SBLOCA for the SMART passive safety system was performed using the MARS code. The analysis results of the most limiting SI line guillotine break showed that the collapsed liquid level inside the core support barrel was maintained sufficiently high above the top of core throughout the transient. This means that the passive safety injection flow from the CMT and SIT causes no core uncovery during the 72 hours following the break with no AC power supply or operator action, which in turn results in a consistent decrease in the fuel cladding temperature. Therefore, the SMART passive safety system can meet the passive safety performance requirement of maintaining the plant at a safe shutdown condition for a minimum of 72 hours without AC power or operator action for a representing accident of SBLOCA

  19. Regulatory Activities on Civil Nuclear Safety Equipment in China

    International Nuclear Information System (INIS)

    Gaoshang, Lu; Choi, Kwang Sik

    2011-01-01

    It is stipulated in IAEA Fundamental Safety Principles (SF1) that the fundamental safety objective is to protect people and the environment from harmful effects of ionizing radiation. The fundamental safety objective applies for all facilities and activities and for all stages over the lifetime of a facility or radiation source, including planning, sitting, design, manufacturing, construction, commissioning and operation, as well as decommissioning and closure. So, according to the requirement, the related activities such as design, manufacturing, installation and non-destructive test that conducted on civil nuclear equipment should be well controlled by the vendors, the owner of the nuclear power plants and the regulatory body. To insure the quality of those equipment, Chinese government had taken a series of measures to regulate the related activities on them

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

    International Nuclear Information System (INIS)

    Boos, K.A.

    1996-01-01

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

  1. Nuclear safety: operational aspects. 3. Hazard Analysis of Passive Systems

    International Nuclear Information System (INIS)

    Burgazzi, Luciano

    2001-01-01

    systems, and classify accident initiators in initiating events of accident sequences. A qualitative overview of accident sequences could be derived from the FMEA table by looking at consequence descriptions and preventive/mitigative actions. Moreover, criticality analysis is applied (failure mode and effect and criticality analysis), extending the procedure beyond the severity classification of accidents, to include estimates of the loss frequencies through failure probabilistic estimation. Probabilistic evaluation of accident initiators points out the probabilities/frequencies of having the plant in fault and/or unavailability conditions during isolation transient IC operation, ensuring, therefore, a complete set of initiating events of reactor accident sequences. To illustrate, Table I identifies two possible initiating events (IEs) as outcomes of the analysis, pertaining, respectively, to the loss of flow in one IC circuit (FF1) and loss of flow in the whole IC (FF) due to cooling loop faults. Loss frequency of an IE and a relative categorization is derived from the single-component failures that could contribute to the cause of the event. Finally, the FMEA study performed for safety assessment purposes will provide important feedback to the design activities. Design modification could be required to improve, for instance, prevention against the accident initiators, the effectiveness of mitigations, or the system control. An important lesson elicited from the analysis is that measures against common-cause failures, for instance, with respect to drain-line valves, can reduce significantly the probability of failure of the system. The study is not plant specific but pertains to the conceptual design of the foregoing system. (authors)

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

    Institute of Scientific and Technical Information of China (English)

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2001-02-01

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

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

    International Nuclear Information System (INIS)

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

    2001-02-01

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

  5. Further activities of safety culture toward nuclear transportation industry

    International Nuclear Information System (INIS)

    Machida, Y.; Shimakura, D.

    2004-01-01

    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

  6. Further activities of safety culture toward nuclear transportation industry

    Energy Technology Data Exchange (ETDEWEB)

    Machida, Y.; Shimakura, D. [NSnet, Tokyo (Japan)

    2004-07-01

    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.

  7. System and safety studies of accelerator driven transmutation systems

    International Nuclear Information System (INIS)

    Gudowski, W.; Wallenius, J.; Tucek, K.; Eriksson, Marcus; Carlsson, Johan; Seltborg, P.; Cetnar, J.

    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

  8. System and safety studies of accelerator driven transmutation systems

    Energy Technology Data Exchange (ETDEWEB)

    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.

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

    International Nuclear Information System (INIS)

    Balaji, P.

    2014-01-01

    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

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

  11. Safety Review related to Commercial Grade Digital Equipment in Safety System

    International Nuclear Information System (INIS)

    Yu, Yeongjin; Park, Hyunshin; Yu, Yeongjin; Lee, Jaeheung

    2013-01-01

    The upgrades or replacement of I and C systems on safety system typically involve digital equipment developed in accordance with non-nuclear standards. However, the use of commercial grade digital equipment could include the vulnerability for software common-mode failure, electromagnetic interference and unanticipated problems. Although guidelines and standards for dedication methods of commercial grade digital equipment are provided, there are some difficulties to apply the methods to commercial grade digital equipment for safety system. This paper focuses on regulatory guidelines and relevant documents for commercial grade digital equipment and presents safety review experiences related to commercial grade digital equipment in safety system. This paper focuses on KINS regulatory guides and relevant documents for dedication of commercial grade digital equipment and presents safety review experiences related to commercial grade digital equipment in safety system. Dedication including critical characteristics is required to use the commercial grade digital equipment on safety system in accordance with KEPIC ENB 6370 and EPRI TR-106439. The dedication process should be controlled in a configuration management process. Appropriate methods, criteria and evaluation result should be provided to verify acceptability of the commercial digital equipment used for safety function

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

    Science.gov (United States)

    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.

  13. Preliminary investigation on reliability assessment of passive safety system

    International Nuclear Information System (INIS)

    Huang Changfan; Kuang Bo

    2012-01-01

    The reliability evaluation of passive safety system plays an important part in probabilistic safety assessment (PSA) of nuclear power plant applying passive safety design, which depends quantitatively on reliabilities of passive safety system. According to the object of reliability assessment of passive safety system, relevant parameters are identified. Then passive system behavior during accident scenarios are studied. A practical example of this method is given for the case of reliability assessment of AP1000 passive heat removal system in loss of normal feedwater accident. Key and design parameters of PRHRS are identified and functional failure criteria are established. Parameter combinations acquired by Latin hyper~ cube sampling (LHS) in possible parametric ranges are input and calculations of uncertainty propagation through RELAP5/MOD3 code are carried out. Based on the calculations, sensitivity assessment on PRHRS functional criteria and reliability evaluation of the system are presented, which might provide further PSA with PRHR system reliability. (authors)

  14. Overall system description and safety characteristics of Prototype Gen IV Sodium Cooled Fast Reactor in Korea

    International Nuclear Information System (INIS)

    Yoo, Jae Woon; Chang, Jin Wook; Lim, Jae Yong; Cheon, Jin Sik; Lee, Tae Ho; Kim, Sung Kyun; Lee, Kwi Lim; Joo, Hyung Kook

    2016-01-01

    The Prototype Gen IV sodium cooled fast reactor (PGSFR) has been developed for the last 4 years, fulfilling the technology demonstration of the burning capability of transuranic elements included in light water reactor spent nuclear fuel. The PGSFR design has been focused on the robustness of safety systems by enhancing inherent safety characteristics of metal fuel and strengthening passive safety features using natural circulation and thermal expansion. The preliminary safety information document as a major outcome of the first design phase of PGSFR development was issued at the end of 2015. The project entered the second design phase at the beginning of 2016. This paper summarizes the overall structures, systems, and components of nuclear steam supply system and safety characteristics of the PGSFR. The research and development activities to demonstrate the safety performance are also briefly introduced in the paper

  15. Overall System Description and Safety Characteristics of Prototype Gen IV Sodium Cooled Fast Reactor in Korea

    Directory of Open Access Journals (Sweden)

    Jaewoon Yoo

    2016-10-01

    Full Text Available The Prototype Gen IV sodium cooled fast reactor (PGSFR has been developed for the last 4 years, fulfilling the technology demonstration of the burning capability of transuranic elements included in light water reactor spent nuclear fuel. The PGSFR design has been focused on the robustness of safety systems by enhancing inherent safety characteristics of metal fuel and strengthening passive safety features using natural circulation and thermal expansion. The preliminary safety information document as a major outcome of the first design phase of PGSFR development was issued at the end of 2015. The project entered the second design phase at the beginning of 2016. This paper summarizes the overall structures, systems, and components of nuclear steam supply system and safety characteristics of the PGSFR. The research and development activities to demonstrate the safety performance are also briefly introduced in the paper.

  16. Managing Safety and Operations: The Effect of Joint Management System Practices on Safety and Operational Outcomes.

    Science.gov (United States)

    Tompa, Emile; Robson, Lynda; Sarnocinska-Hart, Anna; Klassen, Robert; Shevchenko, Anton; Sharma, Sharvani; Hogg-Johnson, Sheilah; Amick, Benjamin C; Johnston, David A; Veltri, Anthony; Pagell, Mark

    2016-03-01

    The aim of this study was to determine whether management system practices directed at both occupational health and safety (OHS) and operations (joint management system [JMS] practices) result in better outcomes in both areas than in alternative practices. Separate regressions were estimated for OHS and operational outcomes using data from a survey along with administrative records on injuries and illnesses. Organizations with JMS practices had better operational and safety outcomes than organizations without these practices. They had similar OHS outcomes as those with operations-weak practices, and in some cases, better outcomes than organizations with safety-weak practices. They had similar operational outcomes as those with safety-weak practices, and better outcomes than those with operations-weak practices. Safety and operations appear complementary in organizations with JMS practices in that there is no penalty for either safety or operational outcomes.

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

    International Nuclear Information System (INIS)

    Bologna, Sandro; Picciolo, Giovanni; Taylor, Robert

    1997-11-01

    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

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

    International Nuclear Information System (INIS)

    Lim, In-Cheol; Wu, Jong-Sup; Lee, Kye-Hong

    2006-01-01

    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

  19. 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

    International Nuclear Information System (INIS)

    2007-04-01

    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

  20. Development of web-based safety review advisory system

    International Nuclear Information System (INIS)

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

    2002-01-01

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

  1. The regulatory system of nuclear safety in Russia

    International Nuclear Information System (INIS)

    Mizoguchi, Shuhei

    2013-01-01

    This article explains what type of mechanism the nuclear system has and how nuclear safety is regulated in Russia. There are two main organizations in this system : ROSATOM and ROSTEKHADZOR. ROSATOM, which was founded in 2007, incorporates all the nuclear industries in Russia, including civil nuclear companies as well as nuclear weapons complex facilities. ROSTEKHNADZOR is the federal body that secures and supervises the safety in using atomic energy. This article also reviews three laws on regulating nuclear safety. (author)

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

    International Nuclear Information System (INIS)

    2001-01-01

    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.)

  3. Application of model systems in nanobiotechnology safety

    International Nuclear Information System (INIS)

    Khalilov, R.I.; Aliev, E.Sh.; Khudaverdieva, S.R.

    2010-11-01

    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.

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

    International Nuclear Information System (INIS)

    Coulston, D.J.; Baylis, C.C.

    2000-01-01

    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)

  5. Control system of labour safety measures in the higher educational institution

    Directory of Open Access Journals (Sweden)

    O. G. Feoktistova

    2015-01-01

    Full Text Available The article examines a system of labour safety measures control. With the introduction of the integrated system of management the competitive ability of production and organization, the effectiveness of its activity rise, and sinnergicheskiy effect is also reached and the savings of all forms of resources are ensured. Objectives and methods of control system of labour safety measures in enterprises are developed, including in the educational institutions.

  6. Crime, perceived safety, and physical activity: A meta-analysis.

    Science.gov (United States)

    Rees-Punia, Erika; Hathaway, Elizabeth D; Gay, Jennifer L

    2018-06-01

    Perceived safety from crime and objectively-measured crime rates may be associated with physical inactivity. The purpose of this meta-analysis is to estimate the odds of accumulating high levels of physical activity (PA) when the perception of safety from crime is high and when objectively-measured crime is high. Peer-reviewed studies were identified through PubMed, Web of Science, ProQuest Criminal Justice, and ScienceDirect from earliest record through 2016. Included studies measured total PA, leisure-time PA, or walking in addition to perceived safety from crime or objective measures of crime. Mean odds ratios were aggregated with random effects models, and meta-regression was used to examine effects of potential moderators: country, age, and crime/PA measure. Sixteen cross-sectional studies yielded sixteen effects for perceived safety from crime and four effects for objective crime. Those reporting feeling safe from crime had a 27% greater odds of achieving higher levels of physical activity (OR=1.27 [1.08, 1.49]), and those living in areas with higher objectively-measured crime had a 28% reduced odds of achieving higher levels of physical activity (OR=0.72 [0.61, 0.83]). Effects of perceived safety were highly heterogeneous (I 2 =94.09%), but explored moderators were not statistically significant, likely because of the small sample size. Despite the limited number of effects suitable for aggregation, the mean association between perceived safety and PA was significant. As it seems likely that perceived lack of safety from crime constrains PA behaviors, future research exploring moderators of this association may help guide public health recommendations and interventions. Copyright © 2017 Elsevier Inc. All rights reserved.

  7. Food safety performance indicators to benchmark food safety output of food safety management systems

    NARCIS (Netherlands)

    Jacxsens, L.; Uyttendaele, M.; Devlieghere, F.; Rovira, J.; Oses Gomez, S.; Luning, P.A.

    2010-01-01

    There is a need to measure the food safety performance in the agri-food chain without performing actual microbiological analysis. A food safety performance diagnosis, based on seven indicators and corresponding assessment grids have been developed and validated in nine European food businesses.

  8. Work Pressure and Safety Behaviors among Health Workers in Ghana: The Moderating Role of Management Commitment to Safety

    Directory of Open Access Journals (Sweden)

    Kwesi Amponsah-Tawaih

    2016-12-01

    Conclusion: When employees perceive safety communication, safety systems and training to be positive, they seem to comply with safety rules and procedures than voluntarily participate in safety activities.

  9. Safety implications of electronic driving support systems : an orientation.

    OpenAIRE

    Gundy, C.M. Steyvers, F.J.J.M. & Kaptein, N.A.

    1995-01-01

    This report focuses on traffic safety aspects of driving support systems. The report consists of two parts. First of all, the report discusses a number of topics, relevant for the implementation and evaluation of driving support systems. These topics include: (1) safety research into driving support systems: (2) the importance of research into driver models and the driving task; (3) horizontal integration of driving support systems; (4) vertical integration of driving support systems; (5) tas...

  10. The Integrated Safety Management System (ISMS) of the US Department of Energy

    International Nuclear Information System (INIS)

    Linn, M.A.

    1999-01-01

    While the Integrated Safety Management System (ISMS) program is a fairly rational approach to safety, it represents the culmination of several years of hard-earned lessons learned. Considering the size and the diversity of interrelated elements which make up the USDOE complex, this result shows the determination of both the USDOE and its contractors to bring safety hazards to heel. While these lessons learned were frustrating and expensive, the results were several key insights upon which the ISMS was built: (1) Ensure safety management is integral to the business. Safety management must become part of each work activity, rather that something in addition to or on top of. (2) Tailor the safety requirements to the work and its hazards. In order to be cost-effective and efficient, safety management should have flexibility in order to match safety requirements with the level of the hazards in a graded manner. (3) Safety management must be coherent and integrated. Large and complex organizations are no excuse for fragmented and overlapping safety initiatives and programs. Simple, from the ground up objectives and principles must be defined and used to guide a comprehensive safety management program. (4) A safety management system must balance resources and priorities. The system must provide the means to balance resources against the particular work hazards, recognizing that different degrees of hazards requires corresponding prevention measures. (5) Clear roles and responsibilities for safety management must be defined. Both the regulator and the contractor have specific responsibilities for safety which must be clearly articulated at all levels of the work processes. (6) Those responsible for safety must have the competence to carry it out. Those assigned responsibilities must have the experience, knowledge, skills, and authority to carry them out. As one can surmise, the ISMS is not a new program to be implemented, but rather a new attitude which must be adopted

  11. Development of a Generic Environmental Safety Case for the Disposal of Higher Activity Wastes in the UK

    International Nuclear Information System (INIS)

    Bailey, Lucy; Hicks, Tim

    2016-01-01

    The UK generic ESC demonstrates safe disposal of higher activity wastes, by providing: • A demonstration of how environmental safety can be achieved by a variety of disposal concepts based on systems of multiple engineered and natural barriers, providing multiple safety functions; • An understanding of expected barrier performance and how conditions in a disposal system will evolve, based on research findings presented in RWM’s knowledge base; • An approach to safety assessment based on multiple lines of reasoning, involving both qualitative and quantitative analysis; • Complementary insight modelling and total system modelling used to develop understanding of how different components of the engineered and natural barrier system contribute to safety

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

    Science.gov (United States)

    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.

  13. A concurrent diagnosis of microbiological food safety output and food safety management system performance: Cases from meat processing industries

    NARCIS (Netherlands)

    Luning, P.A.; Jacxsens, L.; Rovira, J.; Oses Gomez, S.; Uyttendaele, M.; Marcelis, W.J.

    2011-01-01

    Stakeholder requirements force companies to analyse their food safety management system (FSMS) performance to improve food safety. Performance is commonly analysed by checking compliance against preset requirements via audits/inspections, or actual food safety (FS) output is analysed by

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

    Energy Technology Data Exchange (ETDEWEB)

    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).

  15. On the safety performance of the advanced nuclear energy systems

    International Nuclear Information System (INIS)

    Li Shounan

    1999-01-01

    Some features on the safety performances of the Advanced Nuclear Energy Systems are discussed. The advantages and some peculiar problems on the safety of Advanced Nuclear Energy Systems with subcritical nuclear reactor driven by external neutron sources are also pointed out in comparison with conventional nuclear reactors

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

    International Nuclear Information System (INIS)

    Vătăsescu, Mihaela

    2015-01-01

    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

  17. Towards predictive cardiovascular safety : a systems pharmacology approach

    NARCIS (Netherlands)

    Snelder, Nelleke

    2014-01-01

    Cardiovascular safety issues related to changes in blood pressure, arise frequently in drug development. In the thesis “Towards predictive cardiovascular safety – a systems pharmacology approach”, a system-specific model is described to quantify drug effects on the interrelationship between mean

  18. Emerging standards with application to accelerator safety systems

    International Nuclear Information System (INIS)

    Mahoney, K.L.; Robertson, H.P.

    1997-01-01

    This paper addresses international standards which can be applied to the requirements for accelerator personnel safety systems. Particular emphasis is given to standards which specify requirements for safety interlock systems which employ programmable electronic subsystems. The work draws on methodologies currently under development for the medical, process control, and nuclear industries

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

  20. Safety implications of electronic driving support systems : an orientation.

    NARCIS (Netherlands)

    Gundy, C.M. Steyvers, F.J.J.M. & Kaptein, N.A.

    1995-01-01

    This report focuses on traffic safety aspects of driving support systems. The report consists of two parts. First of all, the report discusses a number of topics, relevant for the implementation and evaluation of driving support systems. These topics include: (1) safety research into driving support

  1. New Automated System Available for Reporting Safety Concerns | Poster

    Science.gov (United States)

    A new system has been developed for reporting safety issues in the workplace. The Environment, Health, and Safety’s (EHS’) Safety Inspection and Issue Management System (SIIMS) is an online resource where any employee can report a problem or issue, said Siobhan Tierney, program manager at EHS.

  2. Improvement of the regulatory system by implementation new safety demands

    International Nuclear Information System (INIS)

    Iglesias, R.; Alfonso, C.

    1996-01-01

    The work describes in broad terms, the analysis that is being performed aiming at the adoption of a regulatory system that could meet the current safety demands, but which, at the same time, could be a general system that might allow different safety assessments to be done by making use of more specific technical standards of the technology supplier

  3. Innovation in the Safety of nuclear systems: fundamental aspects

    International Nuclear Information System (INIS)

    Herranz, L. E.

    2009-01-01

    Safety commercial nuclear reactors has been an indispensable condition for future enlargement of power generation based on nuclear technology. Its fundamental principle, defence in depth, far from being outdated, is still adopted as a key foundation in the advanced nuclear system (generations III and IV). Nevertheless, the cumulative experience gained in the operation and maintenance of nuclear reactors, the development of methodologies like the probabilistic safety analysis, the use of passive safety systems and, even, the inherent characteristics of some new design (which exclude accident scenarios), allow estimating safety figures of merit even more outstanding that those achieved in the second generation of nuclear reactors. This safety innovation of upcoming nuclear reactors has entailed a huge investigation program (generation III) that will be focused on optimizing and demonstrating the postulated safety of future nuclear systems (Generation IV). (Author)

  4. Molten salt reactor as asymptotic safety nuclear system

    International Nuclear Information System (INIS)

    Novikov, V.M.; Ignatyev, V.V.

    1989-01-01

    Safety is becoming the main and priority problem of the nuclear power development. An increase of the active safety measures could hardly be considered as the proper way to achieve the asymptotically high level of nuclear safety. It seem that the more realistic way to achieve such a goal is to minimize risk factors and to maximize the use of inherent and passive safety properties. The passive inherent safety features of the liquid fuel molten salt reactor (MSR) technology are making it attractive for future energy generation. The achievement of the asymptotic safety in MSR is being connected with the minimization of such risk factors as a reactivity excess, radioactivity stored, decay heat, non nuclear energy stored in core. In this paper safety peculiarities of the different MSR concepts are discussed

  5. Patient safety - the role of human factors and systems engineering.

    Science.gov (United States)

    Carayon, Pascale; Wood, Kenneth E

    2010-01-01

    Patient safety is a global challenge that requires knowledge and skills in multiple areas, including human factors and systems engineering. In this chapter, numerous conceptual approaches and methods for analyzing, preventing and mitigating medical errors are described. Given the complexity of healthcare work systems and processes, we emphasize the need for increasing partnerships between the health sciences and human factors and systems engineering to improve patient safety. Those partnerships will be able to develop and implement the system redesigns that are necessary to improve healthcare work systems and processes for patient safety.

  6. Patient Safety: The Role of Human Factors and Systems Engineering

    Science.gov (United States)

    Carayon, Pascale; Wood, Kenneth E.

    2011-01-01

    Patient safety is a global challenge that requires knowledge and skills in multiple areas, including human factors and systems engineering. In this chapter, numerous conceptual approaches and methods for analyzing, preventing and mitigating medical errors are described. Given the complexity of healthcare work systems and processes, we emphasize the need for increasing partnerships between the health sciences and human factors and systems engineering to improve patient safety. Those partnerships will be able to develop and implement the system redesigns that are necessary to improve healthcare work systems and processes for patient safety. PMID:20543237

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

    Science.gov (United States)

    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. Problems of current regulatory system, the ongoing adjustments and changes for modifying and improving regulatory system are discussed. The aim of reform and the incentives to drive forward more health and safety conditions in workplaces are also outlined.

  8. Declarative Rule-based Safety for Robotic Perception Systems

    DEFF Research Database (Denmark)

    Mogensen, Johann Thor Ingibergsson; Kraft, Dirk; Schultz, Ulrik Pagh

    2017-01-01

    Mobile robots are used across many domains from personal care to agriculture. Working in dynamic open-ended environments puts high constraints on the robot perception system, which is critical for the safety of the system as a whole. To achieve the required safety levels the perception system needs...... to be certified, but no specific standards exist for computer vision systems, and the concept of safe vision systems remains largely unexplored. In this paper we present a novel domain-specific language that allows the programmer to express image quality detection rules for enforcing safety constraints...

  9. Safety surveillance of activities on nuclear pressure components in China

    International Nuclear Information System (INIS)

    Li Ganjie; Li Tianshu; Yan Tianwen

    2005-01-01

    The nuclear pressure components, which perform the nuclear safety functions, are one of the key physical barriers for nuclear safety. For the national strategy on further development of nuclear power and localization of nuclear pressure components, there still exist some problems in preparedness on the localization. As for the technical basis, what can not be overlooked is the management. Aiming at the current problems, National Nuclear Safety Administration (NNSA) has taken measures to strengthen the propagation and popularization of nuclear safety culture, adjust the review and approval policies for nuclear pressure components qualification license, establish more stringent management requirements, and enhance the surveillance of activities on nuclear pressure equipment. Meanwhile, NNSA has improved the internal management and the regulation efficiency on nuclear pressure components. At the same time, with the development and implementation of 'Rules on the Safety Regulation for Nuclear Safety Important Components' to be promulgated by the State Council of China, NNSA will complete and improve the regulation on nuclear pressure components and other nuclear equipment. (authors)

  10. The reliability of nuclear power plant safety systems

    International Nuclear Information System (INIS)

    Susnik, J.

    1978-01-01

    A criterion was established concerning the protection that nuclear power plant (NPP) safety systems should afford. An estimate of the necessary or adequate reliability of the total complex of safety systems was derived. The acceptable unreliability of auxiliary safety systems is given, provided the reliability built into the specific NPP safety systems (ECCS, Containment) is to be fully utilized. A criterion for the acceptable unreliability of safety (sub)systems which occur in minimum cut sets having three or more components of the analysed fault tree was proposed. A set of input MTBF or MTTF values which fulfil all the set criteria and attain the appropriate overall reliability was derived. The sensitivity of results to input reliability data values was estimated. Numerical reliability evaluations were evaluated by the programs POTI, KOMBI and particularly URSULA, the last being based on Vesely's kinetic fault tree theory. (author)

  11. In vitro Activity and Safety Assessment of New Synthesized Thiazolo ...

    African Journals Online (AJOL)

    Purpose: To synthesis a series of novel thiazolo pyrimidine derivatives and evaluate them in vitro for their safety and anthelmintic activity against E. multilocularis metacestodes using BALB/c mice. Methods: A new series of substituted amino thiazole, hydrazinothiazole and thiazolo pyrimidine derivatives (2-6) were ...

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

    NARCIS (Netherlands)

    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

  13. Survey of the passive safety systems of the BWR 1000 concept from SIEMENS

    Energy Technology Data Exchange (ETDEWEB)

    Mattern, J; Brettschuh, W; Palavecino, C [SIEMENS, Energieerzeugung, Offenbach (Germany)

    1996-12-01

    Through the use of passive safety systems and components for accident control in addition to the active systems required for plant operation, a higher degree of safety against core-endangering conditions is achieved which is no longer ruled by complex system engineering dependent on power supply and activation by I and C systems. A low core power density and large water inventories stored inside the reactor pressure vessel as well as inside and outside the containment ensure good plant behaviour in the event of transients or accidents. These passive safety systems - which required neither electric power to function nor I and C systems for actuation, being activated solely on the basis of changes in process variables such as water level, pressure and temperature - provide a grace period of more than 5 days after the onset of accident conditions before manual intervention becomes necessary. 8 figs.

  14. IAEA activities on safety aspects of NPP ageing

    International Nuclear Information System (INIS)

    Pachner, J.

    1998-01-01

    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

  15. The complexity of patient safety reporting systems in UK dentistry.

    Science.gov (United States)

    Renton, T; Master, S

    2016-10-21

    Since the 'Francis Report', UK regulation focusing on patient safety has significantly changed. Healthcare workers are increasingly involved in NHS England patient safety initiatives aimed at improving reporting and learning from patient safety incidents (PSIs). Unfortunately, dentistry remains 'isolated' from these main events and continues to have a poor record for reporting and learning from PSIs and other events, thus limiting improvement of patient safety in dentistry. The reasons for this situation are complex.This paper provides a review of the complexities of the existing systems and procedures in relation to patient safety in dentistry. It highlights the conflicting advice which is available and which further complicates an overly burdensome process. Recommendations are made to address these problems with systems and procedures supporting patient safety development in dentistry.

  16. Research on advanced system safety assessment procedures (4)

    International Nuclear Information System (INIS)

    Suzuki, Kazuhiko; Shimada, Yukiyasu

    2001-03-01

    The past research reports in the area of safety engineering proposed the Computer-aided HAZOP system to be applied to Nuclear Reprocessing Facilities. Automated HAZOP system has great advantage compared with human analysts in terms of accuracy of the results, and time required to conduct HAZOP studies. This report surveys the literature on risk assessment and safety design based on the concept of independent protection layers (IPLs). Furthermore, to improve HAZOP System, tool is proposed to construct the basic model and the internal state model. Such HAZOP system is applied to analyze two kinds of processes, where the ability of the proposed system is verified. In addition, risk assessment support system is proposed to integrate safety design environment and assessment result to be used by other plants as well as to enable the underline plant to use other plants' information. This technique can be implemented using web-based safety information systems. (author)

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

    International Nuclear Information System (INIS)

    1996-12-01

    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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-01

    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.

  19. Cost/benefit analyses of reactor safety systems

    International Nuclear Information System (INIS)

    1988-01-01

    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

  20. Effective vaccine safety systems in all countries: a challenge for more equitable access to immunization.

    Science.gov (United States)

    Amarasinghe, Ananda; Black, Steve; Bonhoeffer, Jan; Carvalho, Sandra M Deotti; Dodoo, Alexander; Eskola, Juhani; Larson, Heidi; Shin, Sunheang; Olsson, Sten; Balakrishnan, Madhava Ram; Bellah, Ahmed; Lambach, Philipp; Maure, Christine; Wood, David; Zuber, Patrick; Akanmori, Bartholomew; Bravo, Pamela; Pombo, María; Langar, Houda; Pfeifer, Dina; Guichard, Stéphane; Diorditsa, Sergey; Hossain, Md Shafiqul; Sato, Yoshikuni

    2013-04-18

    Serious vaccine-associated adverse events are rare. To further minimize their occurrence and to provide adequate care to those affected, careful monitoring of immunization programs and case management is required. Unfounded vaccine safety concerns have the potential of seriously derailing effective immunization activities. To address these issues, vaccine pharmacovigilance systems have been developed in many industrialized countries. As new vaccine products become available to prevent new diseases in various parts of the world, the demand for effective pharmacovigilance systems in low- and middle-income countries (LMIC) is increasing. To help establish such systems in all countries, WHO developed the Global Vaccine Safety Blueprint in 2011. This strategic plan is based on an in-depth analysis of the vaccine safety landscape that involved many stakeholders. This analysis reviewed existing systems and international vaccine safety activities and assessed the financial resources required to operate them. The Blueprint sets three main strategic goals to optimize the safety of vaccines through effective use of pharmacovigilance principles and methods: to ensure minimal vaccine safety capacity in all countries; to provide enhanced capacity for specific circumstances; and to establish a global support network to assist national authorities with capacity building and crisis management. In early 2012, the Global Vaccine Safety Initiative (GVSI) was launched to bring together and explore synergies among on-going vaccine safety activities. The Global Vaccine Action Plan has identified the Blueprint as its vaccine safety strategy. There is an enormous opportunity to raise awareness for vaccine safety in LMIC and to garner support from a large number of stakeholders for the GVSI between now and 2020. Synergies and resource mobilization opportunities presented by the Decade of Vaccines can enhance monitoring and response to vaccine safety issues, thereby leading to more equitable

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

    International Nuclear Information System (INIS)

    Chung, Moon Ki; Park, Chun Kyeong; Yang, Seon Kyu; Chung, Chang Hwan; Chun, Shee Yeong; Song, Cheol Hwa; Chun, Hyeong Gil; Chang, Seok Kyu; Chung, Heung Joon; Won, Soon Yeon; Cho, Yeong Ro; Kim, Bok Deuk; Min, Kyeong Ho

    1994-07-01

    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)

  2. Design requirements of communication architecture of SMART safety system

    International Nuclear Information System (INIS)

    Park, H. Y.; Kim, D. H.; Sin, Y. C.; Lee, J. Y.

    2001-01-01

    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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2012-05-15

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

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

    International Nuclear Information System (INIS)

    BRADY RAAP, M.C.

    1999-01-01

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

  5. ADASY (Active Daylighting System)

    Science.gov (United States)

    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

  6. 78 FR 55775 - Pipeline Safety: Information Collection Activities

    Science.gov (United States)

    2013-09-11

    ... important tool for identifying safety trends in the hazardous liquid pipeline industry. In a Federal... reference of American Petroleum Institute (API) API 1130 (the industry standard on leak detection) which... requests that volume exiting a system during a controlled event not be reported. PHMSA Response: PHMSA does...

  7. Safety study of PCC 2140 and ALILOG 21 used as part of safety measurement systems

    International Nuclear Information System (INIS)

    Meriaux, Pierre; Adnot, Serge; Rayrolles, Catherine.

    1978-03-01

    The PCC 2140 and ALILOG 21 equipment may be used at C.E.A. or E.D.F., as part of safety measurement systems. In a study of a similar, but earlier equipment, it was noticed that certain types of failures caused the system to switch to the least sensitive measurement range, which was detrimental to safety. This report analyses failure modes leading to unsafe failures and evaluates the risks ran into taking in account tests during use [fr

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

    Energy Technology Data Exchange (ETDEWEB)

    Hughes, P. J. [HM Nuclear Installations Inspectorate Marine Engineering Submarines Defence Nuclear Safety Regulator Serco Assurance Redgrave Court, Merton Road, Bootle L20 7HS (United Kingdom); Westwood, R.N; Mark, R. T. [FLEET HQ, Leach Building, Whale Island, Portsmouth, PO2 8BY (United Kingdom); Tapping, K. [Serco Assurance,Thomson House, Risley, Warrington, WA3 6GA (United Kingdom)

    2006-07-01

    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)

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

    International Nuclear Information System (INIS)

    Koh, Jung Soo

    1997-02-01

    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

  10. Risk-based reconfiguration of safety monitoring system using dynamic Bayesian network

    International Nuclear Information System (INIS)

    Kohda, Takehisa; Cui Weimin

    2007-01-01

    To prevent an abnormal event from leading to an accident, the role of its safety monitoring system is very important. The safety monitoring system detects symptoms of an abnormal event to mitigate its effect at its early stage. As the operation time passes by, the sensor reliability decreases, which implies that the decision criteria of the safety monitoring system should be modified depending on the sensor reliability as well as the system reliability. This paper presents a framework for the decision criteria (or diagnosis logic) of the safety monitoring system. The logic can be dynamically modified based on sensor output data monitored at regular intervals to minimize the expected loss caused by two types of safety monitoring system failure events: failed-dangerous (FD) and failed-safe (FS). The former corresponds to no response under an abnormal system condition, while the latter implies a spurious activation under a normal system condition. Dynamic Bayesian network theory can be applied to modeling the entire system behavior composed of the system and its safety monitoring system. Using the estimated state probabilities, the optimal decision criterion is given to obtain the optimal diagnosis logic. An illustrative example of a three-sensor system shows the merits and characteristics of the proposed method, where the reasonable interpretation of sensor data can be obtained

  11. Safety analysis and evaluation methodology for fusion systems

    International Nuclear Information System (INIS)

    Fujii-e, Y.; Kozawa, Y.; Namba, C.

    1987-03-01

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

    International Nuclear Information System (INIS)

    Matzie, Regis A.; Carpentino, Frederick L.; Robertson, James E.

    1996-01-01

    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 80 R 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

  13. Seismic safety programme at NPP Paks. Propositions for coordinated international activity in seismic safety of the WWER-440 V-213

    International Nuclear Information System (INIS)

    Katona, T.

    1995-01-01

    This paper presents the Paks NPP seismic safety program, highlighting the specifics of the WWER-440/213 type in operation, and the results of work obtained so far. It covers the following scope: establishment of the seismic safety program (original seismic design, current requirements, principles and structure of the seismic safety program); implementation of the seismic safety program (assessing the seismic hazard of the site, development of the new concept of seismic safety for the NPP, assessing the seismic resistance of the building and the technology); realization of the seismic safety of higher level (technical solutions, drawings, realization); ideas and propositions for coordinated international activity

  14. METIS: Dependable Cooperative Systems for Public Safety

    NARCIS (Netherlands)

    Hendriks, A.J.; Laar, P.J.L.J. van de

    2013-01-01

    Much, if not most, information needed to assess a crisis situation originates these days from cooperative sources such as the Internet and social networks. Public safety authorities face the challenge to compile this information of uncertain origin and quality in their situation understanding and

  15. Safety and efficiency of future systems

    International Nuclear Information System (INIS)

    2000-01-01

    The objective of the program was to investigate and evaluate new or revised concepts for nuclear energy that offer potential long term benefits in terms of cost, safety, waste management, use of fissile material, less risk of diversion and sustainability. The work program was concerned with studying innovative or revised reactor concepts and other applications, and innovative fuels and fuel cycles

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

    Science.gov (United States)

    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.

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

    Institute of Scientific and Technical Information of China (English)

    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. Development and application of digital safety system in NPPs

    International Nuclear Information System (INIS)

    Kwon, Keechoon; Kim, Changhwoi; Lee, Dongyoung

    2012-01-01

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

  19. Development and application of digital safety system in NPPs

    Energy Technology Data Exchange (ETDEWEB)

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

    2012-03-15

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

  20. Jefferson Lab IEC 61508/61511 Safety PLC Based Safety System

    International Nuclear Information System (INIS)

    Mahoney, Kelly; Robertson, Henry

    2009-01-01

    This paper describes the design of the new 12 GeV Upgrade Personnel Safety System (PSS) at the Thomas Jefferson National Accelerator Facility (TJNAF). The new PSS design is based on the implementation of systems designed to meet international standards IEC61508 and IEC 61511 for programmable safety systems. In order to meet the IEC standards, TJNAF engineers evaluated several SIL 3 Safety PLCs before deciding on an optimal architecture. In addition to hardware considerations, software quality standards and practices must also be considered. Finally, we will discuss R and D that may lead to both high safety reliability and high machine availability that may be applicable to future accelerators such as the ILC.