WorldWideScience

Sample records for vessel safety management

  1. 78 FR 55230 - Safety and Environmental Management System Requirements for Vessels on the U.S. Outer Continental...

    Science.gov (United States)

    2013-09-10

    ...\\ including the regulation of workplace safety and health.\\2\\ The Coast Guard's regulatory authority extends... 147 [Docket No. USCG-2012-0779] RIN 1625-AC05 Safety and Environmental Management System Requirements... a vessel-specific Safety and Environmental Management System (SEMS) that incorporates the management...

  2. Aspects of the state safety regulation dealing with management of radioactive wastes from nuclear vessels

    International Nuclear Information System (INIS)

    Markarov, Valentin G.

    1999-01-01

    According to this presentation, the Constitution of the Russian Federation states that nuclear power engineering and fissile materials are under the jurisdiction of the Russian Federation. But there is no federal law with detailed directions for radioactive waste (RW) management, which thus comes under the Federal law ''On Use of Atomic Energy''. This law defines the legal basis and principles of regulating the relations occurring during RW management and sets some general requirements. RW management safety is regulated by the federal norms and rules (1) Radiation Safety Norms (NRB-96), Basic Sanitary Rules (OSP-72, 87) and (3) Sanitary Rules for RW Management (SPORO-85), etc. A number of normative documents on RW management will be put in force in 1999. For work in the field of RW management, licence must in general be obtained from Gozatomnazdor of Russia. The conditions for receiving a license for the management of RW from vessels are presented

  3. ADA access to passenger vessels : finding safety equivalence solutions for weathertight doors with coamings : Phase 2 : a risk management approach to reconfiguration design solutions

    Science.gov (United States)

    2005-03-01

    This report examines a risk management methodology to provide for both marine safety and disability access at weathertight doors into passenger accommodation spaces on U.S. passenger vessels. The Architectural and Transportation Barriers Compliance B...

  4. Assessment and management of ageing of major nuclear power plant components important to safety: PWR vessel internals: 2007 update

    International Nuclear Information System (INIS)

    2007-06-01

    At present, there are over four hundred operational nuclear power plants (NPPs) in IAEA Member States. Operating experience has shown that effective control of the ageing degradation of the major NPP components (e.g. caused by unanticipated phenomena and by operating, maintenance or manufacturing errors) is one of the most important issues for plant safety and also plant life. Ageing in these NPPs must be therefore effectively managed to ensure the availability of design functions throughout the plant service life. From the safety perspective, this means controlling within acceptable limits the ageing degradation and wearout of plant components important to safety so that adequate safety margins remain, i.e. integrity and functional capability in excess of normal operating requirements. IAEA-TECDOC-1119 documents ageing assessment and management practices for PWR Reactor Vessel Internals (RVIs) that were current at the time of its finalization in 1997-1998. Safety significant operating events have occurred since the finalization of the TECDOC, e.g. irradiation assisted stress corrosion cracking (IASCC) of baffle-former bolts, which threatened the integrity of the vessel internals. In addition, concern of fretting wear of control rod guide tubes has been raised in Japan. These events led to new ageing management actions by both NPP operators and regulators. Therefore it was recognized that IAEA-TECDOC-1119 should be updated by incorporating those new events and their countermeasures. The objective of this report is to update relevant sections of the existing IAEA-TECDOC- 1119 in order to provide current ageing management guidance for PWR RVIs to all involved in the operation and regulation of PWRs and thus to help ensure PWR safety in IAEA Member States throughout their entire service life

  5. Assessment and management of ageing of major nuclear power plant components important to safety: BWR pressure vessel internals

    International Nuclear Information System (INIS)

    2005-10-01

    At present, there are over four hundred operational nuclear power plants (NPPs) in IAEA Member States. Operating experience has shown that ineffective control of the ageing degradation of the major NPP components (caused for instance by unanticipated phenomena and by operating maintenance or manufacturing errors) can jeopardize plant safety and also plant life. Ageing in these NPPs must be therefore effectively managed to ensure the availability of design functions throughout the plant service life. From the safety perspective, this means controlling, within acceptable limits, the ageing degradation and ware out of components important to safety so that adequate safety margins remain, i.e. integrity and functional capability in excess of normal operating requirements. This TECDOC is one in a series of guidance reports on the assessment and management of ageing of the major NPP components important to safety. The reports are based on experience and practices of NPP operators, regulators, designers, manufacturers, and technical support organizations and a widely accepted Methodology for the Management of Ageing of NPP Components Important to Safety, which was issued by the IAEA in 1992. Since the reports are written from a safety perspective, they do not address life or life cycle management of plant components, which involves economic considerations. The current practices for the assessment of safety margins (fitness for service) and the inspection, monitoring and mitigation of ageing degradation of selected components of heavy water moderated reactors (HWRs), boiling water reactors (BWRs), pressurized water reactors (PWRs), and water moderated, water cooled energy reactors (WWERs) are documented in the reports. These practices are intended to help all involved directly and indirectly in ensuring the safe operation of NPPs, and also to provide a common technical basis for dialogue between plant operators and regulators when dealing with age related licensing issues

  6. Assessment and management of ageing of major nuclear power plant components important to safety: PWR vessel internals

    International Nuclear Information System (INIS)

    1999-10-01

    At present, there are over four hundred operational nuclear power plants (NPPs) in IAEA Member States. Operating experience has shown that ineffective control of the ageing degradation of the major NPP components (e.g. caused by unanticipated phenomena and by operating, maintenance or manufacturing errors) can jeopardize plant safety and also plant life. Ageing in these NPPs must be therefore effectively managed to ensure the availability of design functions throughout the plant service life. From the safety perspective, this means controlling within acceptable limits the ageing degradation and wear-out of plant components important to safety so that adequate safety margins remain, i.e. integrity and functional capability in excess of normal operating requirements. This TECDOC is one in a series of reports on the assessment and management of ageing of the major NPP components important to safety. The reports are based on experience and practices of NPP operators, regulators, designers, manufacturers, and technical support organizations and a widely accepted Methodology for the Management of Ageing of NPP Components Important to Safety, which was issued by the IAEA in 1992. The current practices for the assessment of safety margins (fitness-for-service) and the inspection, monitoring and mitigation of ageing degradation of selected components of Canada deuterium-uranium (CANDU) reactors, boiling water reactors (BWRs), pressurized water reactors (PWRs), and water moderated, water cooled energy reactors (WWERs) are documented in the reports. These practices are intended to help all involved directly and indirectly in ensuring the safe operation of NPPs, and to provide a common technical basis for dialogue between plant operators and regulators when dealing with age related licensing issues. The guidance reports are directed at technical experts from NPPs and from regulatory, plant design, manufacturing and technical support organizations dealing with specific plant

  7. Assessment and management of ageing of major nuclear power plant components important to safety: PWR pressure vessels. 2007 update

    International Nuclear Information System (INIS)

    2007-06-01

    At present, there are over four hundred operational nuclear power plants (NPPs) in IAEA Member States. Operating experience has shown that effective control of the ageing degradation of the major NPP components (e.g. caused by unanticipated phenomena and by operating, maintenance or manufacturing errors) is one of the most important issues for plant safety and also plant life. Ageing in these NPPs must be therefore effectively managed to ensure the availability of design functions throughout the plant service life. From the safety perspective, this means controlling within acceptable limits the ageing degradation and wear-out of plant components important to safety so that adequate safety margins remain, i.e. integrity and functional capability in excess of normal operating requirements. IAEA-TECDOC-1120 documented ageing assessment and management practices for pressurized water reactor (PWR) reactor pressure vessels (RPVs) that were current at the time of its finalization in 1997-1998. Safety significant operating events have occurred since the finalization of the TECDOC, e.g. primary water stress corrosion cracking (PWSCC) of Alloy 600 control rod drive mechanism (CRDM) penetrations and boric acid corrosion/wastage of RPV heads, which threatened the integrity of the RPV heads. These events led to new ageing management actions by both NPP operators and regulators. Therefore it was recognized that IAEA-TECDOC-1120 should be updated by incorporating those new events and their countermeasures. The objective of this report is to update IAEA-TECDOC-1120 in order to provide current ageing management guidance for PWR RPVs to all involved in the operation and regulation of PWRs and thus to help ensure PWR RPV integrity in IAEA Member States throughout their entire service life

  8. 33 CFR 151.1512 - Vessel safety.

    Science.gov (United States)

    2010-07-01

    ... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false Vessel safety. 151.1512 Section... River § 151.1512 Vessel safety. Nothing in this subpart relieves the master of the responsibility for ensuring the safety and stability of the vessel or the safety of the crew and passengers, or any other...

  9. Assessment and management of ageing of major nuclear power plant components important to safety: BWR pressure vessels

    International Nuclear Information System (INIS)

    2005-10-01

    At present, there are over four hundred operational nuclear power plants (NPPs) in IAEA Member States. Operating experience has shown that ineffective control of the ageing degradation of the major NPP components (caused for instance by unanticipated phenomena and by operating, maintenance or manufacturing errors) can jeopardize plant safety and also plant life. Ageing in these NPPs must be therefore effectively managed to ensure the availability of design functions throughout the plant service life. From the safety perspective, this means controlling, within acceptable limits, the ageing degradation and wear out of plant components important to safety so that adequate safety margins remain, i.e. integrity and functional capability in excess of normal operating requirements. This TECDOC is one in a series of reports on the assessment and management of ageing of the major NPP components important to safety. The reports are based on experience and practices of NPP operators, regulators, designers, manufacturers and technical support organizations and a widely accepted Methodology for the Management of Ageing of NPP Components Important to Safety, which was issued by the IAEA in 1992. Since the reports are written from a safety perspective, they do not address life or life cycle management of plant components, which involves economic considerations. The current practices for the assessment of safety margins (fitness for service) and the inspection, monitoring and mitigation of ageing degradation of selected components of Canada deuterium-uranium (CANDU) reactors, boiling water reactors (BWRs), pressurized water reactors (PWRs), and water moderated, water cooled energy reactors (WWERs) are documented in the reports. These practices are intended to help all involved directly and indirectly in ensuring the safe operation of NPPs, and also to provide a common technical basis for dialogue between plant operators and regulators when dealing with age related licensing issues

  10. Assessment and Management of ageing of major nuclear power plant components important to safety: PWR pressure vessels

    International Nuclear Information System (INIS)

    1999-10-01

    At present, there are over four hundred operational nuclear power plants (NPPs) in IAEA Member States. Operating experience has shown that ineffective control of the ageing degradation of the major NPP components (e.g., caused by unanticipated phenomena and by operating, maintenance or manufacturing errors) can jeopardize plant safety and also plant life. Ageing in these NPPs must be therefore effectively managed to ensure the availability of design functions throughout the plant service life. From the safety perspective, this means controlling within acceptable limits the ageing degradation and wear-out of plant components important to safety so that adequate safety margins remain, i.e. integrity and functional capability in excess of normal operating requirements. This TECDOC is one in a series of reports on the assessment and management of ageing of the major NPP components important to safety. The reports are based on experience and practices of NPP operators, regulators, designers, manufacturers and technical support organizations and a widely accepted Methodology for the Management of Ageing of NPP Components Important to Safety which was issued by the IAEA in 1992. The current practices for the assessment of safety margins (fitness-for-service) and the inspection, monitoring and mitigation of ageing degradation of selected components of Canada deuterium-uranium (CANDU) reactors, boiling water reactors (BWRs), pressurized water reactors (PWRs), including water moderated, water cooled energy reactors (WWERs) are documented in the reports. These practices are intended to help all involved directly and indirectly in ensuring the safe operation of NPPs; and also to provide a common technical basis for dialogue between plant operators and regulators when dealing with age related licensing issues. Since the reports are written from a safety perspective, they do not address life or life-cycle management of the plant components, which involves the integration of

  11. 15 CFR 970.205 - Vessel safety.

    Science.gov (United States)

    2010-01-01

    ... 15 Commerce and Foreign Trade 3 2010-01-01 2010-01-01 false Vessel safety. 970.205 Section 970.205... safety. In order to provide a basis for the necessary determinations with respect to the safety of life... Safety of Life at Sea, 1974 (SOLAS 74) possesses current valid SOLAS 74 certificates; (2) That any...

  12. Safety vessels for explosive fusion reactor

    International Nuclear Information System (INIS)

    Mineev, V.

    1994-01-01

    The failure of several types of geometrically similar cylindrical and spherical steel and glass fibers vessels filled with water or air was investigated when an explosive charge of TNT was detonated in the center. Vessels had radius 50-1000 mm, thickness of walls 2-20%. The detonation on TNT imitated energy release. The parameter: K = M/mf is a measure of the strength of the vessel where M is the mass of the vessel, and mf is the mass of TNT for which the vessel fails. This demanded 2-4 destroyed and nondestroyed shots. It may be showed that: K=A/σ f where σ f is the fracture stress of the material vessel, and A = const = F(energy TNT, characteristic of elasticity of vessel material). The chief results are the following: (1) A similar increase in the geometrical dimensions of steel vessels by a factor of 10 leads to the increase of parameter K in about 5 times and to decrease of failure deformation in 7 times (scale effect). (2) For glass fibers, scale effect is absent. (3) This problem is solved in terms of theory energetic scale effect. (4) The concept of TNT equivalent explosive makes it possible to use these investigations to evaluate the response of safety vessels for explosive fusion reactor

  13. Guidelines for pressure vessel safety assessment

    Science.gov (United States)

    Yukawa, S.

    1990-04-01

    A technical overview and information on metallic pressure containment vessels and tanks is given. The intent is to provide Occupational Safety and Health Administration (OSHA) personnel and other persons with information to assist in the evaluation of the safety of operating pressure vessels and low pressure storage tanks. The scope is limited to general industrial application vessels and tanks constructed of carbon or low alloy steels and used at temperatures between -75 and 315 C (-100 and 600 F). Information on design codes, materials, fabrication processes, inspection and testing applicable to the vessels and tanks are presented. The majority of the vessels and tanks are made to the rules and requirements of ASME Code Section VIII or API Standard 620. The causes of deterioration and damage in operation are described and methods and capabilities of detecting serious damage and cracking are discussed. Guidelines and recommendations formulated by various groups to inspect for the damages being found and to mitigate the causes and effects of the problems are presented.

  14. Safety of steel vessel Magnox pressure circuits

    International Nuclear Information System (INIS)

    Stokoe, T.Y.; Bolton, C.J.; Heffer, P.J.H.

    1991-01-01

    The maintenance of pressure circuit integrity is fundamental to nuclear safety at the steel vessel Magnox stations. To confirm continued pressure circuit integrity the CEGB, as part of the Long Term Safety Review, has carried out extensive assessment and inspection in recent years. The assessment methods and inspection techniques employed are based on the most modern available. Reactor pressure vessel integrity is confirmed by a combination of arguments including safety factors inferred from the successful pre-service overpressure test, leak-before-break analysis and probabilistic assessment. In the case of other parts of the pressure circuits that are more accessible, comprising the boiler shells and interconnecting gas duct work, in-service inspection is a major element of the safety substantiation. The assessment and inspection techniques and the materials property data have been underpinned for many years by extensive research and development programmes and in-reactor monitoring of representative samples has also been undertaken. The paper summarises the work carried out to demonstrate the long term integrity of the Magnox pressure circuits and provides examples of the results obtained. (author)

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

    International Nuclear Information System (INIS)

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

    2013-01-01

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

  16. 77 FR 37600 - Safety Zone; Arctic Drilling and Support Vessels, Puget Sound, WA

    Science.gov (United States)

    2012-06-22

    ... 1625-AA00 Safety Zone; Arctic Drilling and Support Vessels, Puget Sound, WA AGENCY: Coast Guard, DHS... are underway in the Puget Sound Captain of the Port Zone. The safety zone is necessary to ensure the... Ensign Anthony P. LaBoy, Waterways Management Division, Coast Guard Sector Puget Sound; Coast Guard...

  17. 33 CFR 96.220 - What makes up a safety management system?

    Science.gov (United States)

    2010-07-01

    ... system? 96.220 Section 96.220 Navigation and Navigable Waters COAST GUARD, DEPARTMENT OF HOMELAND SECURITY VESSEL OPERATING REGULATIONS RULES FOR THE SAFE OPERATION OF VESSELS AND SAFETY MANAGEMENT SYSTEMS Company and Vessel Safety Management Systems § 96.220 What makes up a safety management system? (a) The...

  18. 33 CFR 96.230 - What objectives must a safety management system meet?

    Science.gov (United States)

    2010-07-01

    ... management system meet? 96.230 Section 96.230 Navigation and Navigable Waters COAST GUARD, DEPARTMENT OF HOMELAND SECURITY VESSEL OPERATING REGULATIONS RULES FOR THE SAFE OPERATION OF VESSELS AND SAFETY MANAGEMENT SYSTEMS Company and Vessel Safety Management Systems § 96.230 What objectives must a safety...

  19. 33 CFR 96.250 - What documents and reports must a safety management system have?

    Science.gov (United States)

    2010-07-01

    ... safety management system have? 96.250 Section 96.250 Navigation and Navigable Waters COAST GUARD, DEPARTMENT OF HOMELAND SECURITY VESSEL OPERATING REGULATIONS RULES FOR THE SAFE OPERATION OF VESSELS AND SAFETY MANAGEMENT SYSTEMS Company and Vessel Safety Management Systems § 96.250 What documents and...

  20. 33 CFR 96.240 - What functional requirements must a safety management system meet?

    Science.gov (United States)

    2010-07-01

    ... a safety management system meet? 96.240 Section 96.240 Navigation and Navigable Waters COAST GUARD, DEPARTMENT OF HOMELAND SECURITY VESSEL OPERATING REGULATIONS RULES FOR THE SAFE OPERATION OF VESSELS AND SAFETY MANAGEMENT SYSTEMS Company and Vessel Safety Management Systems § 96.240 What functional...

  1. Safety margins of PWR irradiated vessels - The Chooz A issue

    Energy Technology Data Exchange (ETDEWEB)

    Hedin, F; Barthelet, B [Electricite de France (EDF), 75 - Paris (France); Guilleret, J C

    1988-12-31

    In 1986, some irradiated specimen of CHOOZ A (SENA) vessel showed a significant excess of {delta} RTNDT to former previsions. The lack of data on one of the two irradiated shells, and discrepancies between dosimeters results and available previous fluence calculations whose accuracy was questionable, cause the safety authorities to require an important complementary work program before putting again the plant on the grid after 1987 fuel reloading. These works are presented and discussed. They lead to a state that a conservative to day value of the vessel RTNDT is 64 degrees Celsius and that there is no underclad defect in the vessel wall and welds. Then the plant was allowed to restart with certitude that vessel irradiation will not impair its lifetime. (author). 4 refs.

  2. Initiation and arrest - two approaches to pressure vessel safety

    International Nuclear Information System (INIS)

    Brumovsky, M.; Filip, R.; Stepanek, S.

    1976-01-01

    The safety analysis is described of the reactor pressure vessel related to brittle fracture based on the fracture mechanics theory using two different approximations, i.e., the Crack Arrest Temperature (CAT) or Nil Ductility Temperature (NDT), and fracture toughness. The variation of CAT with stress was determined for different steel specimens of 120 to 200 mm in thickness. A diagram is shown of CAT variation with stress allowing the determination of crack arrest temperature for all types of commonly used steels independently of the NDT initial value. The diagram also shows that the difference between fracture transition elastic (FTE) and NDT depends on the type of material and determines the value of the ΔTsub(sigma) factor typical of the safety coefficient. The so-called fracture toughness reference value Ksub(IR) is recommended for the computation of pressure vessel criticality. Also shown is a defect analysis diagram which may be used for the calculation of pressure vessel safety prior to and during operation and which may also be used in making the decision on what crack sizes are critical, what cracks may be arrested and what cracks are likely to expand. The diagram is also important for the fact that it is material-independent and may be employed for the estimates of pre-operational and operational inspections and for pressure vessel life prediction. It is generally applicable to materials of greater thickness in the region where the validity of linear elastic fracture mechanics is guaranteed. (J.P.)

  3. Risk management and safety

    International Nuclear Information System (INIS)

    Niehaus, F.; Novegno, A.

    1985-01-01

    Risk assessment, including probabilistic analyses, has made great progress over the past decade. In spite of the inherent uncertainties it has now become possible to utilize methods and results for decision making at various levels. This paper will, therefore, review risk management in industrial installations, risk management for energy safety policy and prospects of risk management in highly industrialized areas. (orig.) [de

  4. Integral reactor vessel related to power reactor safety

    International Nuclear Information System (INIS)

    Widart, J.; Scailteur, A.

    1978-01-01

    Integral design applied to PWR pressure vessels allows to reach a high level of safety because: 1) it presents a better balance of the material in the geometry, resulting in an improved stress level (mainly faulted condition loadings); 2) location and geometry of the welds are designed in order to get a very sound pressure boundary of the upper part of the vessel; 3) the new location and geometry of the welds allow an easy ISI in such a way that ambiguity surrounding defect size or locaton is practically suppressed. (author)

  5. Managing electrical safety

    CERN Document Server

    Wiggins, James H, Jr

    2001-01-01

    Managing Electrical Safety provides an overview of electric basics, hazards, and established standards that enables you to understand the hazards you are likely to encounter in your workplace. Focusing on typical industrial environments-which utilize voltages much higher than household or office circuits-the author identifies the eight key components of an electrical safety program and examines each using a model safety management process. You'll learn how to identify electrical hazards, how to prescribe necessary electrical Personal Protective Equipment, how to ensure that equipment is de-ene

  6. Management of safety culture

    International Nuclear Information System (INIS)

    Kavsek, D.

    2004-01-01

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

  7. Analysis of aging mechanism and management for HTR-PM reactor pressure vessel

    International Nuclear Information System (INIS)

    Sun Yunxue; Shao Jin

    2015-01-01

    Reactor pressure vessel is an important part of the reactor pressure boundary, its important degree ranks high in ageing management and life assessment of nuclear power plant. Carrying out systematic aging management to ensure reactor pressure vessel keeping enough safety margins and executing design functions is one of the key factors to guarantee security and stability operation for nuclear power plant during the whole lifetime and prolong life. This paper briefly introduces the structure and aging mechanism of reactor pressure vessel in pressurized water reactor nuclear power plant, and introduces the design principle and structure characteristics of HTR-PM. At the same time, this paper carries out preliminary analysis and exploration. and discusses aging management of HTR-PM reactor pressure vessel. Finally, the advice of carring out aging management for HTR-PM reactor pressure vessel is proposed. (authors)

  8. Waste management safety

    International Nuclear Information System (INIS)

    Boehm, H.

    1983-01-01

    All studies carried out by competent authors of the safety of a waste management concept on the basis of reprocessing of the spent fuel elements and storage in the deep underground of the radioactive waste show that only a minor technical risk is involved in this step. This also holds true when evaluating the accidents which have occurred in waste management facilities. To explain the risk, first the completely different safety aspects of nuclear power plants, reprocessing plants and repositories are outlined together with the safety related characteristics of these plants. Also this comparison indicates that the risk of waste management facilities is considerably lower than the, already very small, risk of nuclear power plants. For the final storage of waste from reprocessing and for the direct storage of fuel elements, the results of safety analyses show that the radiological exposure following an accident with radioactivity releases, even under conservative assumptions, is considerably below the natural radiation exposure. The very small danger to the environment arising from waste management by reprocessing clearly indicates that aspects of technical safety alone will hardly be a major criterion for the decision in favor of one or the other waste management approach. (orig.) [de

  9. Facilities management and industrial safety

    International Nuclear Information System (INIS)

    2003-06-01

    This book lists occupation safety and health acts with purpose, definition and management system of safety and health, enforcement ordinance of occupation safety and health acts and enforcement regulations such as general rules, safety and health cover, system of management on safety and health, regulation of management on safety and health, regulations of harmfulness and protection of danger, heath management for workers, supervisor and command and inspection of machine and equipment.

  10. Reactor pressure vessels safety and reliability - certainty and uncertainty

    International Nuclear Information System (INIS)

    O'Neil, R.

    1977-01-01

    In the paper, it is suggested that the hazard to the population which would result from vessel failure rate of the order of 10 -6 to 10 -7 per vessel year could be acceptable to society on the basis of other natural and man-made risks. The paper considers the problems of demonstrating safety by calculation based on fracture mechanics, and indicates some of the uncertainties, and inconsistencies in the theory, particularly the effect of cracks in locally degraded volumes of material. The phenomenon of crack arrest is considered, and attention is drawn to the uncertainties as indicated at least by some tests. There is need for speedy resolution of this problem. The uncertainties in material properties, heat treatment and residual stresses are considered, and a proposed upper limit for residual defects ('original sin') is proposed. (orig.) [de

  11. 77 FR 35271 - Safety Zone; NOAA Vessel Rueben Lasker Launch, Marinette, WI

    Science.gov (United States)

    2012-06-13

    ...-AA00 Safety Zone; NOAA Vessel Rueben Lasker Launch, Marinette, WI AGENCY: Coast Guard, DHS. ACTION... during the launching of the NOAA vessel, Rueben Lasker, on June 16, 2012. This temporary safety zone is... preceding paragraph, a 30 day notice period would also be impractical. B. Basis and Purpose The NOAA vessel...

  12. FLUOR HANFORD SAFETY MANAGEMENT PROGRAMS

    Energy Technology Data Exchange (ETDEWEB)

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

    2004-04-13

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

  13. Safety Domain Measurement for Vessels in an Overtaking Situation

    Directory of Open Access Journals (Sweden)

    Hua-Zhi Hsu

    2014-12-01

    Full Text Available Marine traffic engineering has been pushed to the limits due to a rising demand in the shipping business. Merchant ships are growing dramatically, both in numbers and in size. To keep pace with current developments, automation seems to be one viable option when it comes to keeping ships running with fewer seafarers available. The aim of this paper is to monitor a modern day mariners’ performance while working in a tense situation. The objective is to define the size of the safety domain whilst overtaking a vessel. The approach was to assess the ship's domain area within a 3 nm wide traffic separation scheme by using a ship handling simulator. From the simulation results, an overtaking domain was determined as 1.36 nm long and 0.4 nm wide. Safety domains in real-life situations were experienced on a much smaller scale compared to the previous findings. The working load for this particular operation is expected to be stressful and highly skilled orientated.

  14. Study of industry safety management

    International Nuclear Information System (INIS)

    Park, Pil Su

    1987-06-01

    This book deals with general remarks, industrial accidents, statistics of industrial accidents, unsafe actions, making machinery and facilities safe, safe activities, having working environment safe, survey of industrial accidents and analysis of causes, system of safety management and operations, safety management planning, safety education, human engineering such as human-machines system, system safety, and costs of disaster losses. It lastly adds individual protective equipment and working clothes including protect equipment for eyes, face, hands, arms and feet.

  15. 78 FR 76751 - Safety Zone; Vessel Launch; Menominee River; Marinette, WI

    Science.gov (United States)

    2013-12-19

    ...-AA00 Safety Zone; Vessel Launch; Menominee River; Marinette, WI AGENCY: Coast Guard, DHS. ACTION: Temporary final rule. SUMMARY: The Coast Guard is establishing a temporary safety zone on the Menominee River in Marinette, Wisconsin. This zone is intended to restrict vessels from a portion of the Menominee...

  16. 77 FR 60042 - Safety Zone; Research Vessel SIKULIAQ Launch, Marinette, WI

    Science.gov (United States)

    2012-10-02

    ...: Temporary final rule. SUMMARY: The Coast Guard is establishing a temporary safety zone on the Menominee River in Marinette Wisconsin. This zone is intended to restrict vessels from a portion of Menominee River during the launching of the Research vessel SIKULIAQ, on October 13th, 2012. This temporary safety...

  17. 77 FR 3115 - Safety Zone; Grain-Shipment Vessels, Columbia and Snake Rivers

    Science.gov (United States)

    2012-01-23

    ...-AA00 Safety Zone; Grain-Shipment Vessels, Columbia and Snake Rivers AGENCY: Coast Guard, DHS. ACTION... Terminal, Longview, WA, while they are located on the Columbia and Snake Rivers. This safety zone extends... on the Columbia and Snake rivers when vessels begin arriving at EGT, Longview, WA. Under 5 U.S.C. 553...

  18. 76 FR 27897 - Security and Safety Zone Regulations, Large Passenger Vessel Protection, Captain of the Port...

    Science.gov (United States)

    2011-05-13

    ... DEPARTMENT OF HOMELAND SECURITY Coast Guard 33 CFR Part 165 [Docket No. USCG-2011-0342] Security and Safety Zone Regulations, Large Passenger Vessel Protection, Captain of the Port Columbia River... will enforce the security and safety zone in 33 CFR 165.1318 for large passenger vessels operating in...

  19. Safety of nuclear pressure vessels and its regulatory aspects in France

    Energy Technology Data Exchange (ETDEWEB)

    de Torquat, G; Queniart, D; Barrachin, B; Roche, R

    1979-01-01

    Having outlined the basic French regulations governing the safety of both pressure vessels and also of nuclear installations in general the particular safety regulations covering prestressed concrete vessels for nuclear reactors are considered. The regulations now being prepared to cover heat transfer systems of water reactors are detailed under sections headed; general provisions, sizing, and construction.

  20. FOOD QUALITY MANAGEMENT AND SAFETY

    OpenAIRE

    Rizwana Khatoon; Debkumar Chakraborty; R.C. Chandni; Amar Sankar; A.V. Raghu

    2017-01-01

    Food safety system mainly focuses on identifying and preventing hazards that may lead product to deteriorate. The main important of manufacturing practice is a system that ensures that products meet food safety, quality and legal requirements. The hazard analysis and critical control point system, applies to food safety management, uses the approach of controlling critical points in food handling to prevent food safety problems. Besides enhancing food safety, other benefits of applying HACCP ...

  1. Vessel Biofouling Prevention and Management Options Report

    Science.gov (United States)

    2015-03-01

    microorganism -containing biofilm (slime layer) which occurs on a marine surface under the right conditions. Biofilm growth can progress to a point where... biodegradable components, or non-biocidal alternatives; vessels that reside or operate >30 days in copper impaired ports or harbors shall consider alternatives...except for nontoxic, biodegradable types) or chemicals in the water is prohibited, as would be the creation of a cloud or plume generated by paint

  2. Demarcation of inland vessels' limit off Mormugao port region, India: A pilot study for the safety of inland vessels using wave modelling

    Digital Repository Service at National Institute of Oceanography (India)

    Vethamony, P.; Aboobacker, V.M.; Sudheesh, K.; Babu, M.T.; AshokKumar, A.

    The Ministry of Shipping desires to revise the inland vessels' limit (IVL) notification based on scientific rationale to improve the safety of vessels and onboard personnel. The Mormugao port region extending up to the Panaji was considered...

  3. 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)

  4. Reactor pressure vessel stud management automation strategies

    International Nuclear Information System (INIS)

    Biach, W.L.; Hill, R.; Hung, K.

    1992-01-01

    The adoption of hydraulic tensioner technology as the standard for bolting and unbolting the reactor pressure vessel (RPV) head 35 yr ago represented an incredible commitment to new technology, but the existing technology was so primitive as to be clearly unacceptable. Today, a variety of approaches for improvement make the decision more difficult. Automation in existing installations must meet complex physical, logistic, and financial parameters while addressing the demands of reduced exposure, reduced critical path, and extended plant life. There are two generic approaches to providing automated RPV stud engagement and disengagement: the multiple stud tensioner and automated individual tools. A variation of the latter would include the handling system. Each has its benefits and liabilities

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

    International Nuclear Information System (INIS)

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

    2007-01-01

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

  6. 33 CFR 165.121 - Safety and Security Zones: High Interest Vessels, Narragansett Bay, Rhode Island.

    Science.gov (United States)

    2010-07-01

    ... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false Safety and Security Zones: High... COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) PORTS AND WATERWAYS SAFETY REGULATED NAVIGATION... Guard District § 165.121 Safety and Security Zones: High Interest Vessels, Narragansett Bay, Rhode...

  7. A total safety management model

    International Nuclear Information System (INIS)

    Obadia, I.J.; Vidal, M.C.R.; Melo, P.F.F.F.

    2002-01-01

    In nuclear organizations, quality and safety are inextricably linked. Therefore, the search for excellence means reaching excellence in nuclear safety. The International Atomic Energy Agency, IAEA, developed, after the Chernobyl accident, the organizational approach for improving nuclear safety based on the safety culture, which requires a framework necessary to provide modifications in personnel attitudes and behaviors in situations related to safety. This work presents a Total Safety Management Model, based on the Model of Excellence of the Brazilian Quality Award and on the safety culture approach, which represents an alternative to this framework. The Model is currently under validation at the Nuclear Engineering Institute, in Rio de Janeiro, Brazil, and the results of its initial safety culture self assessment are also presented and discussed. (author)

  8. Safety Climate, Perceived Risk, and Involvement in Safety Management

    OpenAIRE

    Kouabenan , Dongo Rémi; Ngueutsa , Robert ,; Safiétou , Mbaye

    2015-01-01

    International audience; This article examines the relationship between safety climate, risk perception and involvement in safety management by first-line managers (FLM). Sixty-three FLMs from two French nuclear plants answered a questionnaire measuring perceived workplace safety climate, perceived risk, and involvement in safety management. We hypothesized that a positive perception of safety climate would promote substantial involvement in safety management, and that this effect would be str...

  9. 78 FR 68995 - Safety Zone: Vessel Removal From the Oakland Estuary, Alameda, CA

    Science.gov (United States)

    2013-11-18

    ...-AA00 Safety Zone: Vessel Removal From the Oakland Estuary, Alameda, CA AGENCY: Coast Guard, DHS. ACTION... waters of the Oakland Estuary just north of the Park Street Bridge in Alameda, CA in support of the Oakland Estuary Closure for the Vessel Removal Project on November 4, 2013 through November 22, 2013. This...

  10. Running Safety of Trains under Vessel-Bridge Collision

    Directory of Open Access Journals (Sweden)

    Yongle Li

    2015-01-01

    Full Text Available To optimize the sensor placement of the health monitoring system, the dynamic behavior of the train-bridge system subjected to vessel-collision should be studied in detail firstly. This study thus focuses on the characteristics of a train-bridge system under vessel-bridge collision. The process of the vessel-bridge collision is simulated numerically with a reliable finite element model (FEM. The dynamic responses of a single car and a train crossing a cable-stayed bridge are calculated. It is shown that the collision causes significant increase of the train’s lateral acceleration, lateral wheelset force, wheel unloading rate, and derailment coefficient. The effect of the collision on the train’s vertical acceleration is much smaller. In addition, parametric studies with various train’s positions, ship tonnage, and train speed are performed. If the train is closer to the vessel-bridge collision position or the ship tonnage is larger, the train will be more dangerous. There is a relatively high probability of running danger at a low speed, resulting from longer stay of the train on the bridge. The train’s position, the ship tonnage, and the train speed must be considered when determining the most adverse conditions for the trains running on bridges under vessel-bridge collision.

  11. 33 CFR 151.2037 - If my vessel cannot conduct ballast water management practices because of its voyage and/or...

    Science.gov (United States)

    2010-07-01

    ... ballast water management practices because of its voyage and/or safety concerns, will I be prohibited from... is inoperable must employ one of the other ballast water management practices stated in § 151.2035(b). If the vessel cannot employ other ballast water management practices due to voyage or safety concerns...

  12. Use of probabilistic safety analyses in severe accident management

    International Nuclear Information System (INIS)

    Neogy, P.; Lehner, J.

    1991-01-01

    An important consideration in the development and assessment of severe accident management strategies is that while the strategies are often built on the knowledge base of Probabilistic Safety Analyses (PSA), they must be interpretable and meaningful in terms of the control room indicators. In the following, the relationships between PSA and severe accident management are explored using ex-vessel accident management at a PWR ice-condenser plant as an example. 2 refs., 1 fig., 3 tabs

  13. 76 FR 31350 - Cruise Vessel Safety and Security Act of 2010, Available Technology

    Science.gov (United States)

    2011-05-31

    ... DEPARTMENT OF HOMELAND SECURITY Coast Guard [Docket No. USCG-2011-0357] Cruise Vessel Safety and Security Act of 2010, Available Technology AGENCY: Coast Guard, DHS. ACTION: Notice of request for comments... Security and Safety Act of 2010(CVSSA), specifically related to video recording and overboard detection...

  14. Nuclear safety management at the Wolsong NGS

    Energy Technology Data Exchange (ETDEWEB)

    Bong-Seob, Han [Korea Electric Power Corp., Wolson NPP no. 1 and 2 (Korea, Republic of)

    1997-12-01

    Nuclear safety management at the Wolsong nuclear power plant is described, including the following issues: site selection; plant history; operational goals; operational guidelines; reactor safety; safety training; plant maintenance; management of plant equipment lifetime; future tasks.

  15. Nuclear safety management at the Wolsong NGS

    International Nuclear Information System (INIS)

    Han Bong-Seob

    1997-01-01

    Nuclear safety management at the Wolsong nuclear power plant is described, including the following issues: site selection; plant history; operational goals; operational guidelines; reactor safety; safety training; plant maintenance; management of plant equipment lifetime; future tasks

  16. Leadership and Management for Safety. General Safety Requirements (Spanish Edition)

    International Nuclear Information System (INIS)

    2017-01-01

    his Safety Requirements publication establishes requirements that support Principle 3 of the Fundamental Safety Principles in relation to establishing, sustaining and continuously improving leadership and management for safety and an integrated management system. It emphasizes that leadership for safety, management for safety, an effective management system and a systemic approach (i.e. an approach in which interactions between technical, human and organizational factors are duly considered) are all essential to the specification and application of adequate safety measures and to the fostering of a strong safety culture. Leadership and an effective management system will integrate safety, health, environmental, security, quality, human-and-organizational factors, societal and economic elements. The management system will ensure the fostering of a strong safety culture, regular assessment of performance and the application of lessons from experience. The publication is intended for use by regulatory bodies, operating organizations and other organizations concerned with facilities and activities that give rise to radiation risks.

  17. Leadership and Management for Safety. General Safety Requirements (French Edition)

    International Nuclear Information System (INIS)

    2016-01-01

    This Safety Requirements publication establishes requirements that support Principle 3 of the Fundamental Safety Principles in relation to establishing, sustaining and continuously improving leadership and management for safety and an integrated management system. It emphasizes that leadership for safety, management for safety, an effective management system and a systemic approach (i.e. an approach in which interactions between technical, human and organizational factors are duly considered) are all essential to the specification and application of adequate safety measures and to the fostering of a strong safety culture. Leadership and an effective management system will integrate safety, health, environmental, security, quality, human-and-organizational factors, societal and economic elements. The management system will ensure the fostering of a strong safety culture, regular assessment of performance and the application of lessons from experience. The publication is intended for use by regulatory bodies, operating organizations and other organizations concerned with facilities and activities that give rise to radiation risks.

  18. Leadership and Management for Safety. General Safety Requirements (Arabic Edition)

    International Nuclear Information System (INIS)

    2016-01-01

    This Safety Requirements publication establishes requirements that support Principle 3 of the Fundamental Safety Principles in relation to establishing, sustaining and continuously improving leadership and management for safety and an integrated management system. It emphasizes that leadership for safety, management for safety, an effective management system and a systemic approach (i.e. an approach in which interactions between technical, human and organizational factors are duly considered) are all essential to the specification and application of adequate safety measures and to the fostering of a strong safety culture. Leadership and an effective management system will integrate safety, health, environmental, security, quality, human-and-organizational factors, societal and economic elements. The management system will ensure the fostering of a strong safety culture, regular assessment of performance and the application of lessons from experience. The publication is intended for use by regulatory bodies, operating organizations and other organizations concerned with facilities and activities that give rise to radiation risks.

  19. Leadership and Management for Safety. General Safety Requirements (Chinese Edition)

    International Nuclear Information System (INIS)

    2016-01-01

    This Safety Requirements publication establishes requirements that support Principle 3 of the Fundamental Safety Principles in relation to establishing, sustaining and continuously improving leadership and management for safety and an integrated management system. It emphasizes that leadership for safety, management for safety, an effective management system and a systemic approach (i.e. an approach in which interactions between technical, human and organizational factors are duly considered) are all essential to the specification and application of adequate safety measures and to the fostering of a strong safety culture. Leadership and an effective management system will integrate safety, health, environmental, security, quality, human-and-organizational factors, societal and economic elements. The management system will ensure the fostering of a strong safety culture, regular assessment of performance and the application of lessons from experience. The publication is intended for use by regulatory bodies, operating organizations and other organizations concerned with facilities and activities that give rise to radiation risks.

  20. Leadership and Management for Safety. General Safety Requirements

    International Nuclear Information System (INIS)

    2016-01-01

    This Safety Requirements publication establishes requirements that support Principle 3 of the Fundamental Safety Principles in relation to establishing, sustaining and continuously improving leadership and management for safety and an integrated management system. It emphasizes that leadership for safety, management for safety, an effective management system and a systemic approach (i.e. an approach in which interactions between technical, human and organizational factors are duly considered) are all essential to the specification and application of adequate safety measures and to the fostering of a strong safety culture. Leadership and an effective management system will integrate safety, health, environmental, security, quality, human-and-organizational factor, societal and economic elements. The management system will ensure the fostering of a strong safety culture, regular assessment of performance and the application of lessons from experience. The publication is intended for use by regulatory bodies, operating organizations (registrants and licensees) and other organizations concerned with facilities and activities that give rise to radiation risks

  1. MARS vessel safety analysis. LATA report No. 115

    International Nuclear Information System (INIS)

    Rigdon, L.D.; Donham, B.J.; Hughes, P.S.

    1979-08-01

    A previous study was performed to assess the hazards associated with an accidental leakage of cooling water into the crucible of molten 238 U for the MARS laser isotope separation experiment. Since that study found that the probability of such an explosion is extremely low during an accidental cooling system failure, a study was conducted to define a more realistic design basis accident (DBA) for the final MARS configuration. If the vapor-phase explosion is considered to be a significant threat, the design criteria for the vacuum vessel should be a working pressure of 67 psig or 101 psig momentary single pulse equivalent static pressure

  2. Safety management in the industry

    International Nuclear Information System (INIS)

    Jaecklin, A.

    1996-01-01

    The safety management in the industry is characterised by the large number of processes and the materials used in them. Correspondingly large are the legal regulations. Through the thickets of today's controls, the industry moves inside a relatively tight network of technical regulations. The experience of environmental audits and industrial damage, however, shows that the greatest deficit lies in the organisational methods and less on the technical side. For the overcoming of risks one needs to recognise the weaknesses of a careful analysis. To this belongs the estimation of how far a possible scenario can be taken. The estimation of the possibilities of occurrence, however, comes up against particular problems in the industry, as the human factor in relationship with danger potentialities is very difficult to evaluate. Actual basic data or statistics are missing. This lack can only be made good with the building up of a safety management. The fundamental principles of such a management can be taken from the environmental management and especially from the standard for environmental management ISO 14001. Here it is important that safety management is integrated into the process-oriented business processes and thus becomes a part of the company culture. (author) 11 figs., tabs., 11 refs

  3. Food quality and safety management

    Directory of Open Access Journals (Sweden)

    Agnieszka Bilska

    2014-09-01

    Full Text Available Ensuring quality and safety of food are nowadays the most important goals set by companies who produce and distribute it. As a result, regulations have been introduced in the European Union countries concerning the production and distribution of food as well as norms which oblige companies to implement and execute several quality management systems.

  4. 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.

  5. 33 CFR 96.340 - Safety Management Certificate: what is it and when is it needed?

    Science.gov (United States)

    2010-07-01

    ... Safety Management Certificate: what is it and when is it needed? (a) Your U.S. vessel engaged on a... 33 Navigation and Navigable Waters 1 2010-07-01 2010-07-01 false Safety Management Certificate: what is it and when is it needed? 96.340 Section 96.340 Navigation and Navigable Waters COAST GUARD...

  6. 33 CFR 96.320 - What is involved to complete a safety management audit and when is it required to be completed?

    Science.gov (United States)

    2010-07-01

    ... Safety Management (ISM) Code by Administrations. (3) Make sure the audit is carried out by a team of... safety management audit and when is it required to be completed? 96.320 Section 96.320 Navigation and... SAFE OPERATION OF VESSELS AND SAFETY MANAGEMENT SYSTEMS How Will Safety Management Systems Be...

  7. Probabilistic Assessment of the Design and Safety of HSLA-100 Steel Confinement Vessels

    Energy Technology Data Exchange (ETDEWEB)

    R.M. Dolin

    2003-03-03

    This probabilistic approach for assessing the design and safety of the HSLA-100 steel confinement vessel used for a DynEx test involved the probability of failure for several scenarios, in which a fragment may penetrate the vessel. The samples involve vessel thicknesses of 1 inch, 2 inches, and 5.25 inches--the combined thicknesses of the 2 inch containment vessel and the 3.25 inch safety vessel. Two simulation approaches were used for each scenario to assess the probability of failure. The Likelihood of Occurrence method simultaneously models all likely fragment events of a test, for which the net probability of failure is the sum of all the fragment events. The Stochastic Sampling method determines the probability of a fragment perforation on the basis of a logical model and takes the overall probability that an experiment results in failure as the maximum probability for any fragment event. With margin and safety assessments taken into account, it was concluded that the one and two inch thicknesses by themselves are inadequate for containing a DynEx test. The 5.25 inch thickness was determined to be safe by the Likelihood of Occurrence method and nearly adequate by the Stochastic Sampling simulation.

  8. Status Report on Ex-Vessel Coolability and Water Management

    Energy Technology Data Exchange (ETDEWEB)

    Farmer, M. T. [Argonne National Lab. (ANL), Argonne, IL (United States). Nuclear Engineering Division; Robb, K. R. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2016-09-15

    Specific to BWR plants, current accident management guidance calls for flooding the drywell to a level of approximately 1.2 m (4 feet) above the drywell floor once vessel breach has been determined. While this action can help to submerge ex-vessel core debris, it can also result in flooding the wetwell and thereby rendering the wetwell vent path unavailable. An alternate strategy is being developed in the industry guidance for responding to the severe accident capable vent Order, EA-13-109. The alternate strategy being proposed would throttle the flooding rate to achieve a stable wetwell water level while preserving the wetwell vent path. The overall objective of this work is to upgrade existing analytical tools (i.e. MELTSPREAD and CORQUENCH - which have been used as part of the DOE-sponsored Fukushima accident analyses) in order to provide flexible, analytically capable, and validated models to support the development of water throttling strategies for BWRs that are aimed at keeping ex-vessel core debris covered with water while preserving the wetwell vent path.

  9. Managing nuclear safety at Point Lepreau

    Energy Technology Data Exchange (ETDEWEB)

    Paciga, J [New Brunswick Power, Point Lepreau NGS, PQ (Canada)

    1997-12-01

    Managing nuclear safety at Point Lepreau nuclear power plant is described, including technical issues (station aging, definition of the safe operating envelope, design configuration management, code validation, safety analysis and engineering standards); regulatory issues (action items, probabilistic safety assessment, event investigation, periodic safety review, prioritization of regulatory issues, cost benefit assessment); human performance issues (goals and measures, expectations and accountability, supervisory training, safety culture, configuration management, quality of operations and maintenance).

  10. Managing nuclear safety at Point Lepreau

    International Nuclear Information System (INIS)

    Paciga, J.

    1997-01-01

    Managing nuclear safety at Point Lepreau nuclear power plant is described, including technical issues (station aging, definition of the safe operating envelope, design configuration management, code validation, safety analysis and engineering standards); regulatory issues (action items, probabilistic safety assessment, event investigation, periodic safety review, prioritization of regulatory issues, cost benefit assessment); human performance issues (goals and measures, expectations and accountability, supervisory training, safety culture, configuration management, quality of operations and maintenance)

  11. French nuclear plants PWR vessel integrity assessment and life management

    Energy Technology Data Exchange (ETDEWEB)

    Bezdikian, G. [Electricite de France (EDF), Div. Production Nucleaire, 93 - Saint-Denis (France); Quinot, P. [FRAMATOME, Dept. Bloc Reacteur et Boucles Primaires, 92 - Paris-La-Defence (France); Faidy, C.; Churier-Bossennec, H. [Electricite de France (EDF), Div. Ingenierie et Service, 69 - Villeurbanne (France)

    2001-07-01

    The Reactor Pressure Vessel life management of 56 PWR 3 loop and 4 loop reactors units was engaged by the French Utility EDF (Electricite de France) a few years ago and is yet on going on. This paper will present the work carried out within the framework of justifying why the 34 three loop reactor vessels will remain acceptable for operation for a lifetime of at least 40-years. A summary of the measures will be given. An overall review of actions will be presented describing the French approach, using important existing databases, including studies related to irradiation surveillance monitoring program and end of life fluence assessment. The last results obtained are based on generic integrity analyses for all categories of situations (normal upset emergency and faulted conditions) until the end of lifetime, postulating circumferential an radial kinds of flaw located in the stainless steel cladding or shallow sub-cladding area. The results of structural integrity analyses beginning with elastic computations and completed with three-dimensional finite element elastic plastic computations for envelope cases, are compared with code criteria for operating plants. The objective is to evaluate the margins on different parameters as RTNDT (Reference Nil Ductility Transition Temperature), toughness or crack size, to justify the global fitness for service of all these Reactor Pressure Vessels. The paper introduces EDF's maintenance strategy, related to integrity assessment, for those nuclear power plants under operation, based on NDE in-service inspection of the first thirty millimeters in the thickness of the wall and major surveillance programs of the vessels. (author)

  12. French nuclear plants PWR vessel integrity assessment and life management

    International Nuclear Information System (INIS)

    Bezdikian, G.; Quinot, P.; Faidy, C.; Churier-Bossennec, H.

    2001-01-01

    The Reactor Pressure Vessel life management of 56 PWR 3 loop and 4 loop reactors units was engaged by the French Utility EDF (Electricite de France) a few years ago and is yet on going on. This paper will present the work carried out within the framework of justifying why the 34 three loop reactor vessels will remain acceptable for operation for a lifetime of at least 40-years. A summary of the measures will be given. An overall review of actions will be presented describing the French approach, using important existing databases, including studies related to irradiation surveillance monitoring program and end of life fluence assessment. The last results obtained are based on generic integrity analyses for all categories of situations (normal upset emergency and faulted conditions) until the end of lifetime, postulating circumferential an radial kinds of flaw located in the stainless steel cladding or shallow sub-cladding area. The results of structural integrity analyses beginning with elastic computations and completed with three-dimensional finite element elastic plastic computations for envelope cases, are compared with code criteria for operating plants. The objective is to evaluate the margins on different parameters as RTNDT (Reference Nil Ductility Transition Temperature), toughness or crack size, to justify the global fitness for service of all these Reactor Pressure Vessels. The paper introduces EDF's maintenance strategy, related to integrity assessment, for those nuclear power plants under operation, based on NDE in-service inspection of the first thirty millimeters in the thickness of the wall and major surveillance programs of the vessels. (author)

  13. Reducing the risk, managing safety.

    Science.gov (United States)

    Aldridge, Peter

    2016-02-01

    Fire safety in healthcare premises has always been a challenge to those that discharge this duty. Statutory compliance should be a matter of course, but in an ever increasingly challenged NHS, even this is not a given. While the NHS is driven by managing very complex risk to deliver cutting edge healthcare, providers cannot be risk averse. Which risk, however, takes priority? Here Peter Aldridge, fire and corporate services manager at Leeds Teaching Hospitals NHS Trust, and Secretary to the National Association of Healthcare Fire Officers (NAHFO)--which will this month and next jointly stage fire safety seminars with IHEEM; see page 8--considers the key issues, with input from a fire officer at a leading mental health and community Trust.

  14. Test of safety injection supply by diesel generator under reactor vessel closed condition

    International Nuclear Information System (INIS)

    Zhang Hao; Bi Fengchuan; Che Junxia; Zhang Jianwen; Yang Bo

    2014-01-01

    The paper studied that the test of diesel generator full load take-up under the condition of actual safety injection and reactor vessel closed in Ningde nuclear project unit l. It is proved that test result accorded with design criteria, meanwhile, the test was removed from the key path of project schedule, which cut a huge cost. (authors)

  15. 75 FR 14609 - Commercial Fishing Industry Vessel Safety Advisory Committee; Vacancies

    Science.gov (United States)

    2010-03-26

    ... which Chapter 45 of Title 46, U.S.C. applies and persons representing the marine insurance industry... Industry Vessel Safety Advisory Committee; Vacancies AGENCY: Coast Guard, DHS. ACTION: Request for applications. SUMMARY: The Coast Guard seeks applications for membership on the Commercial Fishing Industry...

  16. 78 FR 42452 - Safety Zone; Kentucky Air National Guard Vessel for Parachute Rescue Jumpmaster Training, Lake...

    Science.gov (United States)

    2013-07-16

    ... only a few hours at a time during any 24 hour period. The majority of the training exercises will be... greatly reducing the likelihood of affecting transient recreational vessels. Additionally, the starting... Health Risks and Safety Risks. This rule is not an economically significant rule and does not create an...

  17. The role of PSA in safety management

    International Nuclear Information System (INIS)

    Szikszai, T.

    1997-01-01

    The presentation discusses the following issues: defence in depth principle (the role of the barriers, how does PSA represents the barriers?); the safety management and nuclear power plants; the probabilistic and deterministic approaches; the PSA applications and safety management

  18. Implementation of the safety culture for HANARO safety management

    International Nuclear Information System (INIS)

    Wu, Jong Sup; Han, Gee Yang; Kim, Ik Soo

    2008-01-01

    Safety is the fundamental principal upon which a management system is based. The IAEA INSAG(International Nuclear Safety Group) states the general aims of a safety management system. One of which is to foster and support a strong safety culture through the development and reinforcement of good safety attitudes and behavior in individuals and teams, so as to allow them to carry out their tasks safety. The safety culture activities have been implemented and the importance of a safety management in nuclear activities for a reactor application and utilization has also been emphasized for more than 10 years in HANARO which is a 30 MW multi purpose research reactor that achieved its first criticality in February 1995. The safety culture activities and implementation have been conducted continuously to enhance its safe operation such as the seminars and lectures related to safety matters, participation in international workshops and the development of safety culture indicators, a survey on the attitude of HANARO staff toward the safety culture indicators, a survey on the attitude of HANARO staff toward the safety culture, the development of operational safety performance indicators (SPIs), the preparation of a safety text book and the development of an e Learning program for a safety education purpose

  19. Implementation of the safety culture for HANARO safety management

    Energy Technology Data Exchange (ETDEWEB)

    Wu, Jong Sup; Han, Gee Yang; Kim, Ik Soo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2008-11-15

    Safety is the fundamental principal upon which a management system is based. The IAEA INSAG(International Nuclear Safety Group) states the general aims of a safety management system. One of which is to foster and support a strong safety culture through the development and reinforcement of good safety attitudes and behavior in individuals and teams, so as to allow them to carry out their tasks safety. The safety culture activities have been implemented and the importance of a safety management in nuclear activities for a reactor application and utilization has also been emphasized for more than 10 years in HANARO which is a 30 MW multi purpose research reactor that achieved its first criticality in February 1995. The safety culture activities and implementation have been conducted continuously to enhance its safe operation such as the seminars and lectures related to safety matters, participation in international workshops and the development of safety culture indicators, a survey on the attitude of HANARO staff toward the safety culture indicators, a survey on the attitude of HANARO staff toward the safety culture, the development of operational safety performance indicators (SPIs), the preparation of a safety text book and the development of an e Learning program for a safety education purpose.

  20. 78 FR 33224 - Safety Zone; Grain-Shipment and Grain-Shipment Assist Vessels, Columbia and Willamette Rivers

    Science.gov (United States)

    2013-06-04

    ... 1625-AA00 Safety Zone; Grain-Shipment and Grain-Shipment Assist Vessels, Columbia and Willamette Rivers... Guard is establishing a temporary safety zone around all inbound and outbound grain-shipment and grain-shipment assist vessels involved in commerce with the Columbia Grain facility on the Willamette River in...

  1. 78 FR 57261 - Safety Zone; Grain-Shipment and Grain-Shipment Assist Vessels, Columbia and Willamette Rivers

    Science.gov (United States)

    2013-09-18

    ... 1625-AA00 Safety Zone; Grain-Shipment and Grain-Shipment Assist Vessels, Columbia and Willamette Rivers... temporary safety zone around all inbound and outbound grain-shipment and grain-shipment assist vessels involved in commerce with the Columbia Grain facility on the Willamette River in Portland, OR, the United...

  2. Implementation of the safety culture for HANARO Safety Management

    International Nuclear Information System (INIS)

    Wu, Jongsup; Han, Geeyang; Kim, Iksoo

    2008-01-01

    Safety is the fundamental principal upon which the management system is based. The IAEA INSAG(International Nuclear Safety Group) states the general aims of the safety management system. One of which is to foster and support a strong safety culture through the development and reinforcement of good safety attitudes and behavior in individuals and teams so as to allow them to carry out their tasks safety. The safety culture activities have been implemented and the importance of safety management in nuclear activities for a reactor application and utilization has also been emphasized more than 10 years in HANARO which is a 30 MW multi-purpose research reactor and achieved its first criticality in February 1995. The safety culture activities and implementations have been conducted continuously to enhance its safe operation like the seminars and lectures related to safety matters, participation in international workshops, the development of safety culture indicators, the survey on the attitude of safety culture, the development of operational safety performance indicators (SPIs), the preparation of a safety text book and the development of an e-Learning program for safety education. (author)

  3. Safety analysis of nuclear containment vessels subjected to strong earthquakes and subsequent tsunamis

    Directory of Open Access Journals (Sweden)

    Feng Lin

    2017-08-01

    Full Text Available Nuclear power plants under expansion and under construction in China are mostly located in coastal areas, which means they are at risk of suffering strong earthquakes and subsequent tsunamis. This paper presents a safety analysis for a new reinforced concrete containment vessel in such events. A finite element method-based model was built, verified, and first used to understand the seismic performance of the containment vessel under earthquakes with increased intensities. Then, the model was used to assess the safety performance of the containment vessel subject to an earthquake with peak ground acceleration (PGA of 0.56g and subsequent tsunamis with increased inundation depths, similar to the 2011 Great East earthquake and tsunami in Japan. Results indicated that the containment vessel reached Limit State I (concrete cracking and Limit State II (concrete crushing when the PGAs were in a range of 0.8–1.1g and 1.2–1.7g, respectively. The containment vessel reached Limit State I with a tsunami inundation depth of 10 m after suffering an earthquake with a PGA of 0.56g. A site-specific hazard assessment was conducted to consider the likelihood of tsunami sources.

  4. Safety analysis of nuclear containment vessels subjected to strong earthquakes and subsequent tsunamis

    Energy Technology Data Exchange (ETDEWEB)

    Lin, Feng; Li, Hong Zhi [Dept. Structural Engineering, Tongji University, Shanghai (China)

    2017-08-15

    Nuclear power plants under expansion and under construction in China are mostly located in coastal areas, which means they are at risk of suffering strong earthquakes and subsequent tsunamis. This paper presents a safety analysis for a new reinforced concrete containment vessel in such events. A finite element method-based model was built, verified, and first used to understand the seismic performance of the containment vessel under earthquakes with increased intensities. Then, the model was used to assess the safety performance of the containment vessel subject to an earthquake with peak ground acceleration (PGA) of 0.56g and subsequent tsunamis with increased inundation depths, similar to the 2011 Great East earthquake and tsunami in Japan. Results indicated that the containment vessel reached Limit State I (concrete cracking) and Limit State II (concrete crushing) when the PGAs were in a range of 0.8–1.1g and 1.2–1.7g, respectively. The containment vessel reached Limit State I with a tsunami inundation depth of 10 m after suffering an earthquake with a PGA of 0.56g. A site-specific hazard assessment was conducted to consider the likelihood of tsunami sources.

  5. Device for removing hydrogen gas from the safety containment vessel of a nuclear reactor

    International Nuclear Information System (INIS)

    Stiefel, M.

    1983-01-01

    The safe processing of all concentrations of gas mixtures should be possible with such a device using a thermal recombiner of compact construction. A recombiner consisting of a metal case and diverter sheets situated in it is heated by induction. The incoming pipe for the gas mixture enriched with hydrogen and the outgoing pipe for the gas mixture with low hydrogen content are connected together by a three way valve. The third connection to the safety valve takes the larger port of the gas mixture with low hydrogen content back to the safety containment vessel. Sufficient amount of the gas mixture with low hydrogen content is taken via the three way valve to the safety containment vessel to ensure that the hydrogen content of the gas mixture taken to the recombiner remains below the 4% by volume limit. (orig./PW)

  6. Safety of light-water reactor pressure vessels against brittle fracture

    International Nuclear Information System (INIS)

    Brumovsky, M.

    1979-01-01

    The results are surveyed of research by SKODA Trust into brittle failure resistance of materials for WWER type reactor pressure vessels and into pressure vessel operating safety. Conditions are discussed in detail decisive for initiation, propagation and arrest of brittle fracture. The tests on the Cr-Mo-V type steel showed high resistance of the steel to the formation and the propagation of brittle fracture. They also confirmed the high operating reliability and the required service life of the steel. (B.S.)

  7. 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)

  8. Implementation of the safety culture for HANARO safety management

    International Nuclear Information System (INIS)

    Wu, Jongsup; Han, Geeyang; Kim, Iksoo

    2008-01-01

    Safety is the fundamental principal upon which a management system is based. The IAEA INSAG (International Nuclear Safety Group) states the general aims of a safety management system. One of which is to foster and support a strong safety culture through the development and reinforcement of good safety attitudes and behavior in individuals and teams, so as to allow them to carry out their tasks safely. The safety culture activities have been implemented and the importance of a safety management in nuclear activities for a reactor application and utilization has also been emphasized for more than 10 years in HANARO which is a 30MW multi-purpose research reactor that achieved its first criticality in February 1995. The safety culture activities and implementations have been conducted continuously to enhance its safe operation such as the seminars and lectures related to safety matters, participation in international workshops and the development of safety culture indicators, a survey on the attitude of HANARO staff toward the safety culture, the development of operational safety performance indicators (SPIs), the preparation of a safety text book and the development of a e-learning program for a safety education purpose

  9. Implementation of the safety culture for HANARO safety management

    Energy Technology Data Exchange (ETDEWEB)

    Wu, Jongsup; Han, Geeyang; Kim, Iksoo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2008-11-15

    Safety is the fundamental principal upon which a management system is based. The IAEA INSAG (International Nuclear Safety Group) states the general aims of a safety management system. One of which is to foster and support a strong safety culture through the development and reinforcement of good safety attitudes and behavior in individuals and teams, so as to allow them to carry out their tasks safely. The safety culture activities have been implemented and the importance of a safety management in nuclear activities for a reactor application and utilization has also been emphasized for more than 10 years in HANARO which is a 30MW multi-purpose research reactor that achieved its first criticality in February 1995. The safety culture activities and implementations have been conducted continuously to enhance its safe operation such as the seminars and lectures related to safety matters, participation in international workshops and the development of safety culture indicators, a survey on the attitude of HANARO staff toward the safety culture, the development of operational safety performance indicators (SPIs), the preparation of a safety text book and the development of a e-learning program for a safety education purpose.

  10. From Deck Hand to Program Manager - 30 years with Research Vessels

    Science.gov (United States)

    Prince, J. M.

    2012-12-01

    Starting in 1980 as a Mate and Deck Hand and working my way up to Captain, Marine Superintendent, UNOLS Executive Secretary and now as an ONR Research Facilities Program Manager focused on the acquisition of two new Ocean Class Research Vessels, I have witnessed first hand the evolution of the U.S. Academic Research Fleet. The author will focus on a few key events in the evolution of the modern research fleet. As a deck hand, mate and Captain, I was involved in an early multi-disciplinary effort often using two ships working together to conduct sampling and analysis in Physical, Chemical and Biological oceanography. The VERTEX cruises led by John Martin and others used the R/V CAYUSE and R/V WECOMA extensively through out the NE Pacific Ocean conducting research that led to Dr. Martin's Iron Hypothesis. This work and that of others involving trace metal clean sampling and clean laboratories on board our ships pushed many new and demanding requirements for future vessels. As a ship scheduler and as chair of the Research Vessel Operators Committee (RVOC) I saw the increasing use of Remotely Operated Vehicles to complement the work being done with the ALVIN and other occupied submersibles. This led to scheduling challenges and changes to our safety standards, but also to many new opportunities for discoveries on the many mid-ocean ridges and hydro-thermal vent fields. More recently, Autonomous Underwater Vehicles (AUV) and Unmanned Aerial Vehicles (UAV) and aircraft have been used simultaneously with research vessels such as during a multi-PI, multi-ship program in the Monterey Bay. Communications at sea have changed dramatically in the past thirty years. No longer are we limited to reading the data from a spreadsheet over a Single Side Band radio so that the PI ashore can track the progress of a cruise and provide guidance for the next day's sampling. Full bandwidth communications are becoming the norm with the capability of streaming video from an ROV to shore or to

  11. 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...

  12. Is road safety management linked to road safety performance?

    Science.gov (United States)

    Papadimitriou, Eleonora; Yannis, George

    2013-10-01

    This research aims to explore the relationship between road safety management and road safety performance at country level. For that purpose, an appropriate theoretical framework is selected, namely the 'SUNflower' pyramid, which describes road safety management systems in terms of a five-level hierarchy: (i) structure and culture, (ii) programmes and measures, (iii) 'intermediate' outcomes'--safety performance indicators (SPIs), (iv) final outcomes--fatalities and injuries, and (v) social costs. For each layer of the pyramid, a composite indicator is implemented, on the basis of data for 30 European countries. Especially as regards road safety management indicators, these are estimated on the basis of Categorical Principal Component Analysis upon the responses of a dedicated road safety management questionnaire, jointly created and dispatched by the ETSC/PIN group and the 'DaCoTA' research project. Then, quasi-Poisson models and Beta regression models are developed for linking road safety management indicators and other indicators (i.e. background characteristics, SPIs) with road safety performance. In this context, different indicators of road safety performance are explored: mortality and fatality rates, percentage reduction in fatalities over a given period, a composite indicator of road safety final outcomes, and a composite indicator of 'intermediate' outcomes (SPIs). The results of the analyses suggest that road safety management can be described on the basis of three composite indicators: "vision and strategy", "budget, evaluation and reporting", and "measurement of road user attitudes and behaviours". Moreover, no direct statistical relationship could be established between road safety management indicators and final outcomes. However, a statistical relationship was found between road safety management and 'intermediate' outcomes, which were in turn found to affect 'final' outcomes, confirming the SUNflower approach on the consecutive effect of each layer

  13. Management of safety, safety culture and self assessment

    International Nuclear Information System (INIS)

    Carnino, A.

    2000-01-01

    Safety management is the term used for the measures required to ensure that an acceptable level of safety is maintained throughout the life of an installation, including decommissioning. The safety culture concept and its implementation are described in part one of the paper. The principles of safety are now quite well known and are implemented worldwide. It leads to a situation where harmonization is being achieved as indicated by the entry into force of the Convention on Nuclear Safety. To go beyond the present nuclear safety levels, management of safety and safety culture will be the means for achieving progress. Recent events which took place in major nuclear power countries have shown the importance of the management and the consequences on safety. At the same time, electricity deregulation is coming and will impact on safety through reductions in staffing and in operation and maintenance cost at nuclear installations. Management of safety as well as its control and monitoring by the safety authorities become a key to the future of nuclear energy.(author)

  14. Safety-barrier diagrams as a safety management tool

    DEFF Research Database (Denmark)

    Duijm, Nijs Jan

    2009-01-01

    Safety-barrier diagrams and “bow-tie” diagrams have become popular methods in risk analysis and safety management. This paper describes the syntax and principles for constructing consistent and valid safety-barrier diagrams. The latter's relation to other methods such as fault trees and Bayesian...

  15. Safety management in nuclear technology. Proceedings

    International Nuclear Information System (INIS)

    2008-01-01

    At the symposium of TueV Sued AG (Munich, Federal Republic of Germany) held in Munich on 28 and 29 October 2008, the following lectures were held: (1) Fundamental requirements of the management system in nuclear technology - Experiences from the international developments at IAEA and WENRA (M. Herttrich); (2) Information from a comparison of requirements of safety management systems (B. Kallenbach-Herbert); (3) Requirements of a modern management system in German nuclear power plants from the view of nuclear safety (D. Majer); (4) Requirements on safety management in module 8 of the regulations project (M. Maqua); (5) Requirements on the management system in nuclear power plants according to GRS-229 and developments at the KTA 1402 ''Integrated management system for safe operation of nuclear power plants (in progress)'' (C. Verstegen); (6) Experiences from the development and implementation of safety management systems in connection with the works management of a nuclear power plant (K. Ramler); (7) Design of a safety management system of a nuclear power plant in consideration of existing management systems (U. Naumann); (8) Experiences in the utilization and evaluation of a safety management system (J. Ritter); (9) Aspects of leadership of safety management systems (S. Seitz); (10) Management of safety or safety management system? Prevailing or administration? (A. Frischknecht); (11) Change management - strategies for successful transfer of new projects: How can I motivate co-workers for a further development of the safety management system? (U. Schnabel); (12) Requirements concerning indicators in integrated management systems and safety management systems (J. Stiller); (13) Integration of proactive and reactive indicators in the safety management system (B. Fahlbruch); (14) What do indicators show? About the use of indicators by regulatory authorities (A. Kern); (15) Safety management and radiation protection in nuclear technology (K. Grantner); (16) Any more

  16. External cooling: The SWR 1000 severe accident management strategy. Part 1: motivation, strategy, analysis: melt phase, vessel integrity during melt-water interaction

    International Nuclear Information System (INIS)

    Kolev, Nikolay Ivanov

    2004-01-01

    This paper provides the description of the basics behind design features for the severe accident management strategy of the SWR 1000. The hydrogen detonation/deflagration problem is avoided by containment inertization. In-vessel retention of molten core debris via water cooling of the external surface of the reactor vessel is the severe accident management concept of the SWR 1000 passive plant. During postulated bounding severe accidents, the accident management strategy is to flood the reactor cavity with Core Flooding Pool water and to submerge the reactor vessel, thus preventing vessel failure in the SWR 1000. Considerable safety margins have determined by using state of the art experiment and analysis: regarding (a) strength of the vessel during the melt relocation and its interaction with water; (b) the heat flux at the external vessel wall; (c) the structural resistance of the hot structures during the long term period. Ex-vessel events are prevented by preserving the integrity of the vessel and its penetrations and by assuring positive external pressure at the predominant part of the external vessel in the region of the molten corium pool. Part 1 describes the motivation for selecting this strategy, the general description of the strategy and the part of the analysis associated with the vessel integrity during the melt-water interaction. (author)

  17. Risk management for industrial safety

    International Nuclear Information System (INIS)

    Novogno, A.

    1989-01-01

    The catastrophic accidents which have occurred in the last decade, in both developed and developing countries, have drawn the attention of decision-makers in the safety area to the urgent necessity to assess and manage risks from hazardous industrial activities which are concentrated in large industrialized areas. The aim of this paper is to review experience gained in conducting studies in the area of 'comparisons of risks in energy systems' and on the practical application of 'cost effectiveness of risk reduction analysis among different energy systems' (case studies). It is also the aim of the paper to discuss and propose a general framework for defining an 'integrated approach' to risk assessment and management in highly industrialized regions within a country. (author)

  18. Managing for safety at nuclear installations

    International Nuclear Information System (INIS)

    1996-01-01

    This publication, by the Health and Safety Executive's (HSE's) Nuclear Safety Division (NSD), provides a statement of the criteria the Nuclear Installations Inspectorate (NII) uses to judge the adequacy of any proposed or existing system for managing a nuclear installation in so far as it affects safety. These criteria have been developed from the basic HSE model, described in the publication Successful health and safety management that applies to industry generally, in order to meet the additional needs for managing nuclear safety. In addition, the publication identifies earlier studies upon which this work was based together with the key management activities and outputs. (Author)

  19. 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.

  20. Developing a strong safety culture - a safety management challenge

    International Nuclear Information System (INIS)

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

    1995-01-01

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

  1. Safety assessment of a multicavity prestressed concrete reactor vessel with hot liner

    Energy Technology Data Exchange (ETDEWEB)

    Lafitte, R.; Marchand, J. D. [Bonnard et Gardel, Ingenieurs-Conseil, Lausanne (Switzerland)

    1981-01-15

    The prestressed concrete reactor vessel of the high temperature reactor with helium turbine project differs from those realized up to this day by the important number of cavities, by the different cavity pressures and by a liner in contact with hot gas. For the cases of operating conditions, the computations can be based on an identical pressure in all the cavities. The overdimensioning of the vessel which results is not a determining factor at this stage of the project. The possible loss of leaktightness of the liner can introduce gas pressure into the walls of the vessel. The great thickness of the walls makes it impossible to withstand the resulting forces with prestressing in offering sufficient safety factor against collapse. It is thus important to design a drainage network largely dimensioned. The warm liner appears at this stage of the project too highly stressed by fatigue at the singularity points (ducts between cavities, angles). A solution is proposed which limits the variations of thermal stresses by using a steel with low coefficient of thermal expansion. The cavity closures, which are numerous and some with large dimensions are an important aspect of the vessel safety. A solution of reinforced concrete shell with independent liner is proposed.

  2. Safety assessment of a multicavity prestressed concrete reactor vessel with hot liner

    International Nuclear Information System (INIS)

    Lafitte, R.; Marchand, J.D.

    1981-01-01

    The prestressed concrete reactor vessel of the high temperature reactor with helium turbine project differs from those realized up to this day by the important number of cavities, by the different cavity pressures and by a liner in contact with hot gas. For the cases of operating conditions, the computations can be based on an identical pressure in all the cavities. The overdimensioning of the vessel which results is not a determining factor at this stage of the project. The possible loss of leaktightness of the liner can introduce gas pressure into the walls of the vessel. The great thickness of the walls makes it impossible to withstand the resulting forces with prestressing in offering sufficient safety factor against collapse. It is thus important to design a drainage network largely dimensioned. The warm liner appears at this stage of the project too highly stressed by fatigue at the singularity points (ducts between cavities, angles). A solution is proposed which limits the variations of thermal stresses by using a steel with low coefficient of thermal expansion. The cavity closures, which are numerous and some with large dimensions are an important aspect of the vessel safety. A solution of reinforced concrete shell with independent liner is proposed

  3. Safety Management at PUSPATI TRIGA Reactor (RTP)

    International Nuclear Information System (INIS)

    Ligam, A.S.; Zarina Masood; Ahmad Nabil Abdul Rahim

    2011-01-01

    Adequate safety measures and precautions, which follow relevant safety standards and procedures, should be in place so that personnel safety is assured. Nevertheless, the public, visitor, contractor or anyone who wishes to enter or be in the reactor building should be well informed with the safety measures applied. Furthermore, these same elements of safety are also applied to other irradiation facilities within the premises of Nuclear Malaysia. This paper will describes and explains current safety management system being enforced especially in the TRIGA PUSPATI Reactor (RTP) namely radiation monitoring system, safety equipment, safe work instruction, and interconnected internal and external health, safety and security related departments. (author)

  4. Administrative Management Competencies for Safety Professionals.

    Science.gov (United States)

    Blair, Earl H.; Logan, Joyce P.

    1999-01-01

    In a 1997 study, 245 safety professionals and educators identified and prioritized management competencies that are important for safety professionals. Results show that the most important competencies are communication, listening, motivating others, creative thinking, and flexibility. (JOW)

  5. 76 FR 30374 - Cruise Vessel Safety and Security Act of 2010, Available Technology

    Science.gov (United States)

    2011-05-25

    ... http://www.regulations.gov on or before July 25, 2011 or reach the Docket Management Facility by that... that occur on the vessel, and provide law enforcement officials in the course and scope of an... industry best practices for placement and retention of video recording devices exist? If yes, please...

  6. Ensuring the nuclear safety of VVER-440 reactor pressure vessels in Skoda, Concern Enterprise, Plzen

    International Nuclear Information System (INIS)

    Hrbek, Z.

    1985-01-01

    Various types of routine inspections are described of reactor pressure vessels with the aim of identifying residual lifetime and overall safety. The inspection programme includes: choice of systems and instruments, type of tests, test frequency, safety criteria, measures to be taken in case of unsatisfactory results, documentation. The criteria are given for periodical inspections and requirements listed for instruments and equipment. The main three groups of tests are: visual inspection and dimension tests, surface inspection and volumetric inspection. Briefly described is some of the equipment used. (M.D.)

  7. Safeguarding the nuclear safety of WWER-440 reactor pressure vessels at SKODA Plzen

    International Nuclear Information System (INIS)

    Hrbek, Z.

    1986-01-01

    The approach is described of the SKODA enterprise to safety assurance and to providing the reliability of WWER-440 reactor pressure vessels. The philosophy is analyzed of in-service inspection and determination of the residual service life of pressure vessels. This follows up on the so-called conception of basic safety whose main aim is to preclude failures at production stage by the selection of suitable material, namely by optimizing the choice of raw materials, of metallurgical procedures such as will lead to high purity of the pressure vessel material, by introducing multiple inspection in production, reducing the sensitivity of materials to technological operations, and by high-quality welds. The quality of in-service inspections is given by the use of technical diagnostic instruments of peak quality and of modern methods of nondestructive materials testing. The instruments and methods used are described. It is stated that the experience gained with in-service inspection will make it possible to draw up operating regulations and safety criteria for nuclear installations and own inspection regulations, this with regard to technical and economic factors. (Z.M.)

  8. Industrial safety management with emphasis on construction safety

    International Nuclear Information System (INIS)

    Bhattacharya, R.

    2016-01-01

    Safety professionals, line managers, team leaders and concerned workers today eagerly discuss to find out the best safety approach for their workplace. Some research suggested that behaviour based and comprehensive ergonomics approaches lead in average reduction of injuries. This article discusses 'the science and engineering' behind improvement in industrial safety aspects particularly at construction sites through various safety approaches. A high degree of commitment to safety by the project management and rigorous and proactive measures are essential to prevent accidents at construction sites particularly in DAE units because of its sensitivity. Persistent efforts by the project management are needed for sustainable and committed safety at work place. The number of fatalities occurring from construction work in DAE units is sometimes disturbing and fall of person from height and through openings are the major causes for serious accidents

  9. Contribution of materials investigations and operating experience of reactor vessel internals to PWRs' safety, performance and reliability

    International Nuclear Information System (INIS)

    Lemaire, E.; Monteil, N.; Jardin, N.; Doll, M.

    2015-01-01

    The Reactor Pressure Vessel Internals (RVI) include all the components inside the pressure vessel, except the nuclear fuel, the rod cluster assemblies and the instrumentation. The RVI consist of bolted and welded structures that are divided into two sub-assemblies: the upper internals which are removed at every refueling outage and the lower internals which are systematically removed for inspection at every 10-year outage. The main functions of the RVI are to position the core, to support it, and to provide a coolant flow by channeling the fluid. Moreover, the lower internals contribute to a neutron protection of the reactor pressure vessel by absorbing most of the neutron flux from the core. Depending on their location and material composition, the RVI components can face different ageing phenomena, that are actual or potential (such as wear, fatigue, stress corrosion cracking, irradiation assisted stress corrosion cracking, hardening and loss of ductility due to neutron irradiation, irradiation creep and irradiation swelling). EDF has developed a strategy for managing ageing and demonstrating the capacity of the RVI to perform their design functions over 40 years of operation. This overall approach is periodically revisited to take into account the most recent knowledge obtained from the following main topics: Safety Analyses, Research-Development programs, In-Service Inspection (ISI) results, Maintenance programs and Metallurgical Examinations. Based on continuous improvements in those fields, the goal of this paper is to present the way that materials investigations and operating experience obtained on RVI are managed by EDF to improve RVI safety, performance and reliability. It is shown that a perspective of 60 years of operation of RVI components is supported by large Research-Development efforts combined with field experience. (authors)

  10. Safety management - policy, analysis and implementation

    International Nuclear Information System (INIS)

    Allen, F.R.

    1993-01-01

    The nuclear industry is moving towards a period of ever increasing emphasis on business performance and profitability. Safety has, of course, always been a major concern of management in the nuclear industry and elsewhere. The civil aviation industry , for example, has had a similar concern for safety. Other industry sectors are also developing safety management as a response to events within and outside their sectors. In this paper the way that the risk management process as a whole is being addressed is looked at. Can we use risk management, initially a safety-orientated tool, to improve business performance? (author)

  11. 33 CFR 165.103 - Safety and Security Zones; LPG Vessel Transits in Portland, Maine, Captain of the Port Zone...

    Science.gov (United States)

    2010-07-01

    ... within a 500-yard radius of any Liquefied Petroleum Gas (LPG) vessel while it is moored at the LPG... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false Safety and Security Zones; LPG... and Security Zones; LPG Vessel Transits in Portland, Maine, Captain of the Port Zone, Portsmouth...

  12. Management of construction safety at KKNPP site

    International Nuclear Information System (INIS)

    Khare, P.K.

    2016-01-01

    Construction is considered as one of the most hazardous activities owing to the number of accidents and injuries. At KKNPP, management of industrial safety has been envisaged since the preliminary stage of construction planning, including design aspects. The governing principles of safety management are evolved from the Factories Act, 1948, the Atomic Energy(Factories) Rules, 1996, AERB safety guidelines on Control of works (2011) and Corporate HSE policy of NPCIL (2014). Numerous risk assessment and hazard control measures are adopted consistently to ensure a safe work environment during the construction, which includes Job Hazard Analysis, work permit through Computerized Maintenance Management System, safety procedures, exclusive safety training facility for the contractor's workmen, safety motivational measures, safety surveillance and reporting through Safety Related Deficiencies Management System. Assessment of efficacy of safety management system is continuously done through safety audits and observations are being circulated and discussed in committee meetings. Fire safety is also being taken care of since inception of project work. Well-equipped fire station with trained fire fighters was made available since the beginning as per AERB safety standard on fire protection system for Nuclear facilities. Fire prevention measures specific to the work are implemented during all activities. (author)

  13. Effective Safety Management in Construction Project

    Science.gov (United States)

    Othman, I.; Shafiq, Nasir; Nuruddin, M. F.

    2017-12-01

    Effective safety management is one of the serious problems in the construction industry worldwide, especially in large-scale construction projects. There have been significant reductions in the number and the rate of injury over the last 20 years. Nevertheless, construction remains as one of the high risk industry. The purpose of this study is to examine safety management in the Malaysian construction industry, as well as to highlight the importance of construction safety management. The industry has contributed significantly to the economic growth of the country. However, when construction safety management is not implemented systematically, accidents will happen and this can affect the economic growth of the country. This study put the safety management in construction project as one of the important elements to project performance and success. The study emphasize on awareness and the factors that lead to the safety cases in construction project.

  14. Safety management in research and development organisation

    International Nuclear Information System (INIS)

    Nivedha, T.

    2016-01-01

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

  15. Aseismic safety analysis of a prestressed concrete containment vessel for CPR1000 nuclear power plant

    Science.gov (United States)

    Yi, Ping; Wang, Qingkang; Kong, Xianjing

    2017-01-01

    The containment vessel of a nuclear power plant is the last barrier to prevent nuclear reactor radiation. Aseismic safety analysis is the key to appropriate containment vessel design. A prestressed concrete containment vessel (PCCV) model with a semi-infinite elastic foundation and practical arrangement of tendons has been established to analyze the aseismic ability of the CPR1000 PCCV structure under seismic loads and internal pressure. A method to model the prestressing tendon and its interaction with concrete was proposed and the axial force of the prestressing tendons showed that the simulation was reasonable and accurate. The numerical results show that for the concrete structure, the location of the cylinder wall bottom around the equipment hatch and near the ring beam are critical locations with large principal stress. The concrete cracks occurred at the bottom of the PCCV cylinder wall under the peak earthquake motion of 0.50 g, however the PCCV was still basically in an elastic state. Furthermore, the concrete cracks occurred around the equipment hatch under the design internal pressure of 0.4MPa, but the steel liner was still in the elastic stage and its leak-proof function soundness was verified. The results provide the basis for analysis and design of containment vessels.

  16. New safety management method at Cominak

    International Nuclear Information System (INIS)

    Kallam, A.

    1993-01-01

    Operations manager Mr. Kallam presents the new safety management system, its implementation and results in this underground uranium mine in northern Niger, where the rate of accidents increased dangerously during the eighties. 3 figs., 3 photos

  17. Editorial safety science special issue road safety management.

    NARCIS (Netherlands)

    Wegman, F.C.M. & Hagezieker, M.P.

    2014-01-01

    The articles presented in this Special Issue on Road Safety Management represent an illustration of the growing interest in policy-related research in the area of road safety. The complex nature of this type of research combined with the observation that scientific journals pay limited attention to

  18. Safety Research Experiment Facility Project. Conceptual design report. Volume V. Reactor vessel and closure

    International Nuclear Information System (INIS)

    1975-12-01

    The Prestressed Concrete Reactor Vessel (PCRV) will serve as the primary pressure retaining structure for the Safety Research Experiment Facility (SAREF) reactor. The reactor core, control rod drive room, primary heat exchangers, and gas circulators will be located in cavities within the PCRV. The orientation of these cavities, except for the control rod drive room, will be similar to the high-temperature gas-cooled reactor (HTGR) designs that are currently proposed or under design. Due to the nature of this type of structure, all biological and radiological shielding requirements are incorporated into the basic vessel design. At the midcore plane there are three radially oriented slots that will extend from the outside surface of the PCRV to the reactor core liner. These slots will accommodate each of the fuel motion monitoring systems which will be part of the observation apparatus used with the loop experiments

  19. Safety assessment of in-vessel vapor explosion loads in next generation reactor

    Energy Technology Data Exchange (ETDEWEB)

    Bang, Kwang Hyun; Cho, Jong Rae; Choi, Byung Uk; Kim, Ki Yong; Lee, Kyung Jung [Korea Maritime University, Busan (Korea); Park, Ik Kyu [Seoul National University, Seoul (Korea)

    1998-12-01

    A safety assessment of the reactor vessel lower head integrity under in-vessel vapor explosion loads has been performed. The premixing and explosion calculations were performed using TRACER-II code. Using the calculated explosion pressures imposed on the lower head inner wall, strain calculations were performed using ANSYS code. The explosion analyses show that the explosion impulses are not altered significantly by the uncertain parameters of triggering location and time, fuel and vapor volume fractions in uniform premixture bounding calculations within the conservative ranges. Strain analyses using the calculated pressure loads on the lower head inner wall show that the vapor explosion-induced lower head failure is physically unreasonable. The static analysis using the conservative explosion-end pressure of 7,246 psia shows that the maximum equivalent strain is 4.3% at the bottom of lower head, which is less than the allowable threshold value of 11%. (author). 24 refs., 40 figs., 3 tabs.

  20. Investigating road safety management processes in Europe.

    NARCIS (Netherlands)

    Jähi, H. Muhlrad, N. Buttler, I. Gitelman, V. Bax, C. Dupont, E. Giustiniani, G. Machata, K. Martensen, H. Papadimitriou, E. Persia, L. Talbot, R. Vallet, G. & Yannis, G.

    2012-01-01

    The work package 1 of the EC FP7 project DaCoTA investigates road safety management processes in Europe. It has drafted a model to investigate the state of the art of road safety policy-making and management at the national level and to define “good practice”. The DaCoTA “good practice”

  1. Risk management and safety culture

    International Nuclear Information System (INIS)

    Takano, K.

    2007-01-01

    Paper informs on the efforts to elaborate a feedback system for risk comprehensive evaluation and a system to improve structure safety foreseeing the possibility to control the latent risk, ensuring the qualitative evaluation of the safety level and improvement of safety culture in various branches of industry, first and foremost, in the electricity producing sector including the nuclear power industry [ru

  2. Road Infrastructure Safety Management in Poland

    Science.gov (United States)

    Budzynski, Marcin; Jamroz, Kazimierz; Kustra, Wojciech; Michalski, Lech; Gaca, Stanislaw

    2017-10-01

    The objective of road safety infrastructure management is to ensure that when roads are planned, designed, built and used road risks can be identified, assessed and mitigated. Road transport safety is significantly less developed than that of rail, water and air transport. The average individual risk of being a fatality in relation to the distance covered is thirty times higher in road transport that in the other modes. This is mainly because the different modes have a different approach to safety management and to the use of risk management methods and tools. In recent years Poland has had one of the European Union’s highest road death numbers. In 2016 there were 3026 fatalities on Polish roads with 40,766 injuries. Protecting road users from the risk of injury and death should be given top priority. While Poland’s national and regional road safety programmes address this problem and are instrumental in systematically reducing the number of casualties, the effects are far from the expectations. Modern approaches to safety focus on three integrated elements: infrastructure measures, safety management and safety culture. Due to its complexity, the process of road safety management requires modern tools to help with identifying road user risks, assess and evaluate the safety of road infrastructure and select effective measures to improve road safety. One possible tool for tackling this problem is the risk-based method for road infrastructure safety management. European Union Directive 2008/96/EC regulates and proposes a list of tools for managing road infrastructure safety. Road safety tools look at two criteria: the life cycle of a road structure and the process of risk management. Risk can be minimized through the application of the proposed interventions during design process as reasonable. The proposed methods of risk management bring together two stages: risk assessment and risk response occurring within the analyzed road structure (road network, road

  3. Safety of the pressure vessels of water reactors. Prevention of sudden failure

    International Nuclear Information System (INIS)

    Petrequin, P.; Barrachin, B.

    1975-01-01

    From the safety view point the primary circuit is considered as the essential barrier against the diffusion of radioactive products in the event of fuel element failure. The safety of the vessel itself, the failure of which is not accounted for in accident analyses, is based chiefly on a series of preventive measures such as the suitable choice of materials and manufacturing process, compliances with detailed specifications concerning tests and defect tolerances, supervision in service. All these points are examined in detail when the safety analysis is performed. In this context the Service de Recherches Metallurgiques Appliquees assists the Department de Surete Nucleaire in the study of special problems such as the prevention of sudden failure and the characterisation of steels as a function of working conditions, particularly neutron irradiation. The report is thus devoted mainly to the presentation of methods to prevent sudden failure, with special emphasis on the limits of application. Some results obtained at the Service de Recherches Metallurgiques Appliquees on steels typical of those used for water reactor vessels (A533 and A508Cl.3) are given by way of example. Part two concentrates on the role of various factors influencing embrittlement by irradiation [fr

  4. Performance standards of road safety management

    Directory of Open Access Journals (Sweden)

    Čabarkapa Milenko R.

    2016-01-01

    Full Text Available Road safety management controlling means the process of finding out the information whether the road safety is improving in a measure to achieve the objectives. The process of control consists of three basic elements: definition of performances and standards, measurement of current performances and comparison with the set standards, and improvement of current performances, if they deviate from the set standards. The performance standards of road safety management system are focused on a performances measurement, in terms of their design and characteristics, in order to support the performances improvement of road safety system and thus, ultimately, improve the road safety. Defining the performance standards of road safety management system, except that determines the design of the system for performances measurement, directly sets requirements whose fulfillment will produce a road safety improvement. The road safety management system, based on the performance standards of road safety, with a focus on results, will produce the continuous improvement of road safety, achieving the long-term 'vision zero', the philosophy of road safety, that human life and health take priority over mobility and other traffic objectives of the road traffic.

  5. Study of evaluation methods for in-vessel corium retention through external vessel cooling and safety of reactor cavity

    Energy Technology Data Exchange (ETDEWEB)

    Huh, Hoon; Chang, Soon Heung; Kim, Soo Hyung; Kim, Kee Poong; Lee, Hyoung Wook; Jang, Kwang Keol; Jeong, Yong Hoon; Kim, Sang Jin; Lee, Seong Jin [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of); Park, Jae Hong [Korea Institute of Nuclear Safety, Taejon (Korea, Republic of)

    2001-03-15

    In this work, assessment system for methodology for reactor pressure vessel integrity is developed. Assessment system is make up of severe accident assessment code which can calculate the conditions of plant and structural analysis code which can assess the integrity of reactor vessel using given plant conditions. An assessment of cavity flooding using containment spray system has been done. As a result, by the containment spray, cavity can be flooded successfully and CCI can be reduced. The technical backgrounds for external vessel cooling and corium cooling on the cavity are summarized and provided in this report.

  6. Study of evaluation methods for in-vessel corium retention through external vessel cooling and safety of reactor cavity

    International Nuclear Information System (INIS)

    Huh, Hoon; Chang, Soon Heung; Kim, Soo Hyung; Kim, Kee Poong; Lee, Hyoung Wook; Jang, Kwang Keol; Jeong, Yong Hoon; Kim, Sang Jin; Lee, Seong Jin; Park, Jae Hong

    2001-03-01

    In this work, assessment system for methodology for reactor pressure vessel integrity is developed. Assessment system is make up of severe accident assessment code which can calculate the conditions of plant and structural analysis code which can assess the integrity of reactor vessel using given plant conditions. An assessment of cavity flooding using containment spray system has been done. As a result, by the containment spray, cavity can be flooded successfully and CCI can be reduced. The technical backgrounds for external vessel cooling and corium cooling on the cavity are summarized and provided in this report

  7. 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

  8. Relocation work of temporary thermocouples for measuring the vessel cooling system in the safety demonstration test

    International Nuclear Information System (INIS)

    Shimazaki, Yosuke; Shinohara, Masanori; Ono, Masato; Yanagi, Shunki; Tochio, Daisuke; Iigaki, Kazuhiko

    2012-05-01

    It is necessary to confirm that the temperature of water cooling panel of the vessel cooling system (VCS) is controlled under the allowable working temperature during the safety demonstration test because the water cooling panel temperature rises due to stop of cooling water circulation pumps. Therefore, several temporary thermocouples are relocated to the water cooling panel near the stabilizers of RPV and the side cooling panel outlet ring header of VCS in order to observe the temperature change of VCS. The relocated thermocouples can measure the temperature change with starting of the cooling water circulation pumps of VCS. So it is confirmed that the relocated thermocouples can observe the VCS temperature change in the safety demonstration test. (author)

  9. Safety culture and quality management

    International Nuclear Information System (INIS)

    Edmondson, B.

    1992-01-01

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

  10. Safety control and risk management

    International Nuclear Information System (INIS)

    Rasmussen, J.

    1987-01-01

    The acceptable probability of major accidents in nuclear power is very small, and can not be determined from direct empirical evidence. Therefore, control of the level of safety is a complex problem. The difficulty is related to the fact that a variable, 'safety', which is not accessible to direct measurement, is to be tightly controlled. Control, therefore, depends on a systematic, analytical prediction of the target state, i.e., the level of safety, from indirect evidence. From a control theoretic point of view this means that safety is controlled by a system which includes openloop as well as closed loop control paths. The aim of the paper is to take a general systems view on the complex mechanisms involved in the control of safety of industrial installations like nuclear power. From this, the role of probabilistic risk analysis is evaluated and needs for further development discussed. (author)

  11. KIT safety management. Annual report 2012

    International Nuclear Information System (INIS)

    Frank, Gerhard

    2013-01-01

    The KIT Safety Management Service Unit (KSM) guarantees radiological and conventional technical safety and security of Karlsruhe Institute of Technology and controls the implementation and observation of legal environmental protection requirements. KSM is responsible for - licensing procedures, - industrial safety organization, - control of environmental protection measures, - planning and implementation of emergency preparedness and response, - operation of radiological laboratories and measurement stations, - extensive radiation protection support and the - the execution of security tasks in and for all organizational units of KIT. Moreover, KSM is in charge of wastewater and environmental monitoring for all facilities and nuclear installations all over the KIT campus. KSM is headed by the Safety Commissioner of KIT, who is appointed by the Presidential Committee. Within his scope of procedure for KIT, the Safety Commissioner controls the implementation of and compliance with safety-relevant requirements. The KIT Safety Management is certified according to DIN EN ISO 9001, its industrial safety management is certified by the VBG as ''AMS-Arbeitsschutz mit System'' and, hence, fulfills the requirements of NLF / ISO-OSH 2001. KSM laboratories are accredited according to DIN EN ISO/IEC 17025. To the extent possible, KSM is committed to maintaining competence in radiation protection and to supporting research and teaching activities. The present reports lists the individual tasks of the KIT Safety Management and informs about the results achieved in 2012. Status figures in principle reflect the status at the end of the year 2012. The processes described cover the areas of competence of KSM.

  12. Supply chain management - safety aspects

    Directory of Open Access Journals (Sweden)

    2010-12-01

    Full Text Available Developing economy, growing customer requirements and competition make the service level higher. Delivery safety - as the highest priority - has to be maintained at the same time. Customers more and more often require transport to be very flexible, fast, and complex in terms of carrying every quantity of goods of different sizes, from and to different countries, through customs clearance, storing and distribution of shipments. Meeting these requirements depends on complex information on transport processes and their safety. The article presents safety foundations and institution Authorized Economic Operator - AEO in supply chains.

  13. 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

  14. Nuclear safety culture and integrated risk management

    International Nuclear Information System (INIS)

    Joksimovich, V.; Orvis, D.D.

    1993-01-01

    A primary focus of nuclear safety is the prevention of large releases of radioactivity in the case of low-probability severe accidents. An analysis of the anatomy of nuclear (Chernobyl, Three Mile Island Unit 2) and nonnuclear (Challenger, Bhopal, Piper Alpha, etc.) severe accidents yields four broad categories of root causes: human (operating crew response), machine (design with its basic flaws), media (natural phenomena, operational considerations, political environment, commercial pressures, etc.)-providing triggering events, and management (basic organizational safety culture flaws). A strong management can minimize the contributions of humans, machines, and media to the risk arising from the operation of hazardous facilities. One way that management can have a powerful positive influence is through the establishment of a proper safety culture. The term safety culture is used as defined by the International Atomic Energy Agency's International Safety Advisory Group

  15. Advanced in-vessel retention design for next generation risk management

    Energy Technology Data Exchange (ETDEWEB)

    Suh, Kune Y.; Hwang, Il Soon [Seoul National University, Seoul (Korea, Republic of)

    1997-12-31

    In the TMI-2 accident, approximately twenty (20) tons of molten core material drained into the lower plenum. Early advanced light water reactor (LWR) designs assumed a lower head failure and incorporated various measures for ex-vessel accident mitigation. However,one of the major findings from the TMI-2 Vessel Investigation Project was that one part of the reactor lower head wall estimated to have attained a temperature of 1100 deg C for about 30 minutes has seemingly experienced a comparatively rapid cooldown with no major threat to the vessel integrity. In this regard, recent empirical and analytical studies have shifted interests to such in-vessel retention designs or strategies as reactor cavity flooding, in-vessel flooding and engineered gap cooling of the vessel. Accurate thermohydrodynamic and creep deformation modeling and rupture prediction are the key to the success in developing practically useful in-vessel accident/risk management strategies. As an advanced in-vessel design concept, this work presents the COrium Attack Syndrome Immunization Structures (COASIS) that are being developed as prospective in-vessel retention devices for a next-generation LWR in concert with existing ex-vessel management measures. Both the engineered gap structures in-vessel (COASISI) and ex-vessel (COASISO) are demonstrated to maintain effective heat transfer geometry during molten core debris attack when applied to the Korean Standard Nuclear Power Plant (KSNPP) reactor. The likelihood of lower head creep rupture during a severe accident is found to be significantly suppressed by the COASIS options. 15 refs., 5 figs., 1 tab. (Author)

  16. Advanced in-vessel retention design for next generation risk management

    Energy Technology Data Exchange (ETDEWEB)

    Suh, Kune Y; Hwang, Il Soon [Seoul National University, Seoul (Korea, Republic of)

    1998-12-31

    In the TMI-2 accident, approximately twenty (20) tons of molten core material drained into the lower plenum. Early advanced light water reactor (LWR) designs assumed a lower head failure and incorporated various measures for ex-vessel accident mitigation. However,one of the major findings from the TMI-2 Vessel Investigation Project was that one part of the reactor lower head wall estimated to have attained a temperature of 1100 deg C for about 30 minutes has seemingly experienced a comparatively rapid cooldown with no major threat to the vessel integrity. In this regard, recent empirical and analytical studies have shifted interests to such in-vessel retention designs or strategies as reactor cavity flooding, in-vessel flooding and engineered gap cooling of the vessel. Accurate thermohydrodynamic and creep deformation modeling and rupture prediction are the key to the success in developing practically useful in-vessel accident/risk management strategies. As an advanced in-vessel design concept, this work presents the COrium Attack Syndrome Immunization Structures (COASIS) that are being developed as prospective in-vessel retention devices for a next-generation LWR in concert with existing ex-vessel management measures. Both the engineered gap structures in-vessel (COASISI) and ex-vessel (COASISO) are demonstrated to maintain effective heat transfer geometry during molten core debris attack when applied to the Korean Standard Nuclear Power Plant (KSNPP) reactor. The likelihood of lower head creep rupture during a severe accident is found to be significantly suppressed by the COASIS options. 15 refs., 5 figs., 1 tab. (Author)

  17. Cesium legacy safety project management work plan

    International Nuclear Information System (INIS)

    Durham, J.S.

    1998-01-01

    This Management Work Plan (MWP) describes the process flow, quality assurance controls, and the Environment, Safety, and Health requirements of the Cesium Legacy Safety Project. This MWP provides an overview of the project goals and methods for repackaging the non-conforming Type W overpacks and packaging the CsCl powder and pellets. This MWP is not intended to apply to other activities associated with the CsCl Legacy Safety Program (i.e., clean out of South Cell)

  18. [Karachi Nuclear Power Plant (KANUPP), Safety Management

    Energy Technology Data Exchange (ETDEWEB)

    Hasan, S M [Karachi Nuclear Power Plant (KANUPP), Karachi (Pakistan)

    1997-12-01

    The present regime for CANDU safety management in Pakistan has evolved in line with contemporary international practice, and is essential adequate to ensure the continued safety of KANUPP and other future CANDU reactors, as confirmed by international reviews as well. But the small size of Pakistan nuclear power program poses limitations in developing - expert judgment in analysis of in-service inspection data; and own methodology for CANDU safety analysis.

  19. [Karachi Nuclear Power Plant (KANUPP), Safety Management

    International Nuclear Information System (INIS)

    Hasan, S.M.

    1997-01-01

    The present regime for CANDU safety management in Pakistan has evolved in line with contemporary international practice, and is essential adequate to ensure the continued safety of KANUPP and other future CANDU reactors, as confirmed by international reviews as well. But the small size of Pakistan nuclear power program poses limitations in developing - expert judgment in analysis of in-service inspection data; and own methodology for CANDU safety analysis

  20. Road safety issues for bus transport management.

    Science.gov (United States)

    Cafiso, Salvatore; Di Graziano, Alessandro; Pappalardo, Giuseppina

    2013-11-01

    Because of the low percentage of crashes involving buses and the assumption that public transport improves road safety by reducing vehicular traffic, public interest in bus safety is not as great as that in the safety of other types of vehicles. It is possible that less attention is paid to the significance of crashes involving buses because the safety level of bus systems is considered to be adequate. The purpose of this study was to evaluate the knowledge and perceptions of bus managers with respect to safety issues and the potential effectiveness of various technologies in achieving higher safety standards. Bus managers were asked to give their opinions on safety issues related to drivers (training, skills, performance evaluation and behaviour), vehicles (maintenance and advanced devices) and roads (road and traffic safety issues) in response to a research survey. Kendall's algorithm was used to evaluate the level of concordance. The results showed that the majority of the proposed items were considered to have great potential for improving bus safety. The data indicated that in the experience of the participants, passenger unloading and pedestrians crossing near bus stops are the most dangerous actions with respect to vulnerable users. The final results of the investigation showed that start inhibition, automatic door opening, and the materials and internal architecture of buses were considered the items most strongly related to bus passenger safety. Brake assistance and vehicle monitoring systems were also considered to be very effective. With the exception of driver assistance systems for passenger and pedestrian safety, the perceptions of the importance of other driver assistance systems for vehicle monitoring and bus safety were not unanimous among the bus company managers who participated in this survey. The study results showed that the introduction of new technologies is perceived as an important factor in improving bus safety, but a better understanding

  1. Transient management using the safety function approach

    International Nuclear Information System (INIS)

    Corcoran, W.R.; Barrow, J.H.; Bischoff, G.C.; Callaghan, V.M.; Pearce, R.T.

    1984-01-01

    The safety function approach is described. Its use in the development of a transient management procedures system includes optimal recovery procedures tailored to specific, anticipated symptom sets and a functional recovery procedure which is more general. Simulator evaluations are described

  2. Managing knowledge and information on nuclear safety

    International Nuclear Information System (INIS)

    Hahn, L.

    2005-01-01

    Described is the management of nuclear safety knowledge through education networks, knowledge pool, sharing, archiving and distributing the knowledge information. Demonstrated is the system used at Gesellschaft fuer Anlagen-und Reaktorsicherheit

  3. Spent Nuclear Fuel Project Safety Management Plan

    International Nuclear Information System (INIS)

    Garvin, L.J.

    1996-02-01

    The Spent Nuclear Fuel Project Safety Management Plan describes the new nuclear facility regulatory requirements basis for the Spemt Nuclear Fuel (SNF) Project and establishes the plan to achieve compliance with this basis at the new SNF Project facilities

  4. In-vessel retention as a severe accident management strategy

    International Nuclear Information System (INIS)

    Theofanous, T.G.

    1999-01-01

    A global view of the in-vessel retention idea, as rendered recently in DOE/ID-10460 and DOE/ID-10541, is provided, with updates on on-going confirmatory work on fundamental aspects of the problem, and projections about potential future applications of the technology. The author's point of view on assessment of complex problems and scaling is emphasized. (author)

  5. Occupational Safety and Health Conditions Aboard Small- and Medium-Size Fishing Vessels: Differences among Age Groups.

    Science.gov (United States)

    Zytoon, Mohamed A; Basahel, Abdulrahman M

    2017-02-24

    Although marine fishing is one of the most hazardous occupations, research on the occupational safety and health (OSH) conditions aboard marine fishing vessels is scarce. For instance, little is known about the working conditions of vulnerable groups such as young and aging fishermen. The objective of the current paper is to study the OSH conditions of young and aging fishermen compared to middle-aged fishermen in the small- and medium-size (SM) marine fishing sector. A cross-sectional study was designed, and 686 fishermen working aboard SM fishing vessels were interviewed to collect information about their safety and health. The associations of physical and psychosocial work conditions with safety and health outcomes, e.g., injuries, illnesses and job satisfaction, are presented. The results of the current study can be utilized in the design of effective accident prevention and OSH training programs for the three age groups and in the regulation of working conditions aboard fishing vessels.

  6. Managing Safety in Small and Medium Enterprises

    DEFF Research Database (Denmark)

    Stephen, legg; Olsen, Kirsten Bendix; Ian S., laird

    2015-01-01

    on safety in SMEs, showing how most current policy and legislation on occupational health and safety (OSH) and the work environment is based on large enterprises and that there is a relative paucity of research on OSH in SMEs. In a summary of current knowledge, it is argued that modern OHS legislation......This paper presents a conceptual model for increasing acceptable working environments for SMEs. It also acts as an editorial for the special issue of Safety Science on ‘Managing safety in small and medium enterprises (SMEs)’. It describes how seven of the ten papers in the special issue originate...

  7. 33 CFR 151.2035 - What are the required ballast water management practices for my vessel?

    Science.gov (United States)

    2010-07-01

    ... water management practices for my vessel? 151.2035 Section 151.2035 Navigation and Navigable Waters...) must employ at least one of the following ballast water management practices: (1) Perform complete... SUBSTANCES, GARBAGE, MUNICIPAL OR COMMERCIAL WASTE, AND BALLAST WATER Ballast Water Management for Control of...

  8. 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...

  9. Safety culture improvement. An adaptive management framework

    International Nuclear Information System (INIS)

    Obadia, Isaac Jose

    2005-01-01

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

  10. Analyses for passive safety of fusion reactor during ex-vessel loss of coolant accident

    International Nuclear Information System (INIS)

    Honda, Takuro; Okazaki, Takashi; Maki, Koichi; Uda, Tatuhiko; Seki, Yasushi; Aoki, Isao; Kunugi, Tomoaki.

    1995-01-01

    Passive safety of nuclear fusion reactors during ex-vessel Loss-of-Coolant Accidents (LOCAs) in the divertor cooling system has been investigated using a hybrid code, which can treat the interaction of the plasma and plasma facing components (PFCs). The code has been modified to include the impurity emission from PFCs with a diffusion model at the edge plasma. We assumed an ex-vessel LOCA of the divertor cooling system during the ignited operation in International Thermonuclear Experimental Reactor (ITER), in which a carbon-copper brazed divertor plate was employed in the Conceptual Design Activity (CDA). When a double-ended break occurs at the cold leg of the divertor cooling system, the impurity density in the main plasma becomes about twice within 2s after the LOCA due to radiation enhanced sublimation of graphite PFCs. The copper cooling tube of the divertor begins to melt at about 3s after the LOCA, even though the plasma is passively shut down at about 4s due to the impurity accumulation. It is necessary to apply other PFC materials, which can shorten the time period for passive shutdown, or an active shutdown system to keep the reactor structures intact for such rapid transient accident. (author)

  11. 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

  12. Fracture toughness requirements of reactor vessel material in evaluation of the safety analysis report of nuclear power plants

    International Nuclear Information System (INIS)

    Widia Lastana Istanto

    2011-01-01

    Fracture toughness requirements of reactor vessel material that must be met by applicants for nuclear power plants construction permit has been investigated in this paper. The fracture toughness should be described in the Safety Analysis Reports (SARs) document that will be evaluated by the Nuclear Energy Regulatory Agency (BAPETEN). Because BAPETEN does not have a regulations or standards/codes regarding the material used for the reactor vessel, especially in the fracture toughness requirements, then the acceptance criteria that applied to evaluate the fracture toughness of reactor vessel material refers to the regulations/provisions from the countries that have been experienced in the operation of nuclear power plants, such as from the United States, Japan and Korea. Regulations and standards used are 10 CFR Part 50, ASME and ASTM. Fracture toughness of reactor vessel materials are evaluated to ensure compliance of the requirements and provisions of the Regulatory Body and the applicable standards, such as ASME or ASTM, in order to assure a reliability and integrity of the reactor vessels as well as providing an adequate safety margin during the operation, testing, maintenance, and postulated accident conditions over the reactor vessel lifetime. (author)

  13. Workplace safety management as correlates of wellbeing among ...

    African Journals Online (AJOL)

    Workplace safety management as correlates of wellbeing among factory ... working in manufacturing firms do not enjoy the desirable level of wellbeing ... Keywords: employees' wellbeing, safety management, workers safety training, design of ...

  14. Application of probabilistic fracture mechanics to reactor pressure vessel safety assessment

    International Nuclear Information System (INIS)

    Venturini, V.; Pitner, P.

    1995-06-01

    Among all the components of a PWR (Pressurized Water Reactor) nuclear power plant, the reactor vessel is of major importance for safety. The integrity of this structure must be guaranteed in all circumstances, even in the case of the most severe accidents, and its mechanical state can be decisive for the lifetime of the plant. The brittle rupture would be the most important of all potential hazards if the irradiation effects were not consistent with predictions. The interest of having a reliable and precise method of evaluating the available safety margins and the integrity of this component led Electricite de France (EDF) to carry out a probabilistic fracture mechanics analysis. The probabilistic model developed by integration of the uncertainties in the usual fracture mechanics equations is presented. A special focus is made on the problem of coupling thermo-mechanical finite element calculations and reliability analysis. The use of a finite element code can be associated with prohibitive computation times when it is invoked numerous times during simulations sequences or complex iterative procedures. The response surface method is used. It provides an approximation of the response from a reduced number of original data. The global approach is illustrated on an example corresponding to a specific accidental transient. A validation of the obtained results is also carried out through the comparison with an equivalent model without coupling. (author)

  15. Assessment of the Zaporizhya NPP unit 1 reactor pressure vessel safety

    International Nuclear Information System (INIS)

    Podkopaev, V.; Popov, V.; Zaritsky, N.

    1997-01-01

    This emergency situation had occurred at the ZNPP unit 1 while its being under ''hot shutdown'' in natural coolant circulation mode. The main difference between emergency situation and mode with improper setting of PPPD described in the ''Technical Safety Substantiation (TSS) is that this mode is being considered in the TSS under rated power of reactor with main circulation pumps (MCP) under operation. This difference is a substantial one. For this reason a necessity appeared to asses an integrity of referred reactor pressure vessel (RPV) under given emergency situation to judge whether results obtained meet the ND requirements (safety assessment). Under operation such RPV elements are being mostly affected as upper cooling, lower cowling, weld No. 3 weld No. 4 situated in front of core. These elements materials ageing process is the most intense one. Thus, this work was aimed at investigation of structure material behavior and RPV integrity assessment under thermal shock conditions while PPPD improper setting. At that time the most attention was drawn to above mentioned upper and lower cowlings along with welds No. 3 and 4. 5 refs, figs, 10 tabs

  16. Efficiency and safety of bipolar vessel and tissue sealing in visceral surgery.

    Science.gov (United States)

    Overhaus, Marcus; Schaefer, Nico; Walgenbach, Klaus; Hirner, Andreas; Szyrach, Mara Natascha; Tolba, René Hany

    2012-11-01

    The aim of this study was to analyze the efficiency and safety of the bipolar tissue/vessel sealing and cutting device EnSeal(™) in comparison to the conventional clamp and ligation technique in visceral surgery. In an acute animal model, a part of the small bowel, a part of the colon and the kidneys were resected either with the conventional clamp and ligation technique or with EnSeal(™). Operation time, blood loss and blood parameters as well as the lateral thermal spread were evaluated. Small bowel, colon and kidney resection time with the EnSeal(™) device was shorter compared to the conventional clamp and ligation technique (small bowel: EnSeal(™): 4.7 ± 1.0 min vs. con: 35.1 ± 2.3 min; colon: EnSeal(™): 7.0 ± 1.4 min vs. con: 16.3 ± 1.5 min, kidney: EnSeal(™): 5.7 ± 1.3 min vs. con: 16.7 ± 3.7 min, p surgery with EnSeal(™) can be performed more efficiently in a shorter time, with significantly less blood loss, minimal thermal damage and without changes of blood parameters, indicating biological safety and integrity.

  17. Assessment of the Zaporizhya NPP unit 1 reactor pressure vessel safety

    Energy Technology Data Exchange (ETDEWEB)

    Podkopaev, V; Popov, V; Zaritsky, N [State Scientific and Technical Centre on Nuclear and Radiation Safety (SSTC NRS), Kiev (Ukraine)

    1997-09-01

    This emergency situation had occurred at the ZNPP unit 1 while its being under ``hot shutdown`` in natural coolant circulation mode. The main difference between emergency situation and mode with improper setting of PPPD described in the ``Technical Safety Substantiation (TSS) is that this mode is being considered in the TSS under rated power of reactor with main circulation pumps (MCP) under operation. This difference is a substantial one. For this reason a necessity appeared to asses an integrity of referred reactor pressure vessel (RPV) under given emergency situation to judge whether results obtained meet the ND requirements (safety assessment). Under operation such RPV elements are being mostly affected as upper cooling, lower cowling, weld No. 3 weld No. 4 situated in front of core. These elements materials ageing process is the most intense one. Thus, this work was aimed at investigation of structure material behavior and RPV integrity assessment under thermal shock conditions while PPPD improper setting. At that time the most attention was drawn to above mentioned upper and lower cowlings along with welds No. 3 and 4. 5 refs, figs, 10 tabs.

  18. Identification and evaluation of PWR in-vessel severe accident management strategies

    International Nuclear Information System (INIS)

    Dukelow, J.S.; Harrison, D.G.; Morgenstern, M.

    1992-03-01

    This reports documents work performed the NRC/RES Accident Management Guidance Program to evaluate possible strategies for mitigating the consequences of PWR severe accidents. The selection and evaluation of strategies was limited to the in-vessel phase of the severe accident, i.e., after the initiation of core degradation and prior to RPV failure. A parallel project at BNL has been considering strategies applicable to the ex-vessel phase of PWR severe accidents

  19. Mobility management and road safety.

    NARCIS (Netherlands)

    2012-01-01

    Mobility management stands for organizing 'smart travel' and focuses on reducing the amount of car mobility (particularly during peak hours) by stimulating travellers to refrain from travelling (telecommuting), to travel at a different time of day (avoiding peak hours) or to choose a different means

  20. Project safety studies - nuclear waste management (PSE)

    International Nuclear Information System (INIS)

    1981-10-01

    The project 'Safety Studies-Nuclear Waste Management' (PSE) is a research project performed by order of the Federal Minister for Research and Technology, the general purpose of which is to deepen and ensure the understanding of the safety aspects of the nuclear waste management and to prepare a risk analysis which will have to be established in the future. Owing to this the project is part of a series of projects which serve the further development of the concept of nuclear waste management and its safety, and which are set up in such a way as to accompany the realization of that concept. This report contains the results of the first stage of the project from 1978 to mid-1981. (orig./RW) [de

  1. 33 CFR 165.1317 - Security and Safety Zone; Large Passenger Vessel Protection, Puget Sound and adjacent waters...

    Science.gov (United States)

    2010-07-01

    ... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false Security and Safety Zone; Large Passenger Vessel Protection, Puget Sound and adjacent waters, Washington. 165.1317 Section 165.1317 Navigation and Navigable Waters COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) PORTS AND WATERWAYS...

  2. 33 CFR 165.1318 - Security and Safety Zone Regulations, Large Passenger Vessel Protection, Portland, OR Captain of...

    Science.gov (United States)

    2010-07-01

    ... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false Security and Safety Zone Regulations, Large Passenger Vessel Protection, Portland, OR Captain of the Port Zone 165.1318 Section 165.1318 Navigation and Navigable Waters COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) PORTS AND...

  3. Safety management in a competitiveness context

    International Nuclear Information System (INIS)

    Rousseau, J.M.

    2013-01-01

    This paper summarizes the first assessment performed by the IRSN related to the management of French power water reactors (PWR) safety. The conclusions of this assessment were submitted to the 'advisory committee' in April 2008. After an introduction reminding the French industrial and regulatory context as well as the way the assessment has been conducted, the relationship between safety and competitiveness is briefly discussed. Then the main issues and recommendations pointed out by the IRSN assessment are presented. These concern in particular: the balance between the shift operation team and the outage project team; the real-time decision-making capabilities of plant managers; the lessons learnt from the analyses of decision-making processes; the management of cultural changes. Finally, a conclusion presents a global diagnosis in terms of strengths and weaknesses of the EDF safety management system and proposes some ideas regarding the 'priority given to safety', the meaning of safety used by operative people and the continuous improvement approach. Lastly, methodological lessons are pointed out. The slides of the presentation have been added at the end of the paper. (author)

  4. International Safety ManagementSafety Management Systems and the Challenges of Changing a Culture

    Directory of Open Access Journals (Sweden)

    Gregory Hanchrow

    2017-03-01

    Full Text Available Over the past generation, the ISM code has brought forth tremendous opportunities to investigate and enhance the human factor in shipping through the implementation of Safety Management Systems. One of the critical factors to this implementation has been mandatory compliance and a requirement for obtaining a Document of Compliance (DOC for vessels operating globally or at least internationally. A primary objective of these systems is to maintain them as “living” or “dynamic” systems that are always evolving. As the ISM code has evolved, there have been instances where large organizations have opted to maintain a voluntary DOC from their respective class society. This has been accomplished with a large human factor element as typically an organizational culture does not always accept change readily especially if there is not a legal requirement to do so. In other words, when considering maritime training is it possible that organizations may represent cultural challenges? The intent of this paper will be to research large maritime operations that have opted for a document of compliance voluntarily and compare them to similar organizations that have been mandated by international law to do the same. The result should be to gain insight into the human factors that must contribute to a culture change in the organization for the purposes of a legal requirement versus the human factors that contribute to a voluntary establishment of a safety management system. This analysis will include both the executive decision making that designs a system implementation and the operational sector that must execute its implementation. All success and failures of education and training can be determined by the outcome. Did the training achieve its goal? Or has the education prepared the students to embrace a new idea in conjunction with a company goal or a new regulatory scheme? In qualifying the goal of a successful ISM integration by examining both

  5. Effect of radiation damage on operating safety of steel pressure vessels of nuclear reactors

    International Nuclear Information System (INIS)

    Vacek, M.; Havel, S.; Stoces, B.; Brumovsky, M.

    1980-01-01

    The effects are assessed of the environment upon mechanical properties of steel used generally for pressure vessels of light water nuclear reactors. Changes caused by radiation affect the reliability of vessels. Deterioration of steel properties is mainly due to neutron radiation. The article deals with factors bearing upon damage and with methods allowing to evaluate the reliability of vessels and predict their service life. Operating reliability of vessels is very unfavourably affected by planned and accidental reactor transients. (author)

  6. 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

  7. Life Management and Safety of Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Fabbri, S.; Diluch, A.; Vega, G., E-mail: fabbri@cnea.gov.ar [Comisión Nacional de Energía Atómica, Buenos Aires (Argentina)

    2014-10-15

    The nuclear programme in Argentina includes: nuclear power and related supplies, medical and industrial applications, waste management, research and development and human training. Nuclear facilities require life management programs that allow a safe operation. Safety is the first priority for designers and operators. This can be attained with defence in depth: regular inspections and maintenance procedures to minimize failure risks. CNEA objectives in this area are to possess the necessary capability to give safe and fast technical support. Within this scheme, one of the main activities undertaken by CNEA is to provide technological assistance to the nuclear plants and research reactors. As a consequence of an increasing concern about safety and ageing a Life Management Department for safe operation was created to take care of these subjects. The goal is to elaborate a Safety Evaluation Process for the critical components of nuclear plants and other facilities. The overall objectives of a safety process are to ensure a continuous safe, reliable and effective operation of nuclear facilities and it means the implementation of the defence in deep concept to enhance safety for the protection of the public, the workers and the environment. (author)

  8. Safety implications of diesel generator aging management

    International Nuclear Information System (INIS)

    Hoopingarner, K.R.

    1989-01-01

    Significant safety improvements can be achieved in diesel-generator management related to aging, testing, and other important regulatory concerns. This paper reports on the progress of aging research related to nuclear service diesel generators, which developed data and information supporting the recommended safety improvements. The key to diesel-generator safety improvements is the development of a new balanced approach where testing, inspections, monitoring and trending, training, and maintenance all have appropriate importance. Safety improvement is projected in a management program that concurrently achieves three goals: first, the reduction of the fast-start stressor by regulatory and utility actions; second, the establishment of more appropriate testing and trending procedures; third, the adoption and use of reliability-centered maintenance activities. This paper describes the recommended safety improvements and the positive role of utility management in the process and outlines a new recommended regulatory approach. Diesel generator aging and wear is the subject of research sponsored by the Nuclear Plant Aging Research (NPAR) Program under the US Nuclear Regulatory Commission (NRC). Office of Nuclear Regulatory Research. The research was conducted by Pacific Northwest Laboratory (PNL), which is operated for the US Department of Energy by Battelle Memorial Institute. 4 refs., 1 fig., 1 tab

  9. Identification and initial assessment of candidate BWR late-phase in-vessel accident management strategies

    International Nuclear Information System (INIS)

    Hodge, S.A.

    1991-01-01

    Work sponsored by the United States Nuclear Regulatory Commission (USNRC) to identify and perform preliminary assessments of candidate BWR [boiling water reactor] in-vessel accident management strategies was completed at Oak Ridge National Laboratory (ORNL) during fiscal year 1990. Mitigative strategies for containment events have been the subject of a companion study at Brookhaven National Laboratory. The focus of this Oak Ridge effort was the development of new strategies for mitigation of the late phase events, that is, the events that would occur in-vessel after the onset of significant core damage. The work began with an investigation of the current status of BWR in-vessel accident management procedures and proceeded through a preliminary evaluation of several candidate new strategies. The steps leading to the identification of the candidate strategies are described. The four new candidate late-phase (in-vessel) accident mitigation strategies identified by this study and discussed in the report are: (1) keep the reactor vessel depressurized; (2) restore injection in a controlled manner; (3) inject boron if control blade damage has occurred; and (4) containment flooding to maintain core and structural debris in-vessel. Additional assessments of these strategies are proposed

  10. 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.

  11. Proximal Occlusion of Medium-Sized Vessels with the Penumbra Occlusion Device: A Study of Safety and Efficacy

    Energy Technology Data Exchange (ETDEWEB)

    Jambon, E.; Petitpierre, F. [Pellegrin Hospital, Department of Radiology (France); Brizzi, V.; Dubuisson, V. [Pellegrin Hospital, Department of Surgery (France); Bras, Y. Le; Grenier, N.; Cornelis, F., E-mail: cornelisfrancois@gmail.com [Pellegrin Hospital, Department of Radiology (France)

    2017-02-15

    PurposeTo retrospectively investigate the safety and efficacy of hybrid proximal coiling of various medium-sized vessels (4 to 8 mm) using the Penumbra Occlusion Device (POD).Materials and MethodsFrom October 2014 to February 2016, 37 proximal embolizations were performed with PODs in 36 patients (mean age: 50.8, range: 10–86; 29 male, 7 female). Vessel occlusions were achieved under fluoroscopic guidance using a 2.7 French microcatheter. Among the 36 vessels targeted, 16 were splenic arteries, 11 renal arteries, 4 mesenteric arteries, 3 arteriovenous fistulae, 1 iliac artery, and 1 gonadal vein. Intermittent follow-up angiography was performed to assess the flow for final occlusion. Outcomes and complications were assessed by clinical and/or imaging follow-up.ResultsTo produce proximal occlusion of the intended vessels, the POD was used alone in 19 embolizations (51.4 %). In 12 procedures (32.4 %), POD was used as a coil constrainer to secure the coil construct. In 6 procedures (16.2 %), additional embolic devices were used to achieve vessel occlusion after initial POD deployment. After a mean follow-up of 3.2 months, no POD migration was observed but two complications occurred (5.4 %): one post embolic syndrome and one extensive infarction with splenic abscess.ConclusionThe POD system allows safe and effective proximal embolization of medium-sized vessels in a variety of clinical settings.

  12. Human factors in safety and business management.

    Science.gov (United States)

    Vogt, Joachim; Leonhardt, Jorg; Koper, Birgit; Pennig, Stefan

    2010-02-01

    Human factors in safety is concerned with all those factors that influence people and their behaviour in safety-critical situations. In aviation these are, for example, environmental factors in the cockpit, organisational factors such as shift work, human characteristics such as ability and motivation of staff. Careful consideration of human factors is necessary to improve health and safety at work by optimising the interaction of humans with their technical and social (team, supervisor) work environment. This provides considerable benefits for business by increasing efficiency and by preventing incidents/accidents. The aim of this paper is to suggest management tools for this purpose. Management tools such as balanced scorecards (BSC) are widespread instruments and also well known in aviation organisations. Only a few aviation organisations utilise management tools for human factors although they are the most important conditions in the safety management systems of aviation organisations. One reason for this is that human factors are difficult to measure and therefore also difficult to manage. Studies in other domains, such as workplace health promotion, indicate that BSC-based tools are useful for human factor management. Their mission is to develop a set of indicators that are sensitive to organisational performance and help identify driving forces as well as bottlenecks. Another tool presented in this paper is the Human Resources Performance Model (HPM). HPM facilitates the integrative assessment of human factors programmes on the basis of a systematic performance analysis of the whole system. Cause-effect relationships between system elements are defined in process models in a first step and validated empirically in a second step. Thus, a specific representation of the performance processes is developed, which ranges from individual behaviour to system performance. HPM is more analytic than BSC-based tools because HPM also asks why a certain factor is

  13. Food safety and total quality management

    NARCIS (Netherlands)

    Barendsz, A.W.

    1998-01-01

    Food safety is a growing global concern not only because of its continuing importance for public health but also because of its impact on international trade. The application of total quality management (TQM) provides the best possible care by continuously improving products and services to meet or

  14. The company's management puts priority on safety

    International Nuclear Information System (INIS)

    Tomek, J.

    2006-01-01

    On 29-30 June, 2006, the training for workers of the Slovenske elektrarne, a. s. was organized to explain the most important management safety aspects on leadership awareness (Nuclear Leadership Awareness Course). The course was held at the regional consultation center in Jaslovske Bohunice. (author)

  15. Fire Safety. Managing School Facilities, Guide 6.

    Science.gov (United States)

    Department for Education and Employment, London (England). Architects and Building Branch.

    This booklet discusses how United Kingdom schools can manage fire safety and minimize the risk of fire. The guide examines what legislation school buildings must comply with and covers the major risks. It also describes training and evacuation procedures and provides guidance on fire precautions, alarm systems, fire fighting equipment, and escape…

  16. A holistic view on Safety Management

    DEFF Research Database (Denmark)

    Jørgensen, Kirsten

    to prevent accidents is to identify the risks in all kinds of situations and take precautions by establishing safety barriers either technically or by improving the processes involved in managing these barriers, as well as bringing about behavioral improvements through good leadership. A project initiated...

  17. 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...

  18. Using objectives for managing safety and health

    International Nuclear Information System (INIS)

    Shoemaker, D.R.

    1990-01-01

    This morning I am going to talk about the International Mine Safety Rating System of the International Loss Control Institute. At the Questa mine we simply call it the ILCI System. The ILCI System has been in effect at Questa since 1982. Today, I want to offer you an outline of the system and a little bit of our experience with the system at Molycorp. In 1965, Molycorp started large-scale open-pit mining at Questa, New Mexico. In 1978 the decision was made to phase out surface mining and develop a large underground mine. Construction started in 1979, and production commenced in 1983. In 1982, with a work force approaching 900, and a 15-man safety department, we had an accident frequency rate twice the national average. At that point, as we were preparing to start underground production, we decided to become part of the International Safety Rating System. The International Safety Rating System (ISRS) is a modern safety program evaluation system. It provides the means for a systematic analysis of each element of the safety program to determine the extent and quality of management control. Auditing has long been an accepted management practice to ensure that critical business operations are performed in an efficient and profitable manner. Likewise, management has inadequate verification of the effectiveness of a safety program without the kind of audit this rating system provides. Today, largely because of the ILCI system our accident/incident rate has dropped to almost half the national average. Our production costs are nearly half of their historical high. A significant part of the savings has come from decreased expenditures for total accident losses as a result of our lower accident rates

  19. Influence of shock waves as a result of assumed vessel failure on parts of the plant relevant to safety

    International Nuclear Information System (INIS)

    Danisch, R.; Graubner, U.

    1981-01-01

    The shock wave induced rupture is of subordinate importance for the laying out of the parts of the plant relevant to safety. It is covered by the precautions for maximum potential earthquakes, aircraft crashes and chemical explosions. The failure of vessels in the power house (WAZUe, SPWB) as the result of a maximum potential earthquake is extremely improbable. If a combination of the stresses resulting from maximum potential earthquakes with the hypothetical stresses resulting from vessel failure is undertaken, it can be seen that the total stresses are only increased by a minimal amount, due to the quadratic averaging of less than 3%. (orig./DG) [de

  20. 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.

  1. Safety margin evaluation of pre-stressed concrete nuclear containment vessel model with BARC code ULCA

    International Nuclear Information System (INIS)

    Basha, S.M.; Patnaik, R.; Ramanujam, S.; Singh, R.K.; Kushwaha, H.S.; Venkat Raj, V.

    2002-01-01

    Full text: Ultimate load capacity assessment of nuclear containments has been a thrust research area for Indian pressurised heavy water reactor (PHWR) power programme. For containment safety assessment of Indian PHWRs a finite element code ULCA was developed at BARC, Trombay. This code has been extensively benchmarked with experimental results and for prediction of safety margins of Indian PHWRs. The present paper highlights the analysis results for prestressed concrete containment vessel (PCCV) tested at Sandia National Labs, USA in a round robin analysis activity co-sponsored by Nuclear Power Engineering Corporation (NUPEC), Japan and the U.S Nuclear Regulatory Commission (NRC). Three levels of failure pressure predictions namely the upper bound, the most probable and the lower bound (all with 90% confidence) were made as per the requirements of the round robin analysis activity. The most likely failure pressure is predicted to be in the range of 2.95 Pd to 3.15 Pd (Pd = design pressure of 0.39 MPa for the PCCV model) depending on the type of liners used in the construction of the PCCV model. The lower bound value of the ultimate pressure of 2.80 Pd and the upper bound of the ultimate pressure of 3.45 Pd are also predicted from the analysis. These limiting values depend on the assumptions of the analysis for simulating the concrete tendon interaction and the strain hardening characteristics of the steel members. The experimental test has been recently concluded at Sandia Laboratory and the peak pressure reached during the test is 3.3 Pd that is enveloped by our upper bound prediction of 3.45 Pd and is close to the predicted most likely pressure of 3.15 Pd

  2. A Safety Management Model for FAR 141 Approved Flight Schools

    OpenAIRE

    Mendonca, Flavio A. C.; Carney, Thomas Q

    2017-01-01

    The Safety Management Annex (Annex 19), which became applicable in November 2013, consolidates safety management provisions previously contained in six other International Civil Aviation Organization (ICAO) Annexes, and will serve as a resource for overarching state safety management responsibilities. Through Annex 19, ICAO has required that its member states develop and implement safety management systems (SMS) to improve safety. This mandate includes an approved training organization that i...

  3. 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.

  4. Communication's Role in Safety Management and Performance for the Road Safety Practices

    OpenAIRE

    Salim Keffane (s)

    2014-01-01

    Communication among organizations could play an important role in increasing road safety. To get in-depth knowledge of its role, this study measured managers' and employees' perceptions of the communication's role on six safety management and performance criteria for road safety practices by conducting a survey using a questionnaire among 165 employees and 135 managers. Path analysis using AMOS-19 software shows that some of the safety management road safety practices have high correlation wi...

  5. Safety management and public spaces: restoring balance.

    Science.gov (United States)

    Ball, David J; Ball-King, Laurence

    2013-05-01

    Since 2000, the reputation of health and safety in the United Kingdom has been tarnished, so much so that it has become the subject of both a media circus and a government inquiry. This not only threatens the worthy goals of health and safety, but also impacts upon the associated tool of risk assessment itself such that "risk assessment" is increasingly seen by the public at large as a term inviting ridicule, even abuse. The main thrust of the government's examination of health and safety has been its concern that safety requirements were placing a disproportionate burden on business. However, there is another source of discontent, which is public chagrin over the impact of injury control measures upon life beyond the conventional workplace, in particular upon the public spaces that people frequent in their leisure time and on the activities they engage in there. This article provides a perspective on this second dimension of the crisis in confidence. It describes how many U.K. agencies with responsibilities for a wide portfolio of public amenities ranging from the provision of play spaces for the young to the management of publicly accessible countryside, the maintenance of urban and rural trees, the stewardship of sites of cultural heritage, and the pursuit of outdoor educational activities have responded to some conflicts posed to their services by the new safety culture. It concludes with a discussion of implications for the management of public space and for risk assessment itself. © 2012 Society for Risk Analysis.

  6. Ageing Management Review of the reactor pressure vessels in Laguna Verde NPP

    International Nuclear Information System (INIS)

    Gris Cruz, Magdalena; Arganis, Carlos R.J.; Medina Almazan, A. Liliana

    2012-01-01

    In the present paper, for both units of Laguna Verde Nuclear Power Plant (LVNPP), the Ageing Management Review of the reactor pressure Vessel was carried out, including the identification of the intended functions, the materials and the environments. The evaluation of the ageing effect/mechanism and the Aging management programs currently implemented were prepared. The most important aging effects/ mechanisms are: loss of fracture toughness due to neutron irradiation embrittlement, fatigue, stress corrosion cracking (SCC), general corrosion and erosion-corrosion. The neutron irradiation embrittlement is managed by the reactor vessel materials surveillance program. The fatigue is a Time Limited Aging Analysis (TLAA), for which is necessary to calculate some fatigue usage factors. SCC is managed by, the In service inspections (ISI) program, but also by the Water Chemistry program, including, currently, On Line Noble Chem. The water chemistry program also manages General Corrosion and erosion-corrosion. The results were compared with the GALL report. (author)

  7. The Coast Guard Proceedings of the Marine Safety and Security Council: Spring 2016

    Science.gov (United States)

    2016-04-01

    management system designed to manage safety elements in the workplace . In practice, an operational...winning DuPont family of workplace safety training offerings. Management Buy-In Even if an organization embraces nonconformities as a call to improved...PROCEEDINGS Spring 2016 Vol. 73, Number 1 Safety Management System Objectives 6 Safety Management Facilitates Safe Vessel Operation Vessel

  8. Drug Safety Crises Management in Pharmacovigilance

    Directory of Open Access Journals (Sweden)

    Gloria Shalviri

    2018-05-01

    Full Text Available Background: Adverse drug events can cause serious consequences including death. A published report by Lazarou et al in 1998 showed that adverse drug events were the 4th to 6th leading cause of death in the United States. These events may lead to drug safety crises in some issues, which need to take crises management process for solving the problem and/or preventing similar events.Objectives: To evaluate nature of drug safety crises based on adverse events reported to Iranian Pharmacovigilance Center from 1999 through 2012. To mention success and failure outcomes of crises management process taken against detected crises.Methods: All adverse drug events received by Iranian Pharmacovigilance Center from 1999 through 2012 were evaluated for reports with fatal outcome. All alerting letters and manuscripts published by the Center during the same period were reviewed for detailed information on detected crises. World Health Organization definition was used for detecting drug safety crises.Results: Among 42036 registered cases in our database, 463 deaths were recorded. The most frequent suspected drug for adverse events with fatal outcome was ceftriaxone (100 cases. Ten different drug safety crises issues were detected during the study period and their successful or failure outcomes were evaluated. There were 112 issued alerting letters and 17 published manuscript during the same period which was monitored for detailed information.  Conclusion: It is necessary for national pharmacovigilance centers to have prepared programs for crises management. This could be useful for reducing drug related mortality.

  9. Predicting safety culture: the roles of employer, operations manager and safety professional.

    Science.gov (United States)

    Wu, Tsung-Chih; Lin, Chia-Hung; Shiau, Sen-Yu

    2010-10-01

    This study explores predictive factors in safety culture. In 2008, a sample 939 employees was drawn from 22 departments of a telecoms firm in five regions in central Taiwan. The sample completed a questionnaire containing four scales: the employer safety leadership scale, the operations manager safety leadership scale, the safety professional safety leadership scale, and the safety culture scale. The sample was then randomly split into two subsamples. One subsample was used for measures development, one for the empirical study. A stepwise regression analysis found four factors with a significant impact on safety culture (R²=0.337): safety informing by operations managers; safety caring by employers; and safety coordination and safety regulation by safety professionals. Safety informing by operations managers (ß=0.213) was by far the most significant predictive factor. The findings of this study provide a framework for promoting a positive safety culture at the group level. Crown Copyright © 2010. Published by Elsevier Ltd. All rights reserved.

  10. Applications of nano-fluids to enhance LWR accidents management in in-vessel retention and emergency core cooling systems

    International Nuclear Information System (INIS)

    Chupin, A.; Hu, L. W.; Buongiorno, J.

    2008-01-01

    Water-based nano-fluid, colloidal dispersions of nano-particles in water; have been shown experimentally to increase the critical heat flux and surface wettability at very low concentrations. The use of nano-fluids to enhance accidents management would allow either to increase the safe margins in case of severe accidents or to upgrade the power of an existing power plant with constant margins. Building on the initial work, computational fluid dynamics simulations of the nano-fluid injection system have been performed to evaluate the feasibility of a nano-fluid injection system for in-vessel retention application. A preliminary assessment was also conducted on the emergency core cooling system of the European Pressurized Reactor (EPR) to implement a nano-fluid injection system for improving the management of loss of coolant accidents. Several design options were compared/or their respective merits and disadvantages based on criteria including time to injection, safety impact, and materials compatibility. (authors)

  11. MOSEG code for safety oriented maintenance management Safety of management of maintenance oriented by MOSEG code

    International Nuclear Information System (INIS)

    Torres Valle, Antonio

    2005-01-01

    Full text: One of the main reasons that makes maintenance contribute highly when facing safety problems and facilities availability is the lack of maintenance management systems to solve these fields in a balanced way. Their main setbacks are shown in this paper. It briefly describes the development of an integrating algorithm for a safety and availability-oriented maintenance management by virtue of the MOSEG Win 1.0 code. (author)

  12. Sailing Vessel Routing Considering Safety Zone and Penalty Time for Altering Course

    Directory of Open Access Journals (Sweden)

    Marcin Zyczkowski

    2017-06-01

    Full Text Available In this paper we introduce new model for simulation sea vessel routing. Besides a vessel types (polar diagram and weather forecast, travel security and the number of maneuvers are considered. Based on these data both the minimal travelling costs and the minimal processing time are found for different vessels and different routes. To test our model the applications SailingAssistance wad improved. The obtained results shows that we can obtain quite acceptable results.

  13. Study of evaluation methods for in-vessel corium retention through external vessel cooling and safety of reactor cavity

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jae Hong; Huh, Hoon; Chang, Soon Heung [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)] (and others)

    1999-03-15

    Cooling methodologies for the molten corium resulted from the severe accident of the Nuclear Power Plant is suggested as one of most important items for the safety of the NPP. In this regard, considerable experimental and analytical works have been devoted. In the second phase of this project, current status of research about corium-concrete interaction and corium coolability which can occur on the reactor cavity has been surveyed, and the researches about lower head failure mechanism have also been surveyed. And, severe accident analysis for Ulchin 3 and 4 has been conducted, and collapse load of lower head has been analyzed through structural analysis considering various heat transfer conditions. The results of accident analysis can be used as a basic input for structural analysis which will be conducted in 3rd phase of this study.

  14. Ageing management of Indian PHWRs - safety aspects

    International Nuclear Information System (INIS)

    Kapoor, R.K.; Sah, B.M.L.; Das, M.; Srinivasan, G.R.

    1994-01-01

    Ageing management has now become a vital area of concern. Ageing management includes determination of degradation factors, taking various steps to determine present conditions of systems, structures and components and taking mitigating steps. It also includes updating, modernization, refurbishment etc. It is important that ageing management starts right from the time of commissioning of the unit and is treated as a continuous process, and a parallel effort to the normal running of the plant. Thus elaborate research and development efforts are required to be instituted. Life extension could have a high benefit to cost ratio. Various steps to ensure safety in ageing management are listed. Selection of critical items, condition monitoring and life estimation of the same and a chronological check sheet from 0 to 60 years, for Indian PHWRs is explained. Areas where future research and development and other efforts need to be directed is listed. The paper concludes emphasizing the need for a systematized approach to ageing management. It recommends intensive research in certain listed areas and suggests standing committees in specialized areas to tap Indian experience in other industries and establishments. A safety guide is also required to be produced to cover all facets of ageing management. (author). 3 appendices

  15. Management services, quality assurance, and safety

    International Nuclear Information System (INIS)

    Anon.

    1987-01-01

    Broad technical and administrative support for the programmatic research and development activities of the Fusion Energy Division is provided by the Management Services Section and by the division's quality assurance (QA) and safety programs. Support is provided through effective communication with division programmatic staff and through the coordination of resources from disciplines outside the division. The QA activity in the division emphasizes the development and documentation of a QA program that conforms to national standards, the review and approval of engineering documents, supplier surveillance, identification and documentation of nonconforming items, audits, and QA assessments/plans. The division's safety activities include a formal safety program, emergency planning activities, and environmental protection services. Efforts devoted to the removal of hazardous wastes from division facilities were expanded during 1986

  16. Time management for preclinical safety professionals.

    Science.gov (United States)

    Wells, Monique Y

    2010-08-01

    A survey about time management in the workplace was distributed to obtain a sense of the level of job satisfaction among preclinical safety professionals in the current economic climate, and to encourage reflection upon how we manage time in our work environment. Roughly equal numbers of respondents (approximately 32%) identified themselves as management or staff, and approximately 27% indicated that they are consultants. Though 45.2% of respondents indicated that time management is very challenging for the profession in general, only 36.7% find it very challenging for themselves. Ten percent of respondents view time management to be exceedingly challenging for themselves. Approximately 34% of respondents indicated that prioritization of tasks was the most challenging aspect of time management for them. Focusing on an individual task was the second most challenging aspect (26%), followed equally by procrastination and delegation of tasks (12.4%). Almost equal numbers of respondents said that they would (35.2%) or might (33.3%) undertake training to improve their time management skills. Almost equal numbers of participants responded "perhaps" (44.6%) or "yes" (44.2%) to the question of whether management personnel should be trained in time management.

  17. Applying the TOC Project Management to Operation and Maintenance Scheduling of a Research Vessel

    Science.gov (United States)

    Manti, M. Firdausi; Fujimoto, Hideo; Chen, Lian-Yi

    Marine research vessels and their systems are major assets in the marine resources development. Since the running costs for the ship are very high, it is necessary to reduce the total cost by an efficient scheduling for operation and maintenance. To reduce project period and make it efficient, we applied TOC project management method that is a project management approach developed by Dr. Eli Goldratt. It challenges traditional approaches to project management. It will become the most important improvement in the project management since the development of PERT and critical path methodologies. As a case study, we presented the marine geology research project for the purpose of operations in addition to repair on the repairing dock projects for maintenance of vessels.

  18. 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...

  19. Food safety objective: an integral part of food chain management

    NARCIS (Netherlands)

    Gorris, L.G.M.

    2005-01-01

    The concept of food safety objective has been proposed to provide a target for operational food safety management, leaving flexibility in the way equivalent food safety levels are achieved by different food chains. The concept helps to better relate operational food safety management to public

  20. Safety and Waste Management for SAM Chemistry Methods

    Science.gov (United States)

    The General Safety and Waste Management page offers section-specific safety and waste management details for the chemical analytes included in EPA's Selected Analytical Methods for Environmental Remediation and Recovery (SAM).

  1. Safety and Waste Management for SAM Pathogen Methods

    Science.gov (United States)

    The General Safety and Waste Management page offers section-specific safety and waste management details for the pathogens included in EPA's Selected Analytical Methods for Environmental Remediation and Recovery (SAM).

  2. Safety and Waste Management for SAM Radiochemical Methods

    Science.gov (United States)

    The General Safety and Waste Management page offers section-specific safety and waste management details for the radiochemical analytes included in EPA's Selected Analytical Methods for Environmental Remediation and Recovery (SAM).

  3. Safety and Waste Management for SAM Biotoxin Methods

    Science.gov (United States)

    The General Safety and Waste Management page offers section-specific safety and waste management details for the biotoxins included in EPA's Selected Analytical Methods for Environmental Remediation and Recovery (SAM).

  4. Process safety management for highly hazardous chemicals

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-02-01

    Purpose of this document is to assist US DOE contractors who work with threshold quantities of highly hazardous chemicals (HHCs), flammable liquids or gases, or explosives in successfully implementing the requirements of OSHA Rule for Process Safety Management of Highly Hazardous Chemicals (29 CFR 1910.119). Purpose of this rule is to prevent releases of HHCs that have the potential to cause catastrophic fires, explosions, or toxic exposures.

  5. Safety and Mission Assurance Knowledge Management Retention

    Science.gov (United States)

    Johnson, Teresa A.

    2006-01-01

    This viewgraph presentation reviews the issues surrounding the management of knowledge in regards to safety and mission assurance. The JSC workers who were hired in the 1960's are slated to retire in the next two to three years. The experiences and knowledge of these NASA workers must be identified, and disseminated. This paper reviews some of the strategies that the S&MA is developing to capture that valuable institutional knowledge.

  6. Dam safety management in Victoria (Australia)

    International Nuclear Information System (INIS)

    Adem, J.

    1996-01-01

    The Victoria state government's decision to make dam owners accountable for safety and upkeep of their dams was reported. To give effect to this decision a series of guidelines have been developed which outline the required activities and skills to ensure that dams are properly managed within a framework of 'light-handed' regulation. The guidelines are also intended to ensure that dam management becomes an integral part of the business decision making process, not just a set of prescribed technical procedures. Details of the direction being taken and the proposed controls to ensure compliance with national and international standards were described. 4 refs., 2 figs

  7. Passive safety features of low sodium void worth metal fueled cores in a bottom supported reactor vessel

    International Nuclear Information System (INIS)

    Chang, Y.I.; Marchaterre, J.F.; Wade, D.C.; Wigeland, R.A.; Kumaoka, Yoshio; Suzuki, Masao; Endo, Hiroshi; Nakagawa, Hiroshi

    1991-01-01

    A study has been performed on the passive safety features of low-sodium-void-worth metallic-fueled reactors with emphasis on using a bottom-supported reactor vessel design. The reactor core designs included self-sufficient types as well as actinide burners. The analyses covered the reactor response to the unprotected, i.e. unscrammed, transient overpower accident and the loss-of-flow accident. Results are given demonstrating the safety margins that were attained. 4 refs., 4 figs., 2 tabs

  8. 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.

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

    Science.gov (United States)

    2010-07-01

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

  10. 33 CFR 96.370 - What are the requirements for vessels of countries not party to Chapter IX of SOLAS?

    Science.gov (United States)

    2010-07-01

    ... vessel, or self-propelled mobile offshore drilling unit of 500 gross tons or more, operated in U.S... Waters COAST GUARD, DEPARTMENT OF HOMELAND SECURITY VESSEL OPERATING REGULATIONS RULES FOR THE SAFE OPERATION OF VESSELS AND SAFETY MANAGEMENT SYSTEMS How Will Safety Management Systems Be Certificated and...

  11. Project management techniques used in the European Vacuum Vessel sectors procurement for ITER

    Energy Technology Data Exchange (ETDEWEB)

    Losasso, Marcello, E-mail: marcello.losasso@f4e.europa.eu [Fusion for Energy (F4E), Barcelona (Spain); Ortiz de Zuniga, Maria; Jones, Lawrence; Bayon, Angel; Arbogast, Jean-Francois; Caixas, Joan; Fernandez, Jose; Galvan, Stefano; Jover, Teresa [Fusion for Energy (F4E), Barcelona (Spain); Ioki, Kimihiro [ITER Organisation, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance (France); Lewczanin, Michal; Mico, Gonzalo; Pacheco, Jose Miguel [Fusion for Energy (F4E), Barcelona (Spain); Preble, Joseph [ITER Organisation, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance (France); Stamos, Vassilis; Trentea, Alexandru [Fusion for Energy (F4E), Barcelona (Spain)

    2012-08-15

    Highlights: Black-Right-Pointing-Pointer File name contains the directory tree structure with a string of three-letter acronyms, thereby enabling parent directory location when confronted with orphan files. Black-Right-Pointing-Pointer The management of the procurement procedure was carried out in an efficient and timely manner, achieving precisely the contract placement date foreseen at the start of the process. Black-Right-Pointing-Pointer The contract start-up has been effectively implemented and a flexible project management system has been put in place for an efficient monitoring of the contract. - Abstract: The contract for the seven European Sectors of the ITER Vacuum Vessel (VV) was placed at the end of 2010 with a consortium of three Italian companies. The task of placing and the initial take-off of this large and complex contract, one of the largest placed by F4E, the European Domestic Agency for ITER, is described. A stringent quality controlled system with a bespoke Vacuum Vessel Project Lifecycle Management system to control the information flow, based on ENOVIA SmarTeam, was developed to handle the storage and approval of Documentation including links to the F4E Vacuum Vessel system and ITER International Organization System interfaces. The VV Sector design and manufacturing schedule is based on Primavera software, which is cost loaded thus allowing F4E to carry out performance measurement with respect to its payments and commitments. This schedule is then integrated into the overall Vacuum Vessel schedule, which includes ancillary activities such as instruments, preliminary design and analysis. The VV Sector Risk Management included three separate risk analyses from F4E and the bidders, utilizing two different methodologies. These efforts will lead to an efficient and effective implementation of this contract, vital to the success of the ITER machine, since the Vacuum Vessel is the biggest single work package of Europe's contribution to ITER and

  12. Associations between safety climate and safety management practices in the construction industry.

    Science.gov (United States)

    Marín, Luz S; Lipscomb, Hester; Cifuentes, Manuel; Punnett, Laura

    2017-06-01

    Safety climate, a group-level measure of workers' perceptions regarding management's safety priorities, has been suggested as a key predictor of safety outcomes. However, its relationship with actual injury rates is inconsistent. We posit that safety climate may instead be a parallel outcome of workplace safety practices, rather than a determinant of workers' safety behaviors or outcomes. Using a sample of 25 commercial construction companies in Colombia, selected by injury rate stratum (high, medium, low), we examined the relationship between workers' safety climate perceptions and safety management practices (SMPs) reported by safety officers. Workers' perceptions of safety climate were independent of their own company's implementation of SMPs, as measured here, and its injury rates. However, injury rates were negatively related to the implementation of SMPs. Safety management practices may be more important than workers' perceptions of safety climate as direct predictors of injury rates. © 2017 Wiley Periodicals, Inc.

  13. Improving ICU risk management and patient safety.

    Science.gov (United States)

    Kielty, Lucy Ann

    2017-06-12

    Purpose The purpose of this paper is to describe a study which aimed to develop and validate an assessment method for the International Electrotechnical Commission (IEC) 80001-1 (IEC, 2010) standard (the Standard); raise awareness; improve medical IT-network project risk management processes; and improve intensive care unit patient safety. Design/methodology/approach An assessment method was developed and piloted. A healthcare IT-network project assessment was undertaken using a semi-structured group interview with risk management stakeholders. Participants provided feedback via a questionnaire. Descriptive statistics and thematic analysis was undertaken. Findings The assessment method was validated as fit for purpose. Participants agreed (63 per cent, n=7) that assessment questions were clear and easy to understand, and participants agreed (82 per cent, n=9) that the assessment method was appropriate. Participant's knowledge of the Standard increased and non-compliance was identified. Medical IT-network project strengths, weaknesses, opportunities and threats in the risk management processes were identified. Practical implications The study raised awareness of the Standard and enhanced risk management processes that led to improved patient safety. Study participants confirmed they would use the assessment method in future projects. Originality/value Findings add to knowledge relating to IEC 80001-1 implementation.

  14. Management and organizational indicators of process safety

    International Nuclear Information System (INIS)

    Van Hemel, S.B.; Connelly, E.M.; Haas, P.M.

    1991-01-01

    This study is part of a Nuclear Regulatory Commission research element on organizational factors in plant safety under the Human Factors research program. This paper reports that the study investigated the chemical industry, to find leading management or organizational tools which could be useful for the NRC. After collecting information form a variety of information sources, the authors concentrated our study on two types of indicators currently in use: the first is audit- or review-based, and concentrates on programmatic factors; the second, based on frequent behavioral observations, concentrates on the management of individual worker behaviors. The authors analyzed data on the relationships between the leading indictors and direct indictors such as accident and injury rates in three case studies, to determine whether sufficient evidence of validity and utility exists to justify consideration of these indicators as public safety indicators. This paper states that on the basis of statistical associations and other evidence, the authors concluded that the two indicator types have promise for use as plant safety performance indicators, and that further development and testing of the candidate indicators should be performed

  15. Environment, Safety, Health and Waste Management Plan

    International Nuclear Information System (INIS)

    1988-01-01

    The mission of the Feed Materials Production Center (FMPC) is the production of high qaulity uranium metal for use by the US Department of Energy (DOE) in Defense Programs. In order to accomplish this mission and to maintain the FMPC as a viable facility in the DOE production complex, the facility must be brought into full compliance with all federal and state regulations and industry standards for environmental protection and worker safety. Where past practices have resulted in environmental insult, a comprehensive program of remediation must be implemented. The purpose of this combined Environment, Safety, Health and Waste Management Plan is to provide a road map for achieving needed improvements. The plan is structured to provide a comprehensive projection from the current fiscal year (FY) through FY 1994 of the programs, projects and funding required to achieve compliance. To do this, the plan is subdivided into chapters which discuss the applicable regulations;project schedules and funding requirements;details of the various programs for environment, safety, health and waste management;details of the ongoing National Environmental Policy Act (NEPA);the quality assurance program and the environmental monitoring program. 14 refs., 30 figs., 29 tabs

  16. 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)

  17. Anatomic variations of the renal vessels pertinent to transperitoneal vascular control in the management of trauma.

    Science.gov (United States)

    Kaneko, Naoyuki; Kobayashi, Yasushi; Okada, Yoshiaki

    2008-05-01

    Operative exposure and control of the renal vessels through a transabdominal retroperitoneal (TARP) approach has been advocated for emergency management of renal trauma. The pertinent anatomic variations of the renal vasculature have not been well described. In 190 cadavers, the renal vessels were examined. The first 20 cadavers were examined via TARP approach, and 170 cadavers were investigated after evisceration. The findings were interpreted as they might relate to the TARP approach to the renal pedicle. The renal artery (RA) originated dorsally or inferiorly to the left renal vein (RV) in 70% of the cadavers on each side. Additional RAs emerging below the inferior mesenteric artery were present in 2.4% of cadavers on the right side and 1.8% on the left. Approach to the inferior vena cava (IVC) adequate for the management of trauma through the TARP approach was impossible, although it has been recommended in some research. The clinically significant incidence of variations was as follows: 47% multiple RAs, 13% multiple RVs, and 50% of at least 1 RA that coursed superior to the right RV on the right margin of the IVC. Knowledge of the varied anatomy of the renal vessels facilitates a safe approach to the kidneys in trauma management. The varied and unpredictable anatomy of the renal vasculature requires prompt change when the TARP approach fails to provide access to the vessels. In such cases, the colon should be mobilized promptly. On the right side of the IVC, the vessels are located so as to require clamping together almost always.

  18. Safety and Efficacy of Advanced Bipolar Vessel Sealing in Vaginal Hysterectomy: 1000 Cases.

    Science.gov (United States)

    Clavé, Henri; Clavé, Arnaud

    2017-02-01

    To determine the safety and efficacy of advanced electrothermal bipolar vessel sealing (EBVS) during vaginal hysterectomy by evaluating urinary complications, overall complications, and reoperation rate. A retrospective cohort (Canadian Task Force classification III). High-volume gynecologic surgeon practice, private hospital. One thousand consecutive patients who have undergone vaginal hysterectomy for benign conditions carried out with EBVS between January 2002 and December 2012. Vaginal hysterectomy performed using an EBVS device. One thousand consecutive patients underwent vaginal hysterectomy with advanced EBVS between January 2002 and December 2012 with an average age of 51.4 ± 8.9 years (range, 31-88) and mean weight and body mass index of 57.4 ± 7.2 kg (range, 42-105) and 25.8 ± 4.2 kg/m 2 (range, 19.1-38.9), respectively. Eighty-five percent of patients (852/1000) were healthy without any severe systemic disease. A single experienced surgeon performed all vaginal hysterectomies with EBVS, specifically by not applying traction during thermofusion to avoid hemorrhage, amputating the cervix to transform the uterus to an apple shape to facilitate a vaginal approach and rotation of the uterus, and placing bi-clamp forceps on the edge of the uterus and not at a 45- or 90-degree angle. Wound closure was completed with a continuous suture. Eleven urinary complications (1.1%) were recorded (10 bladder mechanical injuries and 1 vesicovaginal fistula). This was not statistically different from the rate of .64% previously reported in the FINHYST study (p = .15). The overall rate of complications was 5.3%, and 20 patients (2.0%) required reoperation. The presence of uterine scar tissue (odds ratio, 5.5; 95% confidence interval, 1.6-19.2) and larger uterus size (odds ratio, 2.5; 95% confidence interval, 1.01-19.2) were associated with a higher risk of urinary complications. The use of EBVS during vaginal hysterectomy results in urinary and overall

  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. Process management - critical safety issues with focus on risk management

    International Nuclear Information System (INIS)

    Sanne, Johan M.

    2005-12-01

    Organizational changes focused on process orientation are taking place among Swedish nuclear power plants, aiming at improving the operation. The Swedish Nuclear Power Inspectorate has identified a need for increased knowledge within the area for its regulatory activities. In order to analyze what process orientation imply for nuclear power plant safety a number of questions must be asked: 1. How is safety in nuclear power production created currently? What significance does the functional organization play? 2. How can organizational forms be analysed? What consequences does quality management have for work and for the enterprise? 3. Why should nuclear power plants be process oriented? Who are the customers and what are their customer values? Which customers are expected to contribute from process orientation? 4. What can one learn from process orientation in other safety critical systems? What is the effect on those features that currently create safety? 5. Could customer values increase for one customer without decreasing for other customers? What is the relationship between economic and safety interests from an increased process orientation? The deregulation of the electricity market have caused an interest in increased economic efficiency, which is the motivation for the interest in process orientation. among other means. It is the nuclear power plants' owners and the distributors (often the same corporations) that have the strongest interest in process orientation. If the functional organization and associated practices are decomposed, the prerequisites of the risk management regime changes, perhaps deteriorating its functionality. When nuclear power operators consider the introduction of process orientation, the Nuclear Power Inspectorate should require that 1. The operators perform a risk analysis beforehand concerning the potential consequences that process orientation might convey: the analysis should contain a model specifying how safety is currently

  1. Predisposal Management of Radioactive Waste. General Safety Requirements Pt. 5

    International Nuclear Information System (INIS)

    2010-01-01

    There are a large number of facilities and activities around the world in which radioactive material is produced, handled and stored. This Safety Requirements publication presents international consensus requirements for the management of radioactive waste prior to its disposal. It provides the safety imperatives on the basis of which facilities can be designed, operated and regulated. The publication is supported by a number of Safety Guides that provide up to date recommendations and guidance on best practices for management of particular types of radioactive waste, for storage of radioactive waste, for assuring safety by developing safety cases and supporting safety assessments, and for applying appropriate management systems. Contents: 1. Introduction; 2. Protection of human health and the environment; 3. Responsibilities associated with the predisposal management of radioactive waste; 4. Steps in the predisposal management of radioactive waste; 5. Development and operation of predisposal radioactive waste management facilities and activities; Annex: Predisposal management of radioactive waste and the fundamental safety principles.

  2. Predisposal Management of Radioactive Waste. General Safety Requirements Pt. 5

    International Nuclear Information System (INIS)

    2009-01-01

    There are a large number of facilities and activities around the world in which radioactive material is produced, handled and stored. This Safety Requirements publication presents international consensus requirements for the management of radioactive waste prior to its disposal. It provides the safety imperatives on the basis of which facilities can be designed, operated and regulated. The publication is supported by a number of Safety Guides that provide up to date recommendations and guidance on best practices for management of particular types of radioactive waste, for storage of radioactive waste, for assuring safety by developing safety cases and supporting safety assessments, and for applying appropriate management systems. Contents: 1. Introduction; 2. Protection of human health and the environment; 3. Responsibilities associated with the predisposal management of radioactive waste; 4. Steps in the predisposal management of radioactive waste; 5. Development and operation of predisposal radioactive waste management facilities and activities; Annex: Predisposal management of radioactive waste and the fundamental safety principles.

  3. Management of nanomaterials safety in research environment.

    Science.gov (United States)

    Groso, Amela; Petri-Fink, Alke; Magrez, Arnaud; Riediker, Michael; Meyer, Thierry

    2010-12-10

    Despite numerous discussions, workshops, reviews and reports about responsible development of nanotechnology, information describing health and environmental risk of engineered nanoparticles or nanomaterials is severely lacking and thus insufficient for completing rigorous risk assessment on their use. However, since preliminary scientific evaluations indicate that there are reasonable suspicions that activities involving nanomaterials might have damaging effects on human health; the precautionary principle must be applied. Public and private institutions as well as industries have the duty to adopt preventive and protective measures proportionate to the risk intensity and the desired level of protection. In this work, we present a practical, 'user-friendly' procedure for a university-wide safety and health management of nanomaterials, developed as a multi-stakeholder effort (government, accident insurance, researchers and experts for occupational safety and health). The process starts using a schematic decision tree that allows classifying the nano laboratory into three hazard classes similar to a control banding approach (from Nano 3--highest hazard to Nano1--lowest hazard). Classifying laboratories into risk classes would require considering actual or potential exposure to the nanomaterial as well as statistical data on health effects of exposure. Due to the fact that these data (as well as exposure limits for each individual material) are not available, risk classes could not be determined. For each hazard level we then provide a list of required risk mitigation measures (technical, organizational and personal). The target 'users' of this safety and health methodology are researchers and safety officers. They can rapidly access the precautionary hazard class of their activities and the corresponding adequate safety and health measures. We succeed in convincing scientist dealing with nano-activities that adequate safety measures and management are promoting

  4. Management of nanomaterials safety in research environment

    Directory of Open Access Journals (Sweden)

    Riediker Michael

    2010-12-01

    Full Text Available Abstract Despite numerous discussions, workshops, reviews and reports about responsible development of nanotechnology, information describing health and environmental risk of engineered nanoparticles or nanomaterials is severely lacking and thus insufficient for completing rigorous risk assessment on their use. However, since preliminary scientific evaluations indicate that there are reasonable suspicions that activities involving nanomaterials might have damaging effects on human health; the precautionary principle must be applied. Public and private institutions as well as industries have the duty to adopt preventive and protective measures proportionate to the risk intensity and the desired level of protection. In this work, we present a practical, 'user-friendly' procedure for a university-wide safety and health management of nanomaterials, developed as a multi-stakeholder effort (government, accident insurance, researchers and experts for occupational safety and health. The process starts using a schematic decision tree that allows classifying the nano laboratory into three hazard classes similar to a control banding approach (from Nano 3 - highest hazard to Nano1 - lowest hazard. Classifying laboratories into risk classes would require considering actual or potential exposure to the nanomaterial as well as statistical data on health effects of exposure. Due to the fact that these data (as well as exposure limits for each individual material are not available, risk classes could not be determined. For each hazard level we then provide a list of required risk mitigation measures (technical, organizational and personal. The target 'users' of this safety and health methodology are researchers and safety officers. They can rapidly access the precautionary hazard class of their activities and the corresponding adequate safety and health measures. We succeed in convincing scientist dealing with nano-activities that adequate safety measures and

  5. Reactor pressure vessel life cycle management at the Calvert Cliffs Nuclear Power Plant

    International Nuclear Information System (INIS)

    Doroshuk, B.W.; Bowman, M.E.; Henry, S.A.; Pavinich, W.A.; Lapides, M.E.

    1993-01-01

    Life Cycle Management (LCM) seeks to manage the aging process of important systems, structures, and components during licensed operation. The goal of Baltimore Gas and Electric Company's (BG and E) Life Cycle Management Program is to assure attainment of 40 years of operation and to preserve the option of an additional 20 years of operation for the Calvert Cliffs Nuclear Power Plant (CCNPP). Since the reactor pressure vessel (RPV) has been identified as one of the most critical components with regard to long-term operation of a nuclear power plant, BG and E initiated actions to manage life limiting or aging issues for the CCNPP RPVs. To achieve long-term operation, technical RPV issues must be effectively managed. This paper describes methods BG and E uses for managing RPV age-related degradation. (author)

  6. 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

  7. Evaluation of the Structural Safety of a Vessel with Different Material(Cr-13)-Supplemented Screw Thread

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Yong Hoon; Bae, Jun Ho; Kim, Chul [Pusan National University, Busan (Korea, Republic of)

    2015-04-15

    The dome and neck part of a vessel is generally formed by a hot spinning process with a seamless tube. However, as studies on and design data from the hot spinning process are insufficient, this process has been performed based on trial and error and the experiences of field engineers. Changes in the inner diameter from the bottom to the top of the neck have occurred mainly because of the characteristics of the hot spinning process due to the high-speed rotation of the rollers. In this study, a theoretical and finite element analysis of the vessel is conducted with different material(Cr-13)-supplemented screw threads for tapping and to reduce shape errors. Based on the results, the structural safety under the operating conditions is evaluated.

  8. Resolution of the reactor vessel materials toughness safety issue; Task Action Plan A-11; Appendices C-K

    International Nuclear Information System (INIS)

    Johnson, R.E.

    1981-09-01

    The central problem in the Unresolved Safety Issue A-11, 'Reactor Vessel Materials Toughness,' was to provide guidance in performing analyses for reactor pressure vessels (RPVs) which fail to meet the toughness requirements during service life as a result of neutron radiation embrittlement. A technical team of recognized experts was organized to assist the NRC staff in addressing the problem. Using the foundation of the tearing modulus concept, which has been developed under earlier NRC sponsorship, relationships were obtained which provided approximate solutions to the RPV fracture problem with assumed beltline region flaws. Volume I of this report is a brief presentation of the problem and the results; Volume II provides the detailed technical foundations

  9. Evaluating Performance of Safety Management and Occupational Health Using Total Quality Safety Management Model (TQSM

    Directory of Open Access Journals (Sweden)

    E Mohammadfam

    2015-11-01

    Full Text Available Introduction: All organizations, whether public or private, necessitate performance evaluation systems in regard with growth, stability, and development in the competitive fields. One of the existing models for performance evaluation of occupational health and safety management is Total Quality Safety Management model (TQSM. Therefore, the present study aimed to evaluate performance of safety management and occupational health utilizing TQSM model. Methods: In this descriptive-analytic study, the population consisted of 16 individuals, including managers, supervisors, and members of technical protection and work health committee. Then the participants were asked to respond to TQSM questionnaire before and after the implementation of Occupational Health & Safety Advisory Services 18001 (OHSAS18001. Ultimately, the level of each program as well as the TQSM status were determined before and after the implementation of OHSAS18001. Results: The study results showed that the scores obtained by the company before OHSAS 18001’s implementation, was 43.7 out of 312. After implementing OHSAS 18001 in the company and receiving the related certificate, the total score of safety program that company could obtain was 127.12 out of 312 demonstrating a rise of 83.42 scores (26.8%. The paired t-test revealed that mean difference of TQSM scores before and after OHSAS 18001 implementation was proved to be significant (p> 0.05. Conclusion: The study findings demonstrated that TQSM can be regarded as an appropriate model in order to monitor the performance of safety management system and occupational health, since it possesses the ability to quantitatively evaluate the system performance.

  10. [Blood transfusion and supply chain management safety].

    Science.gov (United States)

    Quaranta, Jean-François; Caldani, Cyril; Cabaud, Jean-Jacques; Chavarin, Patricia; Rochette-Eribon, Sandrine

    2015-02-01

    The level of safety attained in blood transfusion now makes this a discipline better managed care activities. This was achieved both by scientific advances and policy decisions regulating and supervising the activity, as well as by the quality system, which we recall that affects the entire organizational structure, responsibilities, procedures, processes and resources in place to achieve quality management. So, an effective quality system provides a framework within which activities are established, performed in a quality-focused way and continuously monitored to improve outcomes. This system quality has to irrigate all the actors of the transfusion, just as much the establishments of blood transfusion than the health establishments. Copyright © 2014 Elsevier Masson SAS. All rights reserved.

  11. Investigation on regulatory requirements for radiation safety management

    International Nuclear Information System (INIS)

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

    2013-01-01

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

  12. Safety Aspects in Radioactive Waste Management

    Directory of Open Access Journals (Sweden)

    Peter W. Brennecke

    2007-01-01

    Full Text Available In recent years, within the framework of national as well as international programmes, notable advances and considerable experience have been reached, particularly in minimising of the production of radioactive wastes, conditioning and disposal of short-lived, low and intermediate level waste, vitrification of fission product solutions on an industrial scale and engineered storage of long-lived high level wastes, i.e. vitrified waste and spent nuclear fuel. Based on such results, near-surface repositories have successfully been operated in many countries. In contrast to that, the disposal of high level radioactive waste is still a scientific and technical challenge in many countries using the nuclear power for the electricity generation. Siting, planning and construction of repositories for the high level wastes in geological formations are gradually advancing. The site selection, the evaluation of feasible sites as well as the development of safety cases and performance of site-specific safety assessments are essential in preparing the realization of such a repository. In addition to the scientific-technical areas, issues regarding economical, environmental, ethical and political aspects have been considered increasingly during the last years. Taking differences in the national approaches, practices and the constraints into account, it is to be recognised that future developments and decisions will have to be extended in order to include further important aspects and, finally, to enhance the acceptance and confidence in the safety-related planning work as well as in the proposed radioactive waste management and disposal solutions.

  13. MATHEMATICAL APPARATUS FOR KNOWLEDGE BASE PROJECT MANAGEMENT OF OCCUPATIONAL SAFETY

    Directory of Open Access Journals (Sweden)

    Валентина Николаевна ПУРИЧ

    2015-05-01

    Full Text Available The occupational safety project (OSP management is aimed onto a rational choice implementation. With respect to the subjectivity of management goals the project selection is considered as a minimum formalization level information process, The proposed project selection model relies upon the enterprise’s occupational and industrial safety assessment using fuzzy logic and linguistic variables based on occupational safety knowledge base.

  14. TPE upgrade for enhancing operational safety and improving in-vessel tritium inventory assessment in fusion nuclear environment

    Energy Technology Data Exchange (ETDEWEB)

    Shimada, M., E-mail: Masashi.Shimada@inl.gov [Fusion Safety Program, Idaho National Laboratory, Idaho Falls, ID 83415 (United States); Taylor, C.N.; Moore-McAteer, L.; Pawelko, R.J. [Fusion Safety Program, Idaho National Laboratory, Idaho Falls, ID 83415 (United States); Kolasinski, R.D.; Buchenauer, D.A. [Sandia National Laboratories, Hydrogen and Materials Science Department, Livermore, CA 94550 (United States); Cadwallader, L.C.; Merrill, B.J. [Fusion Safety Program, Idaho National Laboratory, Idaho Falls, ID 83415 (United States)

    2016-11-01

    The Tritium Plasma Experiment (TPE) is a unique high-flux linear plasma device that can handle beryllium, tritium, and neutron-irradiated plasma facing materials, and is the only existing device dedicated to evaluate in-vessel tritium inventory in the nuclear environment for fusion safety. The electrical upgrade were recently carried out to enhance operational safety and to improve plasma performance. New DC power supplies and a new control center enable remote plasma operations from outside of the contamination area for tritium, minimizing the possible exposure risk with tritium and beryllium and eliminating heat stress issue. In November 2015, the TPE successfully achieved first deuterium plasma via remote operation after a significant three-year upgrade. Simple linear scaling estimate showed that the TPE is expected to achieve Γ{sub i}{sup max} of >1.0 × 10{sup 23} m{sup −2} s{sup −1} and q{sub heat} of >1 MW m{sup −2} with new power supplies. This upgrade not only improves operational safety of the worker, but also enhances plasma performance to better simulate extreme plasma-material conditions expected in ITER, FNSF, and DEMO for improving in-vessel tritium inventory assessment in fusion nuclear environment.

  15. 33 CFR 165.114 - Safety and Security Zones: Escorted Vessels-Boston Harbor, Massachusetts.

    Science.gov (United States)

    2010-07-01

    ... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false Safety and Security Zones... COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) PORTS AND WATERWAYS SAFETY REGULATED NAVIGATION... Guard District § 165.114 Safety and Security Zones: Escorted Vessels—Boston Harbor, Massachusetts. (a...

  16. Aging impact on the safety and operability of nuclear reactor pressure vessels

    International Nuclear Information System (INIS)

    Pennell, W.E.

    1992-01-01

    Irradiation embrittlement causes a loss of reactor vessel material fracture toughness as nuclear plants age. Fracture mechanics based regulatory requirements limit the permissible level of irradiation embrittlement such that essential fracture prevention margins are maintained throughout the plant operating life. This paper reviews the regulatory requirements and the underlying fracture mechanics technology. Issues identified with that technology are identified and research programs implemented to resolve the issues are described. Where possible, an assessment is given of the anticipated impact on the research program output will have on the reactor vessel fracture-margin assessment process

  17. Management of safety and risk at the HFIR [High-Flux Isotope Reactor

    International Nuclear Information System (INIS)

    Glovier, H.A.

    1990-01-01

    This paper discusses the management of safety and risk at the High-Flux Isotope Reactor (HFIR), a category A research reactor at Oak Ridge National Laboratory (ORNL). The HFIR went critical in 1966 and operated at its designed 100 MW for 20 yr until it was shut down on November 14, 1986. It operated at a >90% availability and without significant event during this period. The result was a complacent management program lacking rigor. This complacency came to an end with the Chernobyl accident, which led to the appointment of an internal committee to assess the safety of ORNL reactor operations. This committee found that HFIR pressure vessel material specimens removed several years earlier had not been analyzed. This issue led to a general review of management practices that were found lacking in quality assurance, safety documentation, training process, and emergency planning, among others. Management accountability was lacking, as shown by design basis and safety analyses that were not up to data and by the fact that reactor operators whose requalification examinations had not been graded were allowed to continue operating the reactor over a long period of time. Between shutdown in 1986 and restart in April 1989, significant management changes and initiatives were made in the area of risk and safety management of ORNL reactors. These are presented briefly in this paper

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

    International Nuclear Information System (INIS)

    Blush, S.M.

    1993-01-01

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

  19. 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…

  20. Exploiting data from safety investigations and processes to assess performance of safety management aspects

    NARCIS (Netherlands)

    Karanikas, Nektarios

    2016-01-01

    This paper presents an alternative way to use records from safety investigations as a means to support the evaluation of safety management (SM) aspects. Datasets from safety investigation reports and progress records of an aviation organization were analyzed with the scope of assessing safety

  1. Safety of Nonoperative Management After Acute Diverticulitis

    Science.gov (United States)

    Amoza Pais, Sonia; Batlle Marin, Xavi; Oronoz Martinez, Begoña; Balen Ribera, Enrique; Yarnoz Irazabal, Concepción

    2014-01-01

    Purpose The role of surgery in the management of diverticular disease after an episode of acute diverticulitis (AD) managed in a conservative form is evolving. Age, number of episodes of AD, type of episode, and symptoms after the episodes are factors related to the need for elective surgery. The aim of this study is to evaluate the safety of conservative management and the risk factors for emergency surgery after a first episode of AD managed without surgery. Methods We retrospectively evaluated 405 patients diagnosed as having had a first episode of AD. Sixty-nine patients underwent emergency surgery on the first admission, and 69 patients had an elective operation in the follow-up (group A). The remaining 267 patients were managed initially without surgery (group B). Thirteen of these 267 patients needed a further urgent surgical procedure. Factors involved in the decision of elective surgery and the probability of emergency surgery after the first episode of AD managed without surgery were evaluated in relation to demographic factors, risk factors, presence of recurrences, and type of the first episode. Results Patients, mean age was 62.7 years, 71 were aged less than 51, and 151 were males. The mean follow-up for patients with nonoperative management was 91.2 months. An elective operation was performed in 69 patients. Compared to patients in group B, those in group A more frequently had a first episode of complicated acute diverticulitis (CAD) (37.1% vs. 16.4%; P = 0.000) and were more likely to be smokers (46.3% vs. 19.3%; P = 0.000) and to suffer more than one episode of AD (42% vs. 26.9%; P = 0.027). Nonoperative management was chosen for 267 patients, but 13 patients needed an emergency operation later. In the multivariate analysis, we found a significant relation between the presence of CAD in the first episode and the need for emergency surgery. There were no differences in surgical mortality between the patients in the two groups, but patients treated

  2. The role of the ward manager in promoting patient safety.

    Science.gov (United States)

    Pinnock, David

    In this article the role of the ward manager in promoting patient safety is explored. The background to the development of the patient safety agenda is briefly discussed and the relationship between quality and safety is illustrated. The pivotal importance of the role of the ward manager in delivering services to patients is underlined and literature on patient safety is examined to identify what a ward manager can do to make care safer. Possible actions of the ward manager to improve safety discussed in the literature are structured around the Leadership Framework. This framework identifies seven domains for the leadership of service delivery. Ward managers use their personal qualities, and network and work within teams, while managing performance and facilitating innovation, change and measurement for improvement. The challenge of promoting patient safety for ward managers is briefly explored and recommendations for further research are made.

  3. Users manual data base MATSURV. Reactor pressure vessel material surveillance data management system

    International Nuclear Information System (INIS)

    Kenworthy, L.D.; Tether, C.D.

    1980-02-01

    This Users Guide to the data management system MATSURV has been prepared to assist the user in all facets of the task of processing data related to reactor pressure vessel materials surveillance; preparation of raw data for input, input of data, modification of existing data, retrieval and display of data, and the creation of data reports. MATSURV is structured upon the System 2000 data base management system which is maintained on the IBM 370/168 computer at National Institutes of Health. An overview of System 2000 is provided

  4. Standardized safety management of AP1000 nuclear power plant

    International Nuclear Information System (INIS)

    Li Xingwen; Cao Zhiqiang; Cong Jiuyuan

    2011-01-01

    In 2002, China published and implemented the Law of the People's Republic of China on Work Safety and promulgated a series of guidelines and policies, which strengthened the safety management supervision. Standardization of safety, as another important step on safety supervision, comes after safety assesment and safety production licensing system, is also a permanent solution. Standardization of safety is a strategic, long term and fundamental work, which is also the basic access to achieving scientific safety management and increasing the inherent safety of an enterprise. Haiyang AP1000 nuclear power plant, adopting the modularized, 'open-top' and parallel construction means, overturned the traditional construction theory of installation work comes after the civil work and greatly shorten the construction period. At the same time, the notable increase of oversize module transportation and lifting and parallel construction raises higher demands for safety management. This article combines the characteristics and difficulties of safety management for Haiyang AP1000 nuclear power plant, puts forward ideas and methods for standardized safety management, and could also serve as reference to the safety management for other AP1000 projects. (authors)

  5. Restaurant manager and worker food safety certification and knowledge.

    Science.gov (United States)

    Brown, Laura G; Le, Brenda; Wong, Melissa R; Reimann, David; Nicholas, David; Faw, Brenda; Davis, Ernestine; Selman, Carol A

    2014-11-01

    Over half of foodborne illness outbreaks occur in restaurants. To combat these outbreaks, many public health agencies require food safety certification for restaurant managers, and sometimes workers. Certification entails passing a food safety knowledge examination, which is typically preceded by food safety training. Current certification efforts are based on the assumption that certification leads to greater food safety knowledge. The Centers for Disease Control and Prevention conducted this study to examine the relationship between food safety knowledge and certification. We also examined the relationships between food safety knowledge and restaurant, manager, and worker characteristics. We interviewed managers (N=387) and workers (N=365) about their characteristics and assessed their food safety knowledge. Analyses showed that certified managers and workers had greater food safety knowledge than noncertified managers and workers. Additionally, managers and workers whose primary language was English had greater food safety knowledge than those whose primary language was not English. Other factors associated with greater food safety knowledge included working in a chain restaurant, working in a larger restaurant, having more experience, and having more duties. These findings indicate that certification improves food safety knowledge, and that complex relationships exist among restaurant, manager, and worker characteristics and food safety knowledge.

  6. Restaurant Manager and Worker Food Safety Certification and Knowledge

    Science.gov (United States)

    Brown, Laura G.; Le, Brenda; Wong, Melissa R.; Reimann, David; Nicholas, David; Faw, Brenda; Davis, Ernestine; Selman, Carol A.

    2017-01-01

    Over half of foodborne illness outbreaks occur in restaurants. To combat these outbreaks, many public health agencies require food safety certification for restaurant managers, and sometimes workers. Certification entails passing a food safety knowledge examination, which is typically preceded by food safety training. Current certification efforts are based on the assumption that certification leads to greater food safety knowledge. The Centers for Disease Control and Prevention conducted this study to examine the relationship between food safety knowledge and certification. We also examined the relationships between food safety knowledge and restaurant, manager, and worker characteristics. We interviewed managers (N = 387) and workers (N = 365) about their characteristics and assessed their food safety knowledge. Analyses showed that certified managers and workers had greater food safety knowledge than noncertified managers and workers. Additionally, managers and workers whose primary language was English had greater food safety knowledge than those whose primary language was not English. Other factors associated with greater food safety knowledge included working in a chain restaurant, working in a larger restaurant, having more experience, and having more duties. These findings indicate that certification improves food safety knowledge, and that complex relationships exist among restaurant, manager, and worker characteristics and food safety knowledge. PMID:25361386

  7. 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.

  8. Safety principles and design management of Chashma Nuclear Power Plant

    International Nuclear Information System (INIS)

    Geng Qirui; Cheng Pingdong

    1997-01-01

    The basic safety consideration and detailed design principles in the design of Chashma Nuclear Power Plant is elaborated. The management within the frame setting up by 'safety culture' and 'quality culture'

  9. 76 FR 31351 - Safety Requirements and Manning Exemption Eligibility on Distant Water Tuna Fleet Vessels

    Science.gov (United States)

    2011-05-31

    ... DWTF vessel owner/operator may demonstrate such non-availability, namely by recounting the good faith... Authorization Act (CGAA, signed into law (Pub. L. 111-281) on October 15, 2010) reauthorized the use of foreign... wording ``to the extent practicable.'' However, since licensed positions often have contracts associated...

  10. Safety cost management in construction companies: A proposal classification.

    Science.gov (United States)

    López-Alonso, M; Ibarrondo-Dávila, M P; Rubio, M C

    2016-06-16

    Estimating health and safety costs in the construction industry presents various difficulties, including the complexity of cost allocation, the inadequacy of data available to managers and the absence of an accounting model designed specifically for safety cost management. Very often, the costs arising from accidents in the workplace are not fully identifiable due to the hidden costs involved. This paper reviews some studies of occupational health and safety cost management and proposes a means of classifying these costs. We conducted an empirical study in which the health and safety costs of 40 construction worksites are estimated. A new classification of the health and safety cost and its categories is proposed: Safety and non-safety costs. The costs of the company's health and safety policy should be included in the information provided by the accounting system, as a starting point for analysis and control. From this perspective, a classification of health and safety costs and its categories is put forward.

  11. Safety culture in nuclear installations. Management of safety and safety culture in Indian NPPs

    International Nuclear Information System (INIS)

    Rawal, S.C.

    2002-01-01

    Nuclear Power Corporation Of India Ltd. (NPCIL) is a company owned by Government of India and is responsible for Design, Construction, Commissioning, Operation and Decommissioning of Nuclear Power plants in India. Presently, a total of 13 Nuclear power Stations are in operation with an installed capacity of 2620 MWe and 2 VVR type PWR Units of 1000 MWe capacity each, 2 PHWR type units of 500 MWe capacity each and 4 PHWR type 220 MWe capacity each are under construction. NPPs generation capacity has been increased from 70% to 85% in the span Of last 7 years with high level of safety standards. This could be achieved through Management commitment towards building a strong Safety Culture. Safety culture is that assembly of characteristics and attitudes in organisation and individuals which establishes that as an overriding priority nuclear plant safety issues receives the attention warranted by their significance. This definition of safety culture brings out two major components in its manifestation. The framework within which individuals within the organisation works.The attitude and response of individual towards the safety issues over productivity and economics in the organisational work practices. The two attributes of safety culture are built in and upgraded in each individuals through special training at the time of entry in the organisation and later through in built procedures in the work practices, motivation and encouragement for free participation of each individuals. Individuals are encouraged to participate in Quality circle teams at the sectional level and review of safety proposal originated by individuals in Station operation Review Committee at Station level, in addition to this to continuously enhance the safety culture, refresher training courses are being organised at regular intervals. The safety related proposals are categorised in to two namely: Proposals from Operating Plants, and Proposals from projects and Design. The concept of safety

  12. The Amplatzer vascular plug for large vessel occlusion in the endovascular management of aneurysms

    Energy Technology Data Exchange (ETDEWEB)

    Ratnam, Lakshmi A.; Walkden, Richard M.; Munneke, Graham J.; Morgan, Robert A.; Belli, Anna-Maria [St.George' s Hospital, Department of Radiology, London (United Kingdom)

    2008-09-15

    The Amplatzer vascular plug (AVP) is derived from the Amplatzer device used in correction of cardiac septal defects. We present a large series of the use of the AVP in the endovascular management of aneurysms. Three patients with a combination of aortic and peripheral aneurysms underwent embolisation with the AVP. Plugs with 10-16 mm diameter were used and delivered using introducer/guiding sheaths. A total of 16 internal iliac arteries, 2 common iliac arteries (CIA), 4 subclavian (SCA) arteries, 1 superior mesenteric (SMA) and 1 popliteal artery were embolised. Successful occlusion with the AVP was achieved in 21 out of 24 vessels (87.5%), of which 18 (75%) occluded immediately and 3 (12.5%) were delayed occlusions. The three patients who are considered to have failed to occlude with the AVP required the use of additional embolic agents. At the end of the 17-month follow-up all 24 target vessels had occluded. Two patients developed persistent buttock claudication, and one had a left hemiparesis. The AVP is useful as an adjunctive device in the management of aneurysms. It has a particular role in embolisation of large-diameter vessels with a short implantation zone. The device is safe and easy to use. (orig.)

  13. Management Commitment to Safety, Teamwork, and Hospital Worker Injuries

    OpenAIRE

    McGonagle, Alyssa K.; Essenmacher, Lynnette; Hamblin, Lydia; Luborsky, Mark; Upfal, Mark; Arnetz, Judith

    2016-01-01

    Although many studies link teamwork in health care settings to patient safety, evidence linking teamwork to hospital worker safety is lacking. This study addresses this gap by providing evidence linking teamwork perceptions in hospital workers to worker injuries, and further, finds a linkage between manager commitment to safety and teamwork. Organizational records of worker injuries and survey responses regarding management commitment to safety and teamwork from 446 hospital workers within 42...

  14. Ageing Management for Research Reactors. Specific Safety Guide

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-10-15

    This Safety Guide was developed under the IAEA programme for safety standards for research reactors, which covers all the important areas of research reactor safety. It supplements and elaborates upon the safety requirements for ageing management of research reactors that are established in paras 6.68-6.70 and 7.109 of the IAEA Safety Requirements publication, Safety of Research Reactors. The safety of a research reactor requires that provisions be made in its design to facilitate ageing management. Throughout the lifetime of a research reactor, including its decommissioning, ageing management of its structures, systems and components (SSCs) important to safety is required, to ensure continued adequacy of the safety level, reliable operation of the reactor, and compliance with the operational limits and conditions. Managing the safety aspects of research reactor ageing requires implementation of an effective programme for the monitoring, prediction, and timely detection and mitigation of degradation of SSCs important to safety, and for maintaining their integrity and functional capability throughout their service lives. Ageing management is defined as engineering, operation, and maintenance strategy and actions to control within acceptable limits the ageing degradation of SSCs. Ageing management includes activities such as repair, refurbishment and replacement of SSCs, which are similar to other activities carried out at a research reactor in maintenance and testing or when a modification project takes place. However, it is important to recognize that effective management of ageing requires the use of a methodology that will detect and evaluate ageing degradation as a consequence of the service conditions, and involves the application of countermeasures for prevention and mitigation of ageing degradation. The objective of this Safety Guide is to provide recommendations on managing ageing of SSCs important to safety at research reactors on the basis of international

  15. Ageing Management for Research Reactors. Specific Safety Guide

    International Nuclear Information System (INIS)

    2010-01-01

    This Safety Guide was developed under the IAEA programme for safety standards for research reactors, which covers all the important areas of research reactor safety. It supplements and elaborates upon the safety requirements for ageing management of research reactors that are established in paras 6.68-6.70 and 7.109 of the IAEA Safety Requirements publication, Safety of Research Reactors. The safety of a research reactor requires that provisions be made in its design to facilitate ageing management. Throughout the lifetime of a research reactor, including its decommissioning, ageing management of its structures, systems and components (SSCs) important to safety is required, to ensure continued adequacy of the safety level, reliable operation of the reactor, and compliance with the operational limits and conditions. Managing the safety aspects of research reactor ageing requires implementation of an effective programme for the monitoring, prediction, and timely detection and mitigation of degradation of SSCs important to safety, and for maintaining their integrity and functional capability throughout their service lives. Ageing management is defined as engineering, operation, and maintenance strategy and actions to control within acceptable limits the ageing degradation of SSCs. Ageing management includes activities such as repair, refurbishment and replacement of SSCs, which are similar to other activities carried out at a research reactor in maintenance and testing or when a modification project takes place. However, it is important to recognize that effective management of ageing requires the use of a methodology that will detect and evaluate ageing degradation as a consequence of the service conditions, and involves the application of countermeasures for prevention and mitigation of ageing degradation. The objective of this Safety Guide is to provide recommendations on managing ageing of SSCs important to safety at research reactors on the basis of international

  16. Resolution of the Task A-11 reactor-vessel materials-toughness safety issue. Appendices C-K

    International Nuclear Information System (INIS)

    1982-10-01

    The central problem in the unresolved safety issue A-11, Reactor Vessel Materials Toughness, was to provide guidance in performing analyses required by 10 CFR Part 50, Appendix G, Section V.C. for reactor pressure vessels (RPVs) which fail to meet the toughness requirement during service life as a result of neutron radiation embrittlement. Although the methods of linear-elastic fracture mechanics (LEFM) were adequate for low-temperature RPV problems, they were inapplicable under operating conditions because vessel steels, even those which exhibit less than 50 ft-lb of C/sub v/ energy, were relatively tough at temperatures where the impact energy reached its upper shelf values. A technical team of recognized experts was organized to assist the NRC staff in addressing the problem. Using the foundation of the tearing modulus concept, which had been developed under earlier NRC sponsorship, relationships were obtained which provided approximate solutions to the problem of RPV fracture with assumed beltline region flaws. The first paper of this report is a summary of the problem, the solutions, and the results of verification analyses. The details are provided in a series of appendices in Volumes I and II

  17. Development of a Safety Management Web Tool for Horse Stables.

    Science.gov (United States)

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

    2015-11-12

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

  18. New method of safety assessment for pressure vessel of nuclear power plant--brief introduction of master curve approach

    International Nuclear Information System (INIS)

    Yang Wendou

    2011-01-01

    The new Master Curve Method is called as a revolutionary advance to the assessment of- reactor pressure vessel integrity in USA. This paper explains the origin, basis and standard of the Master Curve from the reactor pressure-temperature limit curve which assures the safety of nuclear power plant. According to the characteristics of brittle fracture which is greatly susceptible to the microstructure, the theory and the test method of the Master Curve as well as its statistical law which can be modeled using Weibull distribution are described in this paper. The meaning, advantage, application and importance of the Master Curve as well as the relation between the Master Curve and nuclear power safety are understood from the fitting formula for the fracture toughness database by Weibull distribution model. (author)

  19. Implementation of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management

    International Nuclear Information System (INIS)

    Stewart, L.; Tonkay, D.

    2004-01-01

    This paper discusses the implementation of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. The Joint Convention: establishes a commitment with respect to safe management of spent nuclear fuel and radioactive waste; requires the Parties to ''take appropriate steps'' to ensure the safety of their spent fuel and waste management activities, but does not delineate standards the Parties must meet; and seeks to attain, through its Contracting Parties, a higher level of safety with respect to management of their spent nuclear fuel, disused sealed sources, and radioactive waste

  20. 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

  1. Adequacy features of Nucleoelectrica Argentina Safety Management

    Energy Technology Data Exchange (ETDEWEB)

    Rapoport, H [Nucleoelectrica Argentina S.A., Buenso Aires (Argentina)

    1997-12-01

    The Argentine Nuclear Power Plants (NPP) ATUCHA I (357 Mw, SIEMENS) and EMBALSE (648 Mw, CANDU), both of PHWR type, were owned and operated until August 94 by the Comision Nacional de Energia Atomica (CNEA). Until that date, CNEA, the national agency for nuclear R and D, concentrated three activities or roles: Research, Nuclear Regulations and NPP Operation. Since August 1994 NPP`s are owned and operated by a state electrical company (Nucleoelectrica Argentina S.A.) the nuclear utility supplying 15% of the national electrical generation demand. NASA is going to be privatized according to a recent national law regulating nuclear activities. The transition from a research agency to a commercial company requires the introduction of changes in the management of activities. Mention of these changes is limited to those relating to Safety.

  2. Adequacy features of Nucleoelectrica Argentina Safety Management

    International Nuclear Information System (INIS)

    Rapoport, H.

    1997-01-01

    The Argentine Nuclear Power Plants (NPP) ATUCHA I (357 Mw, SIEMENS) and EMBALSE (648 Mw, CANDU), both of PHWR type, were owned and operated until August 94 by the Comision Nacional de Energia Atomica (CNEA). Until that date, CNEA, the national agency for nuclear R and D, concentrated three activities or roles: Research, Nuclear Regulations and NPP Operation. Since August 1994 NPP's are owned and operated by a state electrical company (Nucleoelectrica Argentina S.A.) the nuclear utility supplying 15% of the national electrical generation demand. NASA is going to be privatized according to a recent national law regulating nuclear activities. The transition from a research agency to a commercial company requires the introduction of changes in the management of activities. Mention of these changes is limited to those relating to Safety

  3. Safety management in NPPs using evolutionary algorithm

    International Nuclear Information System (INIS)

    Mishra, A.; Patwardhan, A.; Chauhan, A.; Verma, A.K.

    2005-01-01

    Technical specification and maintenance (TS and M) activities in a plant are associated with controlling risk or with satisfying requirements, and are candidates to be evaluated for their resource effectiveness in risk-informed applications. The general goal of safety management in Nuclear Power Plants (NPPs) is to make requirements and activities more risk effective and less costly. Accordingly, the risk-based analysis of Technical Specification (RBTS) is being considered in evaluating current TS. The multi objective optimization of the TS and M requirements of a NPP based on risk and cost, gives the pareto-optimal solutions, from which the utility can pick its decision variables suiting its interest. In this paper a multi objective Evolutionary Algorithm technique has been used to make a trade-off between risk and cost both at the system level and at the plant level for Loss of coolant Accident (LOCA) and Main Steam Line Break (MSLB) as initiating events. (authors)

  4. Consistency between analytical and finite element predictions for safety of cylindrical pressure vessels at higher temperatures

    International Nuclear Information System (INIS)

    Iancu, Otto Theodor

    2014-01-01

    The prediction of the plastic collapse load of cylindrical pressure vessels is very often made by using expensive Finite Element computations. The calculation of the collapse load requires an elastic-plastic material model and the consideration of non-linear geometry effects. The plastic collapse load causes overall structural instability and cannot be determined directly from a Finite Element analysis. In the present paper the plastic collapse load for a cylindrical pressure vessel is determined by an analytical method based on a linear elastic perfectly plastic material model. When plasticity occurs the material is considered to be incompressible and the tensor of plastic strains to be parallel to the stress deviator tensor. In this case the finite stress-strain relationships of Henkel can be used for calculating the pressure for which plastic flow occurs. The analytical results are completely confirmed by Finite Element predictions. (orig.)

  5. Effectiveness of In-Vessel Retention Strategies and Minimum Safety Injection Flow over Postulated Severe Accidents of OPR1000

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Sung Joong; Seo, Seungwon; Lee, Seongnyeon [Hanyang Univ., Seoul (Korea, Republic of); KIm, Hwan Yeol; Ha, Kwang Soon; Park, Jonghwa; Park, Raejoon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2013-10-15

    The objective of this study is first to evaluate various serious severe accident scenarios of OPR1000 with and without in-vessel retention strategies using MELCOR code. Second is to develop a mechanistic model of minimum safety injection flow using the thermal-hydraulic parameters of CET and collapsed water level obtained from the MELCOR simulation results. Effectiveness of RCS depressurization of OPR1000 is investigated for postulated severe accidents of SBLOCA, SBO, and TLOF. It is seen that timely operator action is important to achieve the best mitigation. Also The MELCOR simulation results of SBLOCA, SBO, and TLOFW are utilized to develop a model for minimum safety injection flow. The model suggests that if HPSI is available with RCS pressure lower than 120 bars, the core coolability can be guaranteed. In this study, several MELCOR simulations are conducted in search for effective in-vessel retention strategies over postulated severe accidents of SBLOCA, SBO, and TLOFW of OPR1000. Detailed accident sequences are presented and indicative parameters diagnosing the reactor thermal-hydraulic state are interrogated to provide useful information to the operator actions. To properly assist operator's action during the severe accident, the thermal-hydraulic parameters should be virtual, intuitive, and reliable. In addition, the parameters should be collected through the instrumentations close to the reactor core. In this regard, Core Exit Temperature (CET) and collapsed core water level are deemed as the commensurate parameters.

  6. Effectiveness of In-Vessel Retention Strategies and Minimum Safety Injection Flow over Postulated Severe Accidents of OPR1000

    International Nuclear Information System (INIS)

    Kim, Sung Joong; Seo, Seungwon; Lee, Seongnyeon; KIm, Hwan Yeol; Ha, Kwang Soon; Park, Jonghwa; Park, Raejoon

    2013-01-01

    The objective of this study is first to evaluate various serious severe accident scenarios of OPR1000 with and without in-vessel retention strategies using MELCOR code. Second is to develop a mechanistic model of minimum safety injection flow using the thermal-hydraulic parameters of CET and collapsed water level obtained from the MELCOR simulation results. Effectiveness of RCS depressurization of OPR1000 is investigated for postulated severe accidents of SBLOCA, SBO, and TLOF. It is seen that timely operator action is important to achieve the best mitigation. Also The MELCOR simulation results of SBLOCA, SBO, and TLOFW are utilized to develop a model for minimum safety injection flow. The model suggests that if HPSI is available with RCS pressure lower than 120 bars, the core coolability can be guaranteed. In this study, several MELCOR simulations are conducted in search for effective in-vessel retention strategies over postulated severe accidents of SBLOCA, SBO, and TLOFW of OPR1000. Detailed accident sequences are presented and indicative parameters diagnosing the reactor thermal-hydraulic state are interrogated to provide useful information to the operator actions. To properly assist operator's action during the severe accident, the thermal-hydraulic parameters should be virtual, intuitive, and reliable. In addition, the parameters should be collected through the instrumentations close to the reactor core. In this regard, Core Exit Temperature (CET) and collapsed core water level are deemed as the commensurate parameters

  7. Managing health and safety risks: Implications for tailoring health and safety management system practices.

    Science.gov (United States)

    Willmer, D R; Haas, E J

    2016-01-01

    As national and international health and safety management system (HSMS) standards are voluntarily accepted or regulated into practice, organizations are making an effort to modify and integrate strategic elements of a connected management system into their daily risk management practices. In high-risk industries such as mining, that effort takes on added importance. The mining industry has long recognized the importance of a more integrated approach to recognizing and responding to site-specific risks, encouraging the adoption of a risk-based management framework. Recently, the U.S. National Mining Association led the development of an industry-specific HSMS built on the strategic frameworks of ANSI: Z10, OHSAS 18001, The American Chemistry Council's Responsible Care, and ILO-OSH 2001. All of these standards provide strategic guidance and focus on how to incorporate a plan-do-check-act cycle into the identification, management and evaluation of worksite risks. This paper details an exploratory study into whether practices associated with executing a risk-based management framework are visible through the actions of an organization's site-level management of health and safety risks. The results of this study show ways that site-level leaders manage day-to-day risk at their operations that can be characterized according to practices associated with a risk-based management framework. Having tangible operational examples of day-to-day risk management can serve as a starting point for evaluating field-level risk assessment efforts and their alignment to overall company efforts at effective risk mitigation through a HSMS or other processes.

  8. Stent-assisted coil embolization of aneurysms with small parent vessels: safety and efficacy analysis.

    Science.gov (United States)

    Kühn, Anna Luisa; Hou, Samuel Y; Puri, Ajit S; Silva, Christine F; Gounis, Matthew J; Wakhloo, Ajay K

    2016-06-01

    Stent-assisted coil embolization (SACE) is a viable therapeutic approach for wide-neck intracranial aneurysms. However, it can be technically challenging in small cerebral vessels (≤2 mm). To present our experience with stents approved for SACE in aneurysms with small parent arteries. All patients who underwent stent-assisted aneurysm treatment with either a Neuroform or an Enterprise stent device at our institution between June 2006 and October 2012 were identified. Additionally, we evaluated each patient's vascular risk factors, aneurysm characteristics (ruptured vs non-ruptured, incidental finding, recanalized) and follow-up angiography data. A total of 41 patients with 44 aneurysms met our criteria, including 31 women and 10 men. Most of the aneurysms were located in the anterior circulation (75%). Stent placement in vessels 1.2-2 mm in diameter was successful in 93.2%. Thromboembolic complications occurred in 6 cases and vessel straightening was seen in 1 case only. Initial nearly complete to complete aneurysm obliteration was achieved in 88.6%. Six-month follow-up angiography showed coil compaction in three cases, one asymptomatic in-stent stenosis and stent occlusion. Twelve to 20-months' follow-up showed stable coil compaction in two patients compared with previous follow-up, and aneurysm recanalization in two patients. Twenty-four to 36-months' follow-up showed further coil compaction in one of these patients and aneurysm recanalization in a previous case of stable coil compaction on mid-term follow-up. Our results suggest that SACE of aneurysms with small parent vessels is feasible in selected cases and shows good long-term patency rates of parent arteries. Published by the BMJ Publishing Group Limited. For permission to use (where not already granted under a licence) please go to http://www.bmj.com/company/products-services/rights-and-licensing/

  9. Management concepts and safety applications for nuclear fuel facilities

    International Nuclear Information System (INIS)

    Eisner, H.; Scotti, R.S.

    1995-05-01

    This report presents an overview of effectiveness of management control of safety. It reviews several modern management control theories as well as the general functions of management and relates them to safety issues at the corporate and at the process safety management (PSM) program level. Following these discussions, structured technique for assessing management of the safety function is suggested. Seven modern management control theories are summarized, including business process reengineering, the learning organization, capability maturity, total quality management, quality assurance and control, reliability centered maintenance, and industrial process safety. Each of these theories is examined for-its principal characteristics and implications for safety management. The five general management functions of planning, organizing, directing, monitoring, and integrating, which together provide control over all company operations, are discussed. Under the broad categories of Safety Culture, Leadership and Commitment, and Operating Excellence, key corporate safety elements and their subelements are examined. The three categories under which PSM program-level safety issues are described are Technology, Personnel, and Facilities

  10. Management concepts and safety applications for nuclear fuel facilities

    Energy Technology Data Exchange (ETDEWEB)

    Eisner, H.; Scotti, R.S. [George Washington Univ., Washington, DC (United States). School of Engineering and Applied Science; Delicate, W.S. [KEVRIC Co., Inc., Silver Spring, MD (United States)

    1995-05-01

    This report presents an overview of effectiveness of management control of safety. It reviews several modern management control theories as well as the general functions of management and relates them to safety issues at the corporate and at the process safety management (PSM) program level. Following these discussions, structured technique for assessing management of the safety function is suggested. Seven modern management control theories are summarized, including business process reengineering, the learning organization, capability maturity, total quality management, quality assurance and control, reliability centered maintenance, and industrial process safety. Each of these theories is examined for-its principal characteristics and implications for safety management. The five general management functions of planning, organizing, directing, monitoring, and integrating, which together provide control over all company operations, are discussed. Under the broad categories of Safety Culture, Leadership and Commitment, and Operating Excellence, key corporate safety elements and their subelements are examined. The three categories under which PSM program-level safety issues are described are Technology, Personnel, and Facilities.

  11. 77 FR 21866 - Safety Zone; Sunken Vessel, Puget Sound, Everett, WA

    Science.gov (United States)

    2012-04-12

    ... Final rule. SUMMARY: The Coast Guard is establishing a safety zone around the Vigor Marine Dry Dock... dry dock and associated debris, and to ensure the safety of the salvage crews on scene. It will do so... of the Port or his Designated Representative. DATES: This rule is effective in the CFR on April 12...

  12. Study on Food Quality and Safety Management Based on Hotel Management

    OpenAIRE

    Shi Zengye

    2017-01-01

    In recent years, with the frequent occurrence of food safety problems, people have begun to pay attention to food safety, especially the food safety of hotels. This paper proposed a Hazard Analysis and Critical Control Point (HACCP) management system to analyze food safety issues of hotels in order to improve the food quality and safety in hotel management. Through the practical application of the HACCP management system in the hotel catering industry, it was found that the amount of bacteria...

  13. Comprehensive safety analysis code system for nuclear fusion reactors III: Ex-vessel LOCA analyses considering passive safety

    International Nuclear Information System (INIS)

    Honda, T.; Okazaki, T.; Maki, K.; Uda, T.; Seki, Y.; Aoki, I.; Kunugi, T.

    1996-01-01

    Ex-vessel loss-of-coolant accidents (LOCAs) in a fusion reactor have been analyzed to investigate the possibility of passive plasma shutdown. For this purpose, a hybrid code of the plasma dynamics and thermal characteristics of the reactor structures, which has been modified to include the impurity emission from plasma-facing components (PFCs), has been developed. Ex-vessel LOCAs of the cooling system during the ignition operation in the International Thermonuclear Experimental Reactor (ITER), in which graphite PFCs were employed in conceptual design activity, were assumed. When double-ended break occurs at the cold leg of the divertor cooling system, the copper cooling tube begins to melt within 3 s after the LOCA, even though the plasma is passively shut down at nearly 4 s. An active plasma shutdown system will be needed for such rapid transient accidents. On the other hand, when a small (1%) break LOCA occurs there, the plasma is passively shut down at nearly 36 s, which happens before the copper cooling tube begins to melt. When the double-ended break LOCA occurs at the cold leg of the first-wall cooling system, there is enough time (nearly 100 s) to shut down the plasma with a controllable method before the reactor structures are damaged. 21 refs., 8 figs

  14. Safety management: a few techniques and their application

    International Nuclear Information System (INIS)

    Soundararajan, S.

    2016-01-01

    Industrial safety practice has grown in its stature tremendously since the age of industrial revolution. A number of modern techniques are available to strengthen design safety features, to review operational safety, and to critically appraise and upgrade practices of occupational safety and health management. This talk focuses on three prominent yet simple techniques and their usefulness in the overall safety management of a workplace. Any industrial set-up undergoes different stages in its life cycle-conceptual design, actual design, construction, fabrication and installation, commissioning, operation, shutdown/re-start up and decommissioning. Checklist procedure is a safety tool that can be applied at any of these stages. Thus it is a quite useful technique in safety management and accident prevention. It can serve as a form of approval from one step to another in the course of any routine or specific task. Safety Audit or Safety Review is a critical safety management appraisal tool. It gives a reasonable indication of how well a company's safety programme works, how hazards are recognised, how well employees are motivated and so on. It gives a clear picture about where a company stands as far as framing and implementation of its SHE policy is concerned. Each of the above tools is complementing each other and required to be applied at appropriate juncture in sustaining good safety management system at the workplace

  15. Safety analyses for transient behavior of plasma and in-vessel components during plasma abnormal events in fusion reactor

    International Nuclear Information System (INIS)

    Honda, Takuro; Okazaki, Takashi; Bartels, H.W.; Uckan, N.A.; Seki, Yasushi.

    1997-01-01

    Safety analyses on plasma abnormal events have been performed using a hybrid code of a plasma dynamics model and a heat transfer model of in-vessel components. Several abnormal events, e.g., increase in fueling rate, were selected for the International Thermonuclear Experimental Reactor (ITER) and transient behavior of the plasma and the invessel components during the events was analyzed. The physics model for safety analysis was conservatively prepared. In most cases, the plasma is terminated by a disruption or it returns to the original operation point. When the energy confinement improves by a factor of 2.0 in the steady state, which is a hypothetical assumption under the present plasma data, the maximum fusion power reaches about 3.3 GW at about 3.6 s and the plasma is terminated due to a disruption. However, the results obtained in this study show the confinement boundary of ITER can be kept almost intact during the abnormal plasma transients, as long as the cooling system works normally. Several parametric studies are needed to comprehend the overpower transient including structure behavior, since many uncertainties are connected to the filed of the plasma physics. And, future work will need to discuss the burn control scenario considering confinement mode transition, system specifications, experimental plans and safety regulations, etc. to confirm the safety related to the plasma anomaly. (author)

  16. Evaluation of safety management in an Appliances manufacturing company

    Directory of Open Access Journals (Sweden)

    F. Golbabaei

    2015-01-01

    Full Text Available Introduction: Prevention of accidents and work related diseases, are not allowed regardless of the safety of employees, customers, contractors and other persons. Assessment of individual safety management activities could reduce many losses. Present study aimed to evaluate the safety management of a household appliance manufacturing company.  .Material and Method: This study has done in a household appliance manufacturing company in Damavand city. Two questionnaires were firstly designed based on the weighted scores. The questionnaire 1 consisted of 4 indicators: Safety of machinery, Electrical safety, Risk assessment and Fire safety. Questionnaire 2 consisted of 11 sub indicators. Both questionnaires were completed by 30 HSE experts and supervisors. Reliability of questionnaires was based on cronbachs alpha coefficient. the safety status of each unit was determined and scored using information acquired by the questionnaires. Lastly, the safety of the entire company was determined.  .Result: Results showed that in safety management: the pressing and store house were in a good range of 66.66 and 60.12 points. Powder painting, enameling, laboratory were in a average range of 56.25, 55.92 and 54.15 points. Assembling and door storage were in a week range of 46.06 points.  .Conclusion: The findings showed that the safety status in the studied appliances company is in average range with 55.45 points. Therefore, it is recommended that the safety indicators should be improved for the betterment of the safety management in the company.

  17. Prestressed safety enclosure (PSE) with metallic cushion for new or existing reactor pressure vessels

    International Nuclear Information System (INIS)

    Wedellsborg, B.W.

    1991-01-01

    The special technology required to build the conventional types of thickwalled forged nuclear reactor pressure vessels is mastered only by a few large world-class manufactures. In order eventually to make it possible for other less established manufacturers, for example, those in newly industrialized nations, to construct nuclear RPVS or containers with large diameter for high pressures and which can tolerate large thermal gradients, an improved novel concept of a prestressed cast-iron container with multilayer shells and interlayer metallic cushions is being developed and is described in this paper. (author)

  18. Impact of Vessel Noise on Oyster Toadfish (Opsanus tau) Behavior and Implications for Underwater Noise Management

    Science.gov (United States)

    Krahforst, Cecilia S.

    Underwater noise and its impacts on marine life are growing management concerns. This dissertation considers both the ecological and social concerns of underwater noise, using the oyster toadfish (Opsanus tau) as a model species. Oyster toadfish call for mates using a boatwhistle sound, but increased ambient noise levels from vessels or other anthropogenic activities are likely to influence the ability of males to find mates. If increased ambient noise levels reduce fish fitness then underwater noise can impact socially valued ecosystem services (e.g. fisheries). The following ecological objectives of the impacts of underwater noise on oyster toadfish were investigated: (1) to determine how noise influences male calling behavior; (2) to assess how areas of high vessel activity ("noisy") and low vessel activity ("quiet") influence habitat utilization (fish standard length and occupancy rate); and (3) to discover if fitness (number of clutches and number of embryos per clutch) is lower in "noisy" compared with "quiet" sites. Field experiments were executed in "noisy" and "quiet" areas. Recorded calls by males in response to playback sounds (vessel, predator, and snapping shrimp sounds) and egg deposition by females ("noisy" vs. "quiet" sites) demonstrated that oyster toadfish are impacted by underwater noise. First, males decreased their call rates and called louder in response to increased ambient noise levels. Second, oyster toadfish selected nesting sites in areas with little or no inboard motorboat activity. Third, male oyster toadfish at "noisy" sites either had no egg clutches on their shelters or the number of embryos per clutch was significantly lower than in the "quiet" areas. Underwater noise and disturbance from vessels are influencing the fitness of the oyster toadfish. The social significance of the growing concerns regarding underwater noise was investigated by identifying dominant themes found within two types of texts: four recent underwater noise

  19. Tools for road infrastructure safety management in poland

    Directory of Open Access Journals (Sweden)

    Kustra Wojciech

    2017-01-01

    Full Text Available Road safety can be improved by implementing principles of road safety infrastructure management (RIS on the network of European roads as adopted in the Directive. The document recommends that member states should use tried and tested tools for road safety management such as: road safety impact assessment (RIA, road safety audit (RSA, safety management on existing road networks including road safety ranking (RSM and road safety inspection (RSI. The objective of the methods is to help road authorities to take rational decisions in the area of road safety and road infrastructure safety and understand the consequences occurring in the particular phases of road life cycle. To help with assessing the impact of a road project on the safety of related roads, a method was developed for long-term forecasts of accidents and accident cost estimation as well as a risk classification to identify risks that are not acceptable risks. With regard to road safety audits and road safety inspection, a set of principles was developed to identify risks and the basic classification of mistakes and omissions.

  20. 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.

  1. Management Commitment to Safety, Teamwork, and Hospital Worker Injuries.

    Science.gov (United States)

    McGonagle, Alyssa K; Essenmacher, Lynnette; Hamblin, Lydia; Luborsky, Mark; Upfal, Mark; Arnetz, Judith

    2016-01-01

    Although many studies link teamwork in health care settings to patient safety, evidence linking teamwork to hospital worker safety is lacking. This study addresses this gap by providing evidence linking teamwork perceptions in hospital workers to worker injuries, and further, finds a linkage between manager commitment to safety and teamwork. Organizational records of worker injuries and survey responses regarding management commitment to safety and teamwork from 446 hospital workers within 42 work units in a multi-site hospital system were examined. Results underscored the particular importance of teamwork on worker injuries as well as the importance of management commitment to safety as relating to teamwork. To improve worker safety, organizational leaders and unit managers should work to maintain environments wherein teamwork can thrive.

  2. Human and organizational biases affecting the management of safety

    Energy Technology Data Exchange (ETDEWEB)

    Reiman, Teemu, E-mail: teemu.reiman@vtt.fi [VTT, Espoo (Finland); Rollenhagen, Carl [KTH, Stockholm (Sweden)

    2011-10-15

    Management of safety is always based on underlying models or theories of organization, human behavior and system safety. The aim of the article is to review and describe a set of potential biases in these models and theories. We will outline human and organizational biases that have an effect on the management of safety in four thematic areas: beliefs about human behavior, beliefs about organizations, beliefs about information and safety models. At worst, biases in these areas can lead to an approach where people are treated as isolated and independent actors who make (bad) decisions in a social vacuum and who pose a threat to safety. Such an approach aims at building barriers and constraints to human behavior and neglects the measures aiming at providing prerequisites and organizational conditions for people to work effectively. This reductionist view of safety management can also lead to too drastic a strong separation of so-called human factors from technical issues, undermining the holistic view of system safety. Human behavior needs to be understood in the context of people attempting (together) to make sense of themselves and their environment, and act based on perpetually incomplete information while relying on social conventions, affordances provided by the environment and the available cognitive heuristics. In addition, a move toward a positive view of the human contribution to safety is needed. Systemic safety management requires an increased understanding of various normal organizational phenomena - in this paper discussed from the point of view of biases - coupled with a systemic safety culture that encourages and endorses a holistic view of the workings and challenges of the socio-technical system in question. - Highlights: > Biases in safety management approaches are reviewed and described. > Four thematic areas are covered: human behavior, organizations, information, safety models. > The biases influence how safety management is defined, executed

  3. Human and organizational biases affecting the management of safety

    International Nuclear Information System (INIS)

    Reiman, Teemu; Rollenhagen, Carl

    2011-01-01

    Management of safety is always based on underlying models or theories of organization, human behavior and system safety. The aim of the article is to review and describe a set of potential biases in these models and theories. We will outline human and organizational biases that have an effect on the management of safety in four thematic areas: beliefs about human behavior, beliefs about organizations, beliefs about information and safety models. At worst, biases in these areas can lead to an approach where people are treated as isolated and independent actors who make (bad) decisions in a social vacuum and who pose a threat to safety. Such an approach aims at building barriers and constraints to human behavior and neglects the measures aiming at providing prerequisites and organizational conditions for people to work effectively. This reductionist view of safety management can also lead to too drastic a strong separation of so-called human factors from technical issues, undermining the holistic view of system safety. Human behavior needs to be understood in the context of people attempting (together) to make sense of themselves and their environment, and act based on perpetually incomplete information while relying on social conventions, affordances provided by the environment and the available cognitive heuristics. In addition, a move toward a positive view of the human contribution to safety is needed. Systemic safety management requires an increased understanding of various normal organizational phenomena - in this paper discussed from the point of view of biases - coupled with a systemic safety culture that encourages and endorses a holistic view of the workings and challenges of the socio-technical system in question. - Highlights: → Biases in safety management approaches are reviewed and described. → Four thematic areas are covered: human behavior, organizations, information, safety models. → The biases influence how safety management is defined

  4. Reactor pressure vessel embrittlement management through EPRI-Developed material property databases

    International Nuclear Information System (INIS)

    Rosinski, S.T.; Server, W.L.; Griesbach, T.J.

    1997-01-01

    Uncertainties and variability in U.S. reactor pressure vessel (RPV) material properties have caused the U.S. Nuclear Regulatory Commission (NRC) to request information from all nuclear utilities in order to assess the impact of these data scatter and uncertainties on compliance with existing regulatory criteria. Resolving the vessel material uncertainty issues requires compiling all available data into a single integrated database to develop a better understanding of irradiated material property behavior. EPRI has developed two comprehensive databases for utility implementation to compile and evaluate available material property and surveillance data. RPVDATA is a comprehensive reactor vessel materials database and data management program that combines data from many different sources into one common database. Searches of the data can be easily performed to identify plants with similar materials, sort through measured test results, compare the ''best-estimates'' for reported chemistries with licensing basis values, quantify variability in measured weld qualification and test data, identify relevant surveillance results for characterizing embrittlement trends, and resolve uncertainties in vessel material properties. PREP4 has been developed to assist utilities in evaluating existing unirradiated and irradiated data for plant surveillance materials; PREP4 evaluations can be used to assess the accuracy of new trend curve predictions. In addition, searches of the data can be easily performed to identify available Charpy shift and upper shelf data, review surveillance material chemistry and fabrication information, review general capsule irradiation information, and identify applicable source reference information. In support of utility evaluations to consider thermal annealing as a viable embrittlement management option, EPRI is also developing a database to evaluate material response to thermal annealing. Efforts are underway to develop an irradiation

  5. 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)

  6. Follow-up Study of ITER Safety Analysis : Large In-vessel First Wall Pipe Break with Wet Confinement Bypass

    Energy Technology Data Exchange (ETDEWEB)

    Moon, Sung Bo; Bang, In Cheol [Ulsan National Institute of Science and Technology, Ulsan (Korea, Republic of)

    2014-10-15

    Previous researches have been analyzed risk assessments of fusion reactors that are dangerous in the severe accidents where the radioactive material released from confinement building to the environment. To simulate the severe accidents in ITER, a number of thermal hydraulics simulation codes were used. Before construction of the fusion reactor, to obtain ITER license about safety issue, MELCOR is chosen as one of the several codes to be used to perform ITER safety analyses. Qualification of the simulation code is to simulate the cooling system in ITER, the transport of radionuclides during design basis accidents (DBAs) including beyond design basis accidents (BDBAs). MELCOR is fully integrated code that models the accidents in Light Water Reactor (LWR). To analyze the accidents in ITER, MELCOR 1.8.2 version is modified. In the nuclear fusion system, the amount of released radioactive material is criteria for safety permission. Tritium (or tritiated water: HTO) and radioactive dust aerosol are the source of radioactive leakage. In the Generic Site Safety Report (GSSR) for the ITER plant, Table I lists the release guidelines for tritium and activation products for normal operation, incidents and accidents. Several accident analyses have been studied to know how much radioactive material could be released from the severe accidents. In the present work, The MELCOR input deck of large First Wall (FW) coolant leak (pipe break) is used to study and radioactive material leakage thorough bypass accident are studied to follow up the ITER safety analysis. In this research, follow-up study of the in-vessel inboard/inboard-outboard FW pipe break was analyzed to investigate the amount of leakage of radioactive aerosol. All of the accident cases released the lower amount of radioactive aerosol compared to the IAEA guide lines. In addition, the OBB pipe break made lower HTO aerosol leakage because of condensation of HTO and adsorption between coolant and aerosol.

  7. Safety management of radioisotopes and others in educational institutions

    International Nuclear Information System (INIS)

    1981-01-01

    Radioisotopes are extensively used in the fields of research in various educational institutions. While considerable progress has been seen in the safety management of RI utilization, such accidents as the loss of radioisotopes and radioactive contamination occurred. Under the situation, the safety management of RIs and others in RI-using facilities provided by the law has been examined by the ad hoc committee. A report by the committee is described as follows: need for a RI safety management organization, defining the responsibility of the chief technicians handling radiation, need for the practices of using RIs, etc. in education and traininng, planned RI-handling facilities, cautions for the loss of RIs and the contamination, centralization in RI safety management, improvement of remuneration for the chief technicians handling radiation, occasional restudy on the safety management of RIs, etc. (J.P.N.)

  8. Applying Sensor-Based Technology to Improve Construction Safety Management.

    Science.gov (United States)

    Zhang, Mingyuan; Cao, Tianzhuo; Zhao, Xuefeng

    2017-08-11

    Construction sites are dynamic and complicated systems. The movement and interaction of people, goods and energy make construction safety management extremely difficult. Due to the ever-increasing amount of information, traditional construction safety management has operated under difficult circumstances. As an effective way to collect, identify and process information, sensor-based technology is deemed to provide new generation of methods for advancing construction safety management. It makes the real-time construction safety management with high efficiency and accuracy a reality and provides a solid foundation for facilitating its modernization, and informatization. Nowadays, various sensor-based technologies have been adopted for construction safety management, including locating sensor-based technology, vision-based sensing and wireless sensor networks. This paper provides a systematic and comprehensive review of previous studies in this field to acknowledge useful findings, identify the research gaps and point out future research directions.

  9. Safety Evaluation Report: Development of Improved Composite Pressure Vessels for Hydrogen Storage, Lincoln Composites, Lincoln, NE, May 25, 2010

    Energy Technology Data Exchange (ETDEWEB)

    Fort, III, William C. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Kallman, Richard A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Maes, Miguel [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Skolnik, Edward G. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Weiner, Steven C. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2010-12-22

    Lincoln Composites operates a facility for designing, testing, and manufacturing composite pressure vessels. Lincoln Composites also has a U.S. Department of Energy (DOE)-funded project to develop composite tanks for high-pressure hydrogen storage. The initial stage of this project involves testing the permeation of high-pressure hydrogen through polymer liners. The company recently moved and is constructing a dedicated research/testing laboratory at their new location. In the meantime, permeation tests are being performed in a corner of a large manufacturing facility. The safety review team visited the Lincoln Composites site on May 25, 2010. The project team presented an overview of the company and project and took the safety review team on a tour of the facility. The safety review team saw the entire process of winding a carbon fiber/resin tank on a liner, installing the boss and valves, and curing and painting the tank. The review team also saw the new laboratory that is being built for the DOE project and the temporary arrangement for the hydrogen permeation tests.

  10. Safety management of software-based equipment

    CERN Document Server

    Boulanger, Jean-Louis

    2013-01-01

    A review of the principles of the safety of software-based equipment, this book begins by presenting the definition principles of safety objectives. It then moves on to show how it is possible to define a safety architecture (including redundancy, diversification, error-detection techniques) on the basis of safety objectives and how to identify objectives related to software programs. From software objectives, the authors present the different safety techniques (fault detection, redundancy and quality control). "Certifiable system" aspects are taken into account throughout the book. C

  11. Information About Dynamics of the Sea Surface as a Means to Improve Safety of the Unmanned Vessel at Sea

    Directory of Open Access Journals (Sweden)

    Przyborski Marek

    2016-12-01

    Full Text Available One of the fundamental states of the sea surface is its heave. Despite of years of the intense scientific inquiry, no clear understanding of the influence of this aspect on the dynamics of the sea environment has emerged. The separation of two nearby fluid elements which one may observed for example as a free floating of small objects on the sea surface (rescuers on the rough sea or small research vessels is caused by the interaction of different components. On the other hand one may say that the heave of the sea is also a summary interaction of a few components describing the dynamics of the sea. Therefore it is the most important aspect, which influenced the dispersion phenomenon. This observation has important consequences for many different problems as for example conducting Search and Rescue missions and using unmanned ships. We would like to present results of our experiment focused on finding the answer to question about nature of the heave of the sea and its influence on safety of Unmanned Surface Vessels (USV.

  12. Research on station management in subway operation safety

    Science.gov (United States)

    Li, Yiman

    2017-10-01

    The management of subway station is an important part of the safe operation of urban subway. In order to ensure the safety of subway operation, it is necessary to study the relevant factors that affect station management. In the protection of subway safety operations on the basis of improving the quality of service, to promote the sustained and healthy development of subway stations. This paper discusses the influencing factors of subway operation accident and station management, and analyzes the specific contents of station management security for subway operation, and develops effective suppression measures. It is desirable to improve the operational quality and safety factor for subway operations.

  13. Regulatory instrument review: Management of aging of LWR [light water reactor] major safety-related components

    International Nuclear Information System (INIS)

    Werry, E.V.

    1990-10-01

    This report comprises Volume 1 of a review of US nuclear plant regulatory instruments to determine the amount and kind of information they contain on managing the aging of safety-related components in US nuclear power plants. The review was conducted for the US Nuclear Regulatory Commission (NRC) by the Pacific Northwest Laboratory (PNL) under the NRC Nuclear Plant Aging Research (NPAR) Program. Eight selected regulatory instruments, e.g., NRC Regulatory Guides and the Code of Federal Regulations, were reviewed for safety-related information on five selected components: reactor pressure vessels, steam generators, primary piping, pressurizers, and emergency diesel generators. Volume 2 will be concluded in FY 1991 and will also cover selected major safety-related components, e.g., pumps, valves and cables. The focus of the review was on 26 NPAR-defined safety-related aging issues, including examination, inspection, and maintenance and repair; excessive/harsh testing; and irradiation embrittlement. The major conclusion of the review is that safety-related regulatory instruments do provide implicit guidance for aging management, but include little explicit guidance. The major recommendation is that the instruments be revised or augmented to explicitly address the management of aging

  14. 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.

  15. Management of safety and safety culture at the NPPs of Ukraine

    International Nuclear Information System (INIS)

    Koltakov, Vladimir

    2002-01-01

    The report contains general aspects of safety and safety culture. The brief description of operational characteristics and basic indexes of atomic power plants at the Ukraine are represented. The information referring to structure of NPPs of Operation organization license-holder, safety responsibility of both Regulatory and Utility Bodies also is given. The main part of the report include seven sections: 1. Practical application of safety management models; 2. erspective on the relationship between safety management and safety culture; 3. The role of leadership in achieving high standards of safety; 4. Current and future challengers that impact on safety culture and safety management (e.g. the impact of competition, changing, economic and political circumstances, workforce demographics, etc.); 5. Key lessons learned from major events; 6. Practical applications of safety culture concepts (e.g. learning organizations, training staff communications, etc.); 7. dvance in human performance. Some of the main pending safety and safety culture problems that are necessary to achieve in the near future are mentioned

  16. Norwegian national report. Joint convention on the safety of spent fuel management and on the safety of radioactive waste management

    International Nuclear Information System (INIS)

    2011-11-01

    This report contains the national report from Norway to the fourth review meeting of the JointConvention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management to be held 14-23 May 2012. (Author)

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

    Science.gov (United States)

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

    2012-07-01

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

  18. Perceived safety management practices in the logistics sector.

    Science.gov (United States)

    Auyong, Hui-Nee; Zailani, Suhaiza; Surienty, Lilis

    2016-03-09

    Malaysia's progress on logistics has been slowed to keep pace with its growth in trade. The Government has been pressing companies to improve the safety of their activities in order to reduce society's loss due to occupational accidents and illnesses. Occupational safety and health is a crucial part of a workplace because every worker has to take care of his/her own safety and health. The main occupational safety and health (OSH) national policy in Malaysia is the enactment of the Occupational Safety and Health Act (OSHA) 1994. Only those companies which have excellent health and safety care have good quality and productive employees. This study investigated safety management practices in the logistics sector. The present study is concerned with the human factors to safety in the logistics industry. The authors examined the perceived safety management practices of workers in the logistics sector. The purpose was to identify the perception of safety management practices of Malaysian logistics personnel. Survey questionnaires were distributed to assess logistics personnel about management commitment. The quantitative method using the availability sampling method was applied. The data gathered from the survey were analysed using SPSS software. The responses to the survey were rated according to the Likert scale type, with '1' indicating strongly disagree and '5' indicating strongly agree. One hundred and three employees of logistics functions completed the survey. The highest mean scores were found for fire apparatus, prioritisation of safety, and safety policy. The results from this study also emphasise the importance of the management's commitment in enhancing workplace safety. Specifically, companies should maintain good relations between the employer and the employee to help reduce workplace injuries.

  19. Pedestrian safety management using the risk-based approach

    Directory of Open Access Journals (Sweden)

    Romanowska Aleksandra

    2017-01-01

    Full Text Available The paper presents a concept of a multi-level pedestrian safety management system. Three management levels are distinguished: strategic, tactical and operational. The basis for the proposed approach to pedestrian safety management is a risk-based method. In the approach the elements of behavioural and systemic theories were used, allowing for the development of a formalised and repeatable procedure integrating the phases of risk assessment and response to the hazards of road crashes involving pedestrians. Key to the method are tools supporting pedestrian safety management. According to the risk management approach, the tools can be divided into two groups: tools supporting risk assessment and tools supporting risk response. In the paper attention is paid to selected tools supporting risk assessment, with particular emphasis on the methods for estimating forecasted pedestrian safety measures (at strategic, national and regional level and identification of particularly dangerous locations in terms of pedestrian safety at tactical (regional and local and operational level. The proposed pedestrian safety management methods and tools can support road administration in making rational decisions in terms of road safety, safety of road infrastructure, crash elimination measures or reducing the consequences suffered by road users (particularly pedestrians as a result of road crashes.

  20. Relevance of microbial finished product testing in food safety management

    DEFF Research Database (Denmark)

    Zwietering, Marcel H.; Jacxsens, Liesbeth; Membré, Jeanne Marie

    2016-01-01

    Management of microbiological food safety is largely based on good design of processes, products and procedures. Finished product testing may be considered as a control measure at the end of the production process. However, testing gives only very limited information on the safety status of a food......-active way by implementing an effective food safety management system. For verification activities in a food safety management system, finished product testing may however be useful. For three cases studies; canned food, chocolate and cooked ham, the relevance of testing both of finished products....... If a hazardous organism is found it means something, but absence in a limited number of samples is no guarantee of safety of a whole production batch. Finished product testing is often too little and too late. Therefore most attention should be focussed on management and control of the hazards in a more pro...

  1. The Research on Safety Management Information System of Railway Passenger Based on Risk Management Theory

    Science.gov (United States)

    Zhu, Wenmin; Jia, Yuanhua

    2018-01-01

    Based on the risk management theory and the PDCA cycle model, requirements of the railway passenger transport safety production is analyzed, and the establishment of the security risk assessment team is proposed to manage risk by FTA with Delphi from both qualitative and quantitative aspects. The safety production committee is also established to accomplish performance appraisal, which is for further ensuring the correctness of risk management results, optimizing the safety management business processes and improving risk management capabilities. The basic framework and risk information database of risk management information system of railway passenger transport safety are designed by Ajax, Web Services and SQL technologies. The system realizes functions about risk management, performance appraisal and data management, and provides an efficient and convenient information management platform for railway passenger safety manager.

  2. On safety management and nuclear safety - A frame of reference for studies of safety management with examples from non-nuclear contects of relevance for nuclear safety

    International Nuclear Information System (INIS)

    Svenson, O.; Allwin, P.; Salo, I.

    2004-03-01

    The report includes three case studies of safety management. The studies are presented as chapters, but are written in a format that makes them easy to read separately. Two of the studies cover regulators (the Swedish Civil Aviation Safety Authority, Luftfartsinspektionen) and the Norwegian Petroleum Directorate) and one a regulated activity/industry (a car manufacturer, Volvo Car). The introduction outlines a living system framework and relates this to concepts used in organizational management. The report concludes with some findings with potential relevance for safety management in the nuclear power domain. In the next phase of the work, the regulated counterparts of the regulators here will be investigated in addition to a fourth case study of a regulated activity/industry. (au)

  3. Simulation modeling on the growth of firm's safety management capability

    Institute of Scientific and Technical Information of China (English)

    LIU Tie-zhong; LI Zhi-xiang

    2008-01-01

    Aiming to the deficiency of safety management measure, established simulation model about firm's safety management capability(FSMC) based on organizational learning theory. The system dynamics(SD) method was used, in which level and rate system, variable equation and system structure flow diagram was concluded. Simulation model was verified from two aspects: first, model's sensitivity to variable was tested from the gross of safety investment and the proportion of safety investment; second, variables dependency was checked up from the correlative variable of FSMC and organizational learning. The feasibility of simulation model is verified though these processes.

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

    International Nuclear Information System (INIS)

    Amauchi, Hiroshi; Nishimura, Kenji; Izumi, Kokichi

    2007-01-01

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

  5. Making the link between radiological assessment, nuclear safety assessment and environmental impact assessment, as applied to unloading of the Lepse spent fuel storage vessel

    International Nuclear Information System (INIS)

    Smith, Graham M.; Sneve, Malgorzata K.; Markarov, Valentine G.

    2000-01-01

    Planning and optimisation of radioactive waste management operations is a complicated task involving scientific, technical and social issues. There are many factors which have to be balanced, involving trade-offs such as those between safety now and long term safety; between protection of human health and protection of the environment as a whole; between protection of workers and protection of the public; and between mitigation of risks of major accidents and mitigation of routine low-level but certain to occur risks. Managing the spent fuel currently stored on the Lepse vessel in Murmansk offers as big a challenge as any other in this context. The Russian Federation state regulatory process imposes strict requirements on operators to demonstrate adequate safety, environmental and human health protection. Practically, however, there is little experience in Russia or elsewhere on how to combine all the issues referred to above within an overall assessment that leads to informed decision making. The paper will describe the components of assessment work being considered within the context of the regulatory planning of Lepse unloading operations. The scope will focus on radiation protection issues but also include non-radioactive pollution risks and other safety issues have to be taken into account if a truly optimal allocation and application of resources is to be made. Consideration will be given to radiation worker dose and other health risk assessments for routine operations, safety assessments of special operations such as spent fuel handling; and the radiological and other environmental and human health impacts of planned releases of effluents to the biosphere. The need to identify and collate particular relevant information will discussed and the links between the different components of the overall assessment will be identified with a view to improving the overall effectiveness of the assessment process. The problem of combining all the information coherently

  6. Coupling finite elements and reliability methods - application to safety evaluation of pressurized water reactor vessels

    International Nuclear Information System (INIS)

    Pitner, P.; Venturini, V.

    1995-02-01

    When reliability studies are extended form deterministic calculations in mechanics, it is necessary to take into account input parameters variabilities which are linked to the different sources of uncertainty. Integrals must then be calculated to evaluate the failure risk. This can be performed either by simulation methods, or by approximations ones (FORM/SORM). Model in mechanics often require to perform calculation codes. These ones must then be coupled with the reliability calculations. Theses codes can involve large calculation times when they are invoked numerous times during simulations sequences or in complex iterative procedures. Response surface method gives an approximation of the real response from a reduced number of points for which the finite element code is run. Thus, when it is combined with FORM/SORM methods, a coupling can be carried out which gives results in a reasonable calculation time. An application of response surface method to mechanics reliability coupling for a mechanical model which calls for a finite element code is presented. It corresponds to a probabilistic fracture mechanics study of a pressurized water reactor vessel. (authors). 5 refs., 3 figs

  7. Measuring enterprise proactiveness in managing occupational safety

    DEFF Research Database (Denmark)

    Sønderstrup-Andersen, Hans H. K.; Fløcke, Thomas; Mikkelsen, Kim Lyngby

    2010-01-01

    The aim of this paper is to communicate results, and lessons learned, from developing and applying a national questionnaire based survey for measuring the initiation of occupational safety activities in Danish enterprises and public institutions1. The survey is cross-sectional and it is part...... on the safety attitude index....

  8. Measuring and managing safety at Wahleach Dam

    International Nuclear Information System (INIS)

    Salmon, G. M.; Cattanach, J. D.; Hartford, D. N. D.

    1996-01-01

    Safety improvements recently implemented at the Wahleach Dam were described as one of the first instances in international dam safety practice where risk concepts have been used in conjunction with acceptable risk criteria to evaluate safety of a dam relative to required level of safety. Erosion was identified as the greatest threat to the safety of the dam. In addressing the deficiencies B.C. Hydro formulated a process which advocates a balanced level of safety,i.e. the probability of failure multiplied by the consequences of failure, integrated over a range of initiators. If the risk posed by the dam is lower than a 'tolerable' risk, the dam is considered to be safe enough. In the case of the Wahleach Dam, the inflow design flood (IDF) was selected to be about one half of the probable maximum flow (PMF), hence it was more likely than not that the spillway could pass floods up to and including the PMF. By accepting the determined level of risk, expenditures of several million dollars for design and construction of dam safety improvements were made redundant. Another byproduct of this new concept of risk assessment was the establishment of improved life safety protection by means of an early warning system for severe floods through the downstream community and emergency authorities. 3 refs., 5 tabs

  9. Use of safety management practices for improving project performance.

    Science.gov (United States)

    Cheng, Eddie W L; Kelly, Stephen; Ryan, Neal

    2015-01-01

    Although site safety has long been a key research topic in the construction field, there is a lack of literature studying safety management practices (SMPs). The current research, therefore, aims to test the effect of SMPs on project performance. An empirical study was conducted in Hong Kong and the data collected were analysed with multiple regression analysis. Results suggest that 3 of the 15 SMPs, which were 'safety committee at project/site level', 'written safety policy', and 'safety training scheme' explained the variance in project performance significantly. Discussion about the impact of these three SMPs on construction was provided. Assuring safe construction should be an integral part of a construction project plan.

  10. A proposal of safety indicators aggregation to assess the safety management effectiveness of nuclear power plants

    International Nuclear Information System (INIS)

    Carvalho, Jose Antonio B.; Saldanha, Pedro L.C.; Melo, Paulo F.F. Frutuoso e

    2009-01-01

    Safety management has changed with the evolution of management methods, named Quality Systems, moving from Quality Control, where the focus was the product, passing through Quality Assurance, which takes care of the whole manufacturing process and reaching the Total Quality Management, where policies and goals are established. Nowadays, there is a trend towards Management Systems, which integrate all different aspects related to the management of an organization (safety, environment, security, quality, costs and, etc), but it is necessary to have features to establish and assure that safety overrides the remaining aspects. The most usual way to reach this goal is to establish a policy where safety is a priority, but its implementation and the assessment of its effectiveness are no so simple. Nuclear power plants usually have over a hundred safety indicators in many processes dedicated to prevent and detect problems, although a lot of them do not evaluate these indicators in an integrated manner or point out degradation trends of organizational aspects, which can affect the plant safety. This work develops an aggregation of proactive and reactive safety indicators in order to evaluate the effectiveness of nuclear power plant safety management and to detect, at early stages, signs of process degradation or activities used to establish, maintain and assure safety conditions. The aggregation integrates indicators of the usual processes and is based on the manner the management activities have been developed in the last decades, that is: Planning, Doing, Checking and Acting - known as PDCA cycle - plus a fifth element related to the capability of those who perform safety activities. The proposed aggregation is in accordance to Brazilian standards and international recommendations and constitutes a friendly link between the top management level and the daily aspects of the organization. (author)

  11. A proposal of safety indicators aggregation to assess the safety management effectiveness of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Carvalho, Jose Antonio B.; Saldanha, Pedro L.C. [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil). Coordenacao-Geral de Reatores e Ciclo Combustivel], e-mail: jantonio@cnen.gov.br, e-mail: saldanha@cnen.gov.br; Melo, Paulo F.F. Frutuoso e [Coordenacao dos Programas de Pos-graduacao de Engenharia (COPPE/UFRJ), Rio de Janeiro, RJ (Brazil). Programa de Engenharia Nuclear], e-mail: frutuoso@con.ufrj.br

    2009-07-01

    Safety management has changed with the evolution of management methods, named Quality Systems, moving from Quality Control, where the focus was the product, passing through Quality Assurance, which takes care of the whole manufacturing process and reaching the Total Quality Management, where policies and goals are established. Nowadays, there is a trend towards Management Systems, which integrate all different aspects related to the management of an organization (safety, environment, security, quality, costs and, etc), but it is necessary to have features to establish and assure that safety overrides the remaining aspects. The most usual way to reach this goal is to establish a policy where safety is a priority, but its implementation and the assessment of its effectiveness are no so simple. Nuclear power plants usually have over a hundred safety indicators in many processes dedicated to prevent and detect problems, although a lot of them do not evaluate these indicators in an integrated manner or point out degradation trends of organizational aspects, which can affect the plant safety. This work develops an aggregation of proactive and reactive safety indicators in order to evaluate the effectiveness of nuclear power plant safety management and to detect, at early stages, signs of process degradation or activities used to establish, maintain and assure safety conditions. The aggregation integrates indicators of the usual processes and is based on the manner the management activities have been developed in the last decades, that is: Planning, Doing, Checking and Acting - known as PDCA cycle - plus a fifth element related to the capability of those who perform safety activities. The proposed aggregation is in accordance to Brazilian standards and international recommendations and constitutes a friendly link between the top management level and the daily aspects of the organization. (author)

  12. 49 CFR 385.321 - What failures of safety management practices disclosed by the safety audit will result in a...

    Science.gov (United States)

    2010-10-01

    ... disclosed by the safety audit will result in a notice to a new entrant that its USDOT new entrant... MOTOR CARRIER SAFETY REGULATIONS SAFETY FITNESS PROCEDURES New Entrant Safety Assurance Program § 385.321 What failures of safety management practices disclosed by the safety audit will result in a notice...

  13. Management of National Nuclear Power Programs for assured safety

    International Nuclear Information System (INIS)

    Connolly, T.J.

    1985-01-01

    Topics discussed in this report include: nuclear utility organization; before the Florida Public Service Commission in re: St. Lucie Unit No. 2 cost recovery; nuclear reliability improvement and safety operations; nuclear utility management; training of nuclear facility personnel; US experience in key areas of nuclear safety; the US Nuclear Regulatory Commission - function and process; regulatory considerations of the risk of nuclear power plants; overview of the processes of reliability and risk management; management significance of risk analysis; international and domestic institutional issues for peaceful nuclear uses; the role of the Institute of Nuclear Power Operations (INPO); and nuclear safety activities of the International Atomic Energy Agency (IAEA)

  14. Management of National Nuclear Power Programs for assured safety

    Energy Technology Data Exchange (ETDEWEB)

    Connolly, T.J. (ed.)

    1985-01-01

    Topics discussed in this report include: nuclear utility organization; before the Florida Public Service Commission in re: St. Lucie Unit No. 2 cost recovery; nuclear reliability improvement and safety operations; nuclear utility management; training of nuclear facility personnel; US experience in key areas of nuclear safety; the US Nuclear Regulatory Commission - function and process; regulatory considerations of the risk of nuclear power plants; overview of the processes of reliability and risk management; management significance of risk analysis; international and domestic institutional issues for peaceful nuclear uses; the role of the Institute of Nuclear Power Operations (INPO); and nuclear safety activities of the International Atomic Energy Agency (IAEA).

  15. Safety analysis of Atucha 1 reactor pressure vessel for a typical transient

    International Nuclear Information System (INIS)

    Chomik, E.; Jinchuk, D.

    1994-01-01

    As a consequence of disturbances on the CNA I external electric grid some incidents were produced in a 6 minutes lapse, causing a sudden cooling of the primary system, while pressure was maintained nearly constant. On the basis of this event, a safety analysis based on the LInear Elastic Fracture Mechanics was carried out. This paper presents an alternative method for the calculation of transients; the Finite Element Method, particularly, the OCA-II FEM code. By using this method it was possible to demonstrate, for this event, a safe operating condition for the end of life of the RPV, with regard to brittle fracture risk. 6 refs, 11 figs, 1 tab

  16. Proceedings of the twenty-fourth water reactor safety information meeting. Volume 2: Reactor pressure vessel embrittlement and thermal annealing; Reactor vessel lower head integrity; Evaluation and projection of steam generator tube condition and integrity

    Energy Technology Data Exchange (ETDEWEB)

    Monteleone, S. [comp.] [Brookhaven National Lab., Upton, NY (United States)

    1997-02-01

    This three-volume report contains papers presented at the Twenty-Fourth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, October 21--23, 1996. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from Czech Republic, Finland, France, Japan, Norway, Russia and United Kingdom. This volume is divided into the following sections: reactor pressure vessel embrittlement and thermal annealing; reactor vessel lower head integrity; and evaluation and projection of steam generator tube condition and integrity. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

  17. Proceedings of the twenty-fourth water reactor safety information meeting. Volume 2: Reactor pressure vessel embrittlement and thermal annealing; Reactor vessel lower head integrity; Evaluation and projection of steam generator tube condition and integrity

    International Nuclear Information System (INIS)

    Monteleone, S.

    1997-02-01

    This three-volume report contains papers presented at the Twenty-Fourth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, October 21--23, 1996. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from Czech Republic, Finland, France, Japan, Norway, Russia and United Kingdom. This volume is divided into the following sections: reactor pressure vessel embrittlement and thermal annealing; reactor vessel lower head integrity; and evaluation and projection of steam generator tube condition and integrity. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database

  18. Nuclear and radiation safety assurance federal target programme management system

    International Nuclear Information System (INIS)

    Kryukov, O.V.; Vasil'ev, V.A.; Nikishin, D.A.; Linge, I.I.; Obodinskij, A.N.

    2012-01-01

    The Federal Program Nuclear and Radiation Safety Assurance for 2008-2015 is presented. Specifics of Federal target program management as well as changes to program management are discussed. Data on evaluation of management effectiveness is given. Further efforts to resolve the nuclear legacy problem in Russia are also presented [ru

  19. Occupational health and safety management in micro and small enterprises

    DEFF Research Database (Denmark)

    Hasle, Peter

    2015-01-01

    Occupational health and safety management (OHSM) in micro and small enterprises may look like an odd ex-pression. Most owner-managers do not think of OHSM as something to give priority. They are occupied with management of the core business which in many cases constitute a simple fight for survival...

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

    International Nuclear Information System (INIS)

    Ali, T.H.; Memon, N.A.

    2008-01-01

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

  1. Managing for safety and safety culture within the UK nuclear industry. A regulator's perspective

    International Nuclear Information System (INIS)

    Tyrer, M.J.

    2002-01-01

    This paper outlines the basis of the legal system for the regulation of health and safety at work within the United Kingdom (UK), and in particular, the regulation of the nuclear industry. The framework, formulated by the regulator, which has been published as a practical guide for directors, managers, health and safety professionals and employee representatives for the successful management of health and safety is explained. This guidance, however, concentrates, to a large extent, on management systems and only addresses in part the types of issues, such as behaviours, values, attitudes and beliefs which contribute to the safety culture of an organization. The regulator of the UK nuclear industry has considered research, and other work, carried out by several organizations in this area, notably the Advisory Committee on the Safety of Nuclear Installations (ACSNI) and the International Atomic Energy Agency (IAEA), and produced its own framework for managing for safety at nuclear installations. As a regulator, the Health and Safety Executive (HSE), and its inspectorate responsible for regulation of the nuclear industry, HM Nuclear Installations Inspectorate (HMNII), are not the appropriate organization to assess the safety culture of an organization, but positively encourage organizations to both carry out this assessment themselves and to monitor their performance. To this end, HSE has developed, and made available, the Health and Safety Climate Tool which is aimed at providing organizations with information which can be used as part of a continuous improvement process. (author)

  2. Safety Management and Safety Culture Self Assessment of Kartini Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Syarip, S., E-mail: syarip@batan.go.id [Centre for Accelerator and Material Process Technology, National Nuclear Energy Agency (BATAN), Yogyakarta (Indonesia)

    2014-10-15

    The self-assessment of safety culture and safety management status of Kartini research reactor is a step to foster safety culture and management by identifying good practices and areas for improvement, and also to improve reactor safety in a whole. The method used in this assessment is based on questionnaires provided by the Forum for Nuclear Cooperation in Asia (FNCA), then reviewed by experts. Based on the assessment and evaluation results, it can be concluded that there were several good practices in maintaining the safety status of Kartini reactor such as: reactor operators and radiation protection workers were aware and knowledgeable of the safety standards and policies that apply to their operation, readily accept constructive criticism from their management and from the inspectors of regulatory body that address safety performance. As a proof, for the last four years the number of inspection/audit findings from Regulatory Body (BAPETEN) tended to decrease while the reactor utilization and its operating hour increased. On the other hands there were also some comments and recommendations for improvement of reactor safety culture, such as that there should be more frequent open dialogues between employees and managers, to grow and attain a mutual support to achieve safety goals. (author)

  3. Safety in waste management plants: An Indian perspective

    International Nuclear Information System (INIS)

    Shekhar, P.; Ozarde, P.D.; Gandhi, P.M.

    2000-01-01

    Assurance of safety of public and plant workers and protection of the environment are prime objectives in the design and construction of Waste Management Plants. In India, waste management principles and strategies have been evolved in accordance with national and international regulations and standards for radiation protection. The regulations governing radiation protection have a far-reaching impact on the management of the radioactive waste. The wastes arise at each stages of the fuel cycle with varying chemical nature, generation rate and specific activity levels depending upon the type of the facility. Segregation of waste based on its chemical nature and specific activity levels is an essential feature, as its aids in selection of treatment and conditioning process. Selection of the process, equipment and materials in the plant, are governed by safety consideration alongside factors like efficiency and simplicity. The plant design considerations like physical separation, general arrangement, ventilation zoning, access control, remote handling, process piping routing, decontamination etc. have major role in realizing waste safety. Stringent quality control measures during all stages of construction have helped in achieving the design intended safety. These aspects together with operating experience gained form basis for the improved safety features in the design and construction of waste management plants. The comprehensive safety is derived from adoption of waste management strategies and appropriate plant design considerations. The paper briefly brings safety in waste management programme in India, in its current perspective. (author)

  4. Study Of Safety Management By Using Gis In Coimbatore

    Directory of Open Access Journals (Sweden)

    S. Kanchana

    2015-08-01

    Full Text Available The safety management is very important in the process of construction .The traditional methods of construction safety control cannot meet the construction of big project. To ensure the safety of construction and reduce accidents in the process of construction the current situation and problems we face in construction safety management should be studied first. And then the project risk warning mechanism based on the GIS is constructed according to the problems we faced to achieve visual monitoring and warning of construction safety risk management and to provide decision support for construction. This project aims to develop a web-based spatial decision support system model for proactive health and safety management in linear construction projects. 5 Currently health and safety management is usually performed reactively instead of proactive management since hazard identification and risk assessment is mostly performed on paper based documents that are not effectively used at site. An information system relates to a chain of operations lead to planning the observation and collection of data to storage and analysis of data to the use of derived information in decision-making processes. To create a web-based free and open sourced GIS that can work with different data formats by exchanging and presenting data as a real-time map on web.

  5. The practical implementation of integrated safety management for nuclear safety analysis and fire hazards analysis documentation

    International Nuclear Information System (INIS)

    COLLOPY, M.T.

    1999-01-01

    In 1995 Mr. Joseph DiNunno of the Defense Nuclear Facilities Safety Board issued an approach to describe the concept of an integrated safety management program which incorporates hazard and safety analysis to address a multitude of hazards affecting the public, worker, property, and the environment. Since then the U S . Department of Energy (DOE) has adopted a policy to systematically integrate safety into management and work practices at all levels so that missions can be completed while protecting the public, worker, and the environment. While the DOE and its contractors possessed a variety of processes for analyzing fire hazards at a facility, activity, and job; the outcome and assumptions of these processes have not always been consistent for similar types of hazards within the safety analysis and the fire hazard analysis. Although the safety analysis and the fire hazard analysis are driven by different DOE Orders and requirements, these analyses should not be entirely independent and their preparation should be integrated to ensure consistency of assumptions, consequences, design considerations, and other controls. Under the DOE policy to implement an integrated safety management system, identification of hazards must be evaluated and agreed upon to ensure that the public. the workers. and the environment are protected from adverse consequences. The DOE program and contractor management need a uniform, up-to-date reference with which to plan. budget, and manage nuclear programs. It is crucial that DOE understand the hazards and risks necessarily to authorize the work needed to be performed. If integrated safety management is not incorporated into the preparation of the safety analysis and the fire hazard analysis, inconsistencies between assumptions, consequences, design considerations, and controls may occur that affect safety. Furthermore, confusion created by inconsistencies may occur in the DOE process to grant authorization of the work. In accordance with

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

    Science.gov (United States)

    Mitchell, Rebecca; Friswell, Rena; Mooren, Lori

    2012-07-01

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

  7. Safety culture and quality management of Kartini research reactor

    Energy Technology Data Exchange (ETDEWEB)

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

    1999-10-01

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

  8. Safety culture and quality management of Kartini research reactor

    International Nuclear Information System (INIS)

    Syarip; Hauptmanns, Ulrich

    1999-01-01

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

  9. Swedish REGULATORY APPROACH TO SAFETY Assessment AND SEVERE ACCIDENT MANAGEMENT

    International Nuclear Information System (INIS)

    Frid, W.; Sandervaag, O.

    1997-01-01

    The Swedish regulatory approach to safety assessment and severe accident management is briefly described. The safety assessment program, which focuses on prevention of incidents and accidents, has three main components: periodic safety reviews, probabilistic safety analysis, and analysis of postulated disturbances and accident progression sequences. Management and man-technology-organisation issues, as well as inspections, play a key role in safety assessment. Basis for severe accident management were established by the Government decisions in 1981 and 1986. By the end of 1988, the severe accident mitigation systems and emergency operating procedures were implemented at all Swedish reactors. The severe accident research has continued after 1988 for further verification of the protection provided by the systems and reduction of remaining uncertainties in risk dominant phenomena

  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. 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.

  12. Development of a safety management protocol.

    Science.gov (United States)

    2008-09-01

    The UC Berkeley Traffic Safety Center (TSC) has produced this report under a contract from the California Department of Transportation : (Caltrans). The aim is to address workplace injuries and accidents among Caltrans employees and develop recommend...

  13. Safety culture management and quantitative indicator evaluation

    International Nuclear Information System (INIS)

    Mandula, J.

    2002-01-01

    This report discuses a relationship between safety culture and evaluation of quantitative indicators. It shows how a systematic use of generally shared operational safety indicators may contribute to formation and reinforcement of safety culture characteristics in routine plant operation. The report also briefly describes the system of operational safety indicators used at the Dukovany plant. It is a PC database application enabling an effective work with the indicators and providing all users with an efficient tool for making synoptic overviews of indicator values in their links and hierarchical structure. Using color coding, the system allows quick indicator evaluation against predefined limits considering indicator value trends. The system, which has resulted from several-year development, was completely established at the plant during the years 2001 and 2002. (author)

  14. Effectively managing public concerns about immunization safety

    Directory of Open Access Journals (Sweden)

    2002-01-01

    Full Text Available Los beneficios de la vacunación frente a las enfermedades prevenibles de este modo son muy superiores a sus mínimos riesgos. Con el fin de mantener o fortalecer los programas nacionales de vacunación, los trabajadores de todos los niveles de la salud pública deberían recibir formación sobre los temas relacionados con la vacunación y estar preparados para responder a las dudas planteadas por el público. Una respuesta rápida y franca a los temores del público acerca de las vacunas podría garantizar la integridad de los programas de vacunación en todo el continente americano, según el documento "Directrices para enfrentarse a los temores sobre la seguridad de las vacunaciones" (Guidelines for Managing Immunization Safety Concerns, elaborado por la División de Vacunas e Inmunización de la Organización Panamericana de la Salud (OPS y resumido aquí. Todo acontecimiento médico que se considere posiblemente relacionado con una vacuna debe ser investigado en el ámbito local. Si su distribución temporal y los síntomas respaldan la sospecha de que pueda estar relacionado con una vacuna, se debe iniciar una investigación más formal y, una vez finalizada, el acontecimiento debe ser clasificado en una de las cuatro categorías siguientes: 1 relacionado con el programa, 2 relacionado con la vacuna, 3 no relacionado, o 4 desconocido (investigación no concluyente. Dependiendo de la categoría a la que haya sido asignado el acontecimiento, las acciones posteriores pueden consistir en tranquilizar a los padres, a los cuidadores y a otros adultos; comunicarse con el público y con otros trabajadores de la salud; instaurar tratamiento; corregir los errores del programa, como pueden ser la manipulación de la vacuna, su almacenamiento, su administration o los problemas relacionados con la jeringuilla; comentar con los fabricantes problemas relacionados con la calidad y eficacia de la vacuna; retirar la vacuna del mercado, o iniciar nuevas

  15. Strengthening of nuclear power plant construction safety management

    International Nuclear Information System (INIS)

    Yu Jun

    2012-01-01

    The article describes the warning of the Fukushima nuclear accident, and analyzes the major nuclear safety issues in nuclear power development in China, problems in nuclear power plants under construction, and how to strengthen supervision and management in nuclear power construction. It also points out that the development of nuclear power must attach great importance to the safety, and nuclear power plant construction should strictly implement the principle of 'safety first and quality first'. (author)

  16. 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

  17. Probabilistic safety assessment in nuclear power plant management

    International Nuclear Information System (INIS)

    Holloway, N.J.

    1989-06-01

    Probabilistic Safety Assessment (PSA) techniques have been widely used over the past few years to assist in understanding how engineered systems respond to abnormal conditions, particularly during a severe accident. The use of PSAs in the design and operation of such systems thus contributes to the safety of nuclear power plants. Probabilistic safety assessments can be maintained to provide a continuous up-to-date assessment (Living PSA), supporting the management of plant operations and modifications

  18. 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

  19. 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".

  20. 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

  1. workplace safety management as correlates of wellbeing among ...

    African Journals Online (AJOL)

    User

    2017-12-28

    Dec 28, 2017 ... ABSTRACT. Significant proportion of Nigerians working in manufacturing firms do not enjoy the desirable level of wellbeing when it comes to safety and health. Safety management practices of industries have implications for employees' wellbeing and productivity. This study investigates relationship ...

  2. Relevance of microbial finished product testing in food safety management

    NARCIS (Netherlands)

    Zwietering, M.H.; Jacxsens, L.; Membre, J.M.; Nauta, M.; Peterz, M.

    2016-01-01

    Management of microbiological food safety is largely based on good design of processes, products and procedures. Finished product testing may be considered as a control measure at the end of the production process. However, testing gives only very limited information on the safety status of a food.

  3. 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.

  4. RISK MANAGEMENT AS TRANSPORTATION SAFETY PROVISION INSTRUMENT IN RUSSIA

    OpenAIRE

    V. A. Nikolayev

    2012-01-01

    Safety of transportation in Russia is subject to a variety of threats. Discussed in the article are characteristics of major threats to transportation security. State transportation policy directions that make it possible to ensure the security of cargo and passenger transportation are shown. A listof activities and innovative risk management tools that provide for improved safety of railway transportation is proposed.

  5. RISK MANAGEMENT AS TRANSPORTATION SAFETY PROVISION INSTRUMENT IN RUSSIA

    Directory of Open Access Journals (Sweden)

    V. A. Nikolayev

    2012-01-01

    Full Text Available Safety of transportation in Russia is subject to a variety of threats. Discussed in the article are characteristics of major threats to transportation security. State transportation policy directions that make it possible to ensure the security of cargo and passenger transportation are shown. A listof activities and innovative risk management tools that provide for improved safety of railway transportation is proposed.

  6. Preclinical efficacy and safety of herbal formulation for management ...

    African Journals Online (AJOL)

    Preclinical efficacy and safety of herbal formulation for management of wounds. ... The effects of the treatments on rate of wound closure, epithelialisation time ... inflammation and better tissue remodeling for rats treated with herbal product.

  7. Health and safety management practices in small and medium ...

    African Journals Online (AJOL)

    Health and safety management practices in small and medium enterprises in the ... on national economies, the construction industry receives additional attention in ... and training were considered key factors of H&S for SMCEs at project level.

  8. Research on asset management for safety and operations.

    Science.gov (United States)

    2011-11-01

    The Texas Department of Transportation (TxDOT) is challenged with managing a wide range of : transportation safety and operations assets in order to respond to public and other outside interests. These : assets include, but are not limited to pavemen...

  9. Enhancing NPP Safety Through an Effective Dependability Management

    Energy Technology Data Exchange (ETDEWEB)

    Vieru, G., E-mail: g_vieru@yahoo.com [AREN, Bucharest (Romania)

    2014-10-15

    Taking into account the importance of the continuous improvement of the performance and reliability of a NPP and practical measures to strengthen nuclear safety and security, it is to be noted that a good management for a nuclear power reactor involves a ''good dependability management'' of the activities, such as: Reliability, Availability, Maintainability (RAM) and maintenance support. In order to evaluate certain safety assessment criteria intended to be applied at the level of the nuclear reactor unit management, equipment dependability indicators and their impact over the availability and reactor safety have to be evaluated. Reactor equipment dependability indicators provide a quantitative indication of equipment RAM performances (Reliability, Availability and Maintenance). One of the important benefits of maintenance and failure data gathering is that it can be used as a support of probabilistic safety assessment (PSA). Also, a good dependability management implementation may be used to complement reactor level unit performance indicators in the field of safe operation, maintenance and improving operating parameters, as well as for Strengthening Safety and Improving Reliability of a NPP. This paper underlines the importance of nuclear safety and security as prerequisites for nuclear power. In addition, it demonstrates how different technical aspects, through implementation of a good dependability management, contribute to a strengthened safety and an improvement of availability of the NPP through dependability indicators determination and evaluation. (author)

  10. 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

  11. Operational Risk Management and Military Aviation Safety

    National Research Council Canada - National Science Library

    Ashley, Park

    1999-01-01

    .... The Army's Class A aviation mishap rate declined after it implemented risk management (RM) principles in 1987. This reduction caught the attention of Air Force leadership who have since stated that the application of operational risk management...

  12. Asset Management Guidebook for Safety and Operations

    Science.gov (United States)

    2012-09-01

    A primary product of this research was the Asset Management Guidebook that TxDOT division and district : personnel can use to help them define, develop, and implement asset management across all levels : particularly as it relates to establishing ...

  13. Investigation of Fire Safety Awareness and Management in Mall

    Directory of Open Access Journals (Sweden)

    Abdul Rahim N.

    2014-03-01

    Full Text Available In spite of having sufficient fire safety system installed in buildings, the incidence of fire hazard becomes the furthermost and supreme threat to health and safety, as well as property to any community. In order to make sure that the safety of the building and its users, the fundamental features depends on the fire precaution system and equipment which should be according to the standard requirements. Nevertheless, the awareness on fire safety could necessarily alleviate the damages or rate of fatality during the event of fire. This paper presents the results on the investigation of fire safety awareness and management, concentrating on shopping mall. The endeavour of this study is to explore the level of fire safety knowledge of the users in the mall, and to study the effectiveness level of fire safety management in a mall. From the study, public awareness is highly related to understanding human behaviour and their personal background. The respondents’ levels of awareness are rather low, which reflects on their poor action when facing emergency situation during fire. The most effective methods identified to improve the awareness and effectiveness of fire safety level is through involvement in related fire safety programmes, distribution of pamphlets or brochures on fire safety and appointing specific personnel for Emergency Response Team in the mall.

  14. OCRWM [Office of Civilian Radioactive Waste Management] Safety Plan

    International Nuclear Information System (INIS)

    1986-12-01

    The OCRWM Safety Plan sets forth management policies and general requirements for the safety of the public and of personnel associated with the Civilian Radioactive Waste Management Program (hereinafter called the ''Program''). It is applicable to all individuals and organizational elements of the Program, including all facilities and activities controlled by the Program pursuant to the Act, and to all phases of the Program. The plan defines the responsibilities assigned by the Director of the OCRWM to the various OCRWM line organizations, and to the contractors and the projects. It discusses the means by which safety policies and requirements will be communicated, and summarizes the applicable DOE Orders, and the procedures for reviewing, reporting, and evaluating safety problems. In addition, the OCRWM Safety Plan addresses DOE Orders applicable to occupational health and safety, worker protection, and public health and safety. OCRWM believes that it has an equally high level of commitment to both public safety and worker safety. The Plan also summarizes applicable NRC criteria and regulations that will be imposed through the formal licensing proceedings. While the Safety Plan sets forth OCRWM policy, it is not intended to be prescriptive in the details of implementation. Each OCRWM program element must develop and control its own set of detailed requirements for the protection of its workers and the public based on the principles set forth herein

  15. Safety managements of the linear IFMIF/EVEDA prototype accelerator

    International Nuclear Information System (INIS)

    Takahashi, Hiroki; Maebara, Sunao; Kojima, Toshiyuki; Narita, Takahiro; Tsutsumi, Kazuyoshi; Sakaki, Hironao; Suzuki, Hiromitsu; Sugimoto, Masayoshi

    2014-01-01

    Highlights: •Safety management is needed to secure the personnel safety from high dose rate. •The management of access to the accelerator vault is mainly performed by PPS. •The operation management is needed for safety during Injector and RFQ commissioning. •Pulse Duty Management system is newly developed for Injector commissioning for operation management. •PDM system is useful to reduce the radioactivation of equipment and the radiation exposure during and after beam operation. -- Abstract: On the Linear IFMIF/EVEDA Prototype Accelerator (LIPAc), the validation up to 9 MeV deuteron beam with 125 mA continuous wave is planned in Rokkasho, Aomori, Japan. Since the deuteron beam power exceeds 1 MW, safety issue related to γ-ray and neutron production is critical. To establish the safety management indispensable to reduce radiation exposure for personnel and activation of accelerator equipment, Personnel Protection System (PPS) of LIPAc control system, which works together with Radiation Monitoring System and Access Control System, was developed for LIPAc. The management of access to the accelerator vault by PPS and the beam duty management of PPS are presented in details

  16. Quality management, a directive approach to patient safety.

    Science.gov (United States)

    Ayuso-Murillo, Diego; de Andrés-Gimeno, Begoña; Noriega-Matanza, Concha; López-Suárez, Rafael Jesús; Herrera-Peco, Ivan

    Nowadays the implementation of effective quality management systems and external evaluation in healthcare is a necessity to ensure not only transparency in activities related to health but also access to health and patient safety. The key to correctly implementing a quality management system is support from the managers of health facilities, since it is managers who design and communicate to health professionals the strategies of action involved in quality management systems. This article focuses on nursing managers' approach to quality management through the implementation of cycles of continuous improvement, participation of improvement groups, monitoring systems and external evaluation quality models (EFQM, ISO). The implementation of a quality management system will enable preventable adverse effects to be minimized or eliminated, and promote patient safety and safe practice by health professionals. Copyright © 2017 Elsevier España, S.L.U. All rights reserved.

  17. 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

  18. 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.

  19. 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.

  20. 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

  1. Logging safety in forest management education

    Science.gov (United States)

    David Elton Fosbroke; John R. Myers

    1995-01-01

    Forest management degree programs prepare students for careers in forestry by teaching a combination of biological sciences (e.g., silvics and genetics) and business management (e.g., forest policy and timber valuation). During a 4-year degree program, students learn the impact of interest rates, equipment costs, and environmental policies on forest management and...

  2. Durability and safety of concrete structures in the nuclear context. The case of the containment vessel

    Energy Technology Data Exchange (ETDEWEB)

    Torrenti, J.M. [Universite Paris Est, LCPC (France); Nahas, G. [IRSN/DSR (France)

    2011-07-01

    The durability of structures, because of its economic and environmental implications, is one of the actual hot topics in civil engineering. In the field of nuclear energy, we are facing very challenging problems like: how could we prolong the service life of actual nuclear containments and how can we assure the durability of a radioactive storage on the very long term (several centuries)? These already difficult questions in a classical civil engineering view are even more complicated in the field of nuclear energy where the structures are massive and the safety of the installations has to be considered. For the containment of nuclear power plants, these stakes will be lit with some examples of research concerning the mechanical behaviour of concrete and concrete structures (at early age, in service on long scales of time and in the event of an accident), the durability of the concrete structures (leaching, swelling due to delayed ettringite formation - DEF -) and the couplings between mechanics and durability. Finally, the importance of probabilistic aspects and the inherent difficulties will be shown. (authors)

  3. Durability and safety of concrete structures in the nuclear context. The case of the containment vessel

    International Nuclear Information System (INIS)

    Torrenti, J.M.; Nahas, G.

    2011-01-01

    The durability of structures, because of its economic and environmental implications, is one of the actual hot topics in civil engineering. In the field of nuclear energy, we are facing very challenging problems like: how could we prolong the service life of actual nuclear containments and how can we assure the durability of a radioactive storage on the very long term (several centuries)? These already difficult questions in a classical civil engineering view are even more complicated in the field of nuclear energy where the structures are massive and the safety of the installations has to be considered. For the containment of nuclear power plants, these stakes will be lit with some examples of research concerning the mechanical behaviour of concrete and concrete structures (at early age, in service on long scales of time and in the event of an accident), the durability of the concrete structures (leaching, swelling due to delayed ettringite formation - DEF -) and the couplings between mechanics and durability. Finally, the importance of probabilistic aspects and the inherent difficulties will be shown. (authors)

  4. Materials technology and the energy problem : application to the reliability and safety of nuclear pressure vessels

    International Nuclear Information System (INIS)

    Garrett, G.G.

    1975-01-01

    In the U.S.A. over the past few months, widespread plant shutdowns because of cracking problems has produced considerable public pressure for a reappraisal of the reliability and safety of nuclear reactors. The awareness of such problems, and their solution, is particularly relevant to South Africa at this time. Some materials problems related to nuclear plant failure are examined in this paper. Since catastrophic failure (without prior warning from slow leakage) is in principle possible for light water (pressurised) reactors under operating conditions, it is essential to maintain rigorous manufacturing and quality control procedures, in conjunction with thorough and frequent examination by non-destructive testing methods. Although tests currently in progress in the U.S.A. on large-scale model reactors suggest that mathematical stress and failure analyses, for simple geometries at least, are sound, current in situ surveillance programmes aimed at categorizing the effects of irradiation are inadequate. In addition, the effects on materials properties and subsequent fracture resistance of the combined effects of irradiation and thermal shock (arising from the injection of emergency cooling water during a loss-of coolant accident) are unknown. The problem of stress corrosion cracking in stainless steel pipelines is considerable, and at present virtually impossible to predict. Much of the available laboratory data is inapplicable in that it cannot account for the complex interactions of stress state, temperature, material variations and segregation effects, and water chemistry, especially in conjunction with irradiation effects, that are experienced in an operating environment

  5. Application of project management methodology in design management of nuclear safety related structure

    International Nuclear Information System (INIS)

    Chen Mao

    2004-01-01

    This paper focuses on the application of project management methodology in the design management of Nuclear Safety Related Structure (NSRS), considering the design management features of its civil construction. Based on the experiences from the management of several projects, the project management triangle is proposed to be used in the management, to well treat the position of design interface in the project management. Some other management methods are also proposed

  6. Defining safety culture and the nexus between safety goals and safety culture. 1. An Investigation Study on Practical Points of Safety Management

    International Nuclear Information System (INIS)

    Hasegawa, Naoko; Takano, Kenichi; Hirose, Ayako

    2001-01-01

    In a report after the Chernobyl accident, the International Atomic Energy Agency indicated the definition and the importance of safety culture and the ideal organizational state where safety culture pervades. However, the report did not mention practical approaches to enhance safety culture. In Japan, although there had been investigations that clarified the consciousness of employees and the organizational climate in the nuclear power and railway industries, organizational factors that clarified the level of organization safety and practical methods that spread safety culture in an organization had not been studied. The Central Research Institute of the Electric Power Industry conducted surveys of organizational culture for the construction, chemical, and manufacturing industries. The aim of our study was to clarify the organizational factors that influence safety in an organization expressed in employee safety consciousness, commitment to safety activities, rate of accidents, etc. If these areas were clarified, the level of organization safety might be evaluated, and practical ways could be suggested to enhance the safety culture. Consequently, a series of investigations was conducted to clarify relationships among organizational climate, employee consciousness, safety management and activities, and rate of accidents. The questionnaire surveys were conducted in 1998-1999. The subjects were (a) managers of the safety management sections in the head offices of the construction, chemical, and manufacturing industries; (b) responsible persons in factories of the chemical and manufacturing industries; and (c) general workers in factories of the chemical and manufacturing industries. The number of collected data was (a) managers in the head office: 48 from the construction industry and 58 from the chemical and manufacturing industries, (b) responsible persons in factories: 567, and (c) general workers: from 29 factories. Items in the questionnaires were selected from

  7. Knowledge Management Methodologies for Improving Safety Culture

    International Nuclear Information System (INIS)

    Rusconi, C.

    2016-01-01

    Epistemic uncertainties could affect operator’s capability to prevent rare but potentially catastrophic accident sequences. Safety analysis methodologies are powerful but fragile tools if basic assumptions are not sound and exhaustive. In particular, expert judgments and technical data could be invalidated by organizational context change (e.g., maintenance planning, supply systems etc.) or by unexpected events. In 1986 accidents like Chernobyl, the explosion of Shuttle Challenger and, two years before, the toxic release at Bhopal chemical plant represented the point of no return with respect to the previous vision of safety and highlighted the undelayable need to change paradigm and face safety issues in complex systems not only from a technical point of view but to adopt a systemic vision able to include and integrate human and organizational aspects.

  8. FULCRUM - A dam safety management and alert system

    Energy Technology Data Exchange (ETDEWEB)

    Butt, Cameron; Greenaway, Graham [Knight Piesold Ltd., Vancouver, (Canada)

    2010-07-01

    Efficient management of instrumentation, monitoring and inspection data are the keys to safe performance and dam structure stability. This paper presented a data management system, FULCRUM, developed for dam safety management. FULCRUM is a secure web-based data management system which simplifies the process of data collection, processing and analysis of the information. The system was designed to organize and coordinate dam safety management requirements. Geotechnical instrumentation such as piezometers or inclinometers and operating data can be added to the database. Data from routine surveillance and engineering inspection can also be incorporated into the database. The system provides users with immediate access to historical and recent data. The integration of a GIS system allows for rapid assessment of the project site. Customisable alerting protocols can be set to identify and respond quickly to significant changes in operating conditions and potential impacts on dam safety.

  9. Interface management: Effective communication to improve process safety

    International Nuclear Information System (INIS)

    Kelly, Brian; Berger, Scott

    2006-01-01

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

  10. 24. MPA-seminar: safety and reliability of plant technology with special emphasis on integrity and life management. Vol. 2. Papers 28-63

    International Nuclear Information System (INIS)

    1999-01-01

    The second volume is dedicated to the safety and reliability of plant technology with special emphasis on the integrity and life management. The following topics are discussed: 1. Integrity of vessels, pipes and components. 2. Fracture mechanics. 3. Measures for the extension of service life, and 4. Online Monitoring. All 30 contributions are separately analyzed for this database. (orig.)

  11. Patient perceptions about illness self-management in ANCA-associated small vessel vasculitis.

    Science.gov (United States)

    Thorpe, C T; DeVellis, R F; Blalock, S J; Hogan, S L; Lewis, M A; DeVellis, B M

    2008-06-01

    To characterize patient perceptions, related to eight self-management behaviours relevant for adults with ANCA-associated small vessel vasculitis (ANCA-SVV), and to determine if these perceptions were associated with performance of each behaviour. Adults with ANCA-SVV (n = 202) completed a self-administered questionnaire that assessed eight self-management behaviours (adherence to recommendations for medication, health service use, diet, exercise, infection avoidance and symptom monitoring; prompt reporting of symptoms and side effects; and adjusting activities in response to symptoms), perceptions about these behaviours, socio-demographics, clinical factors and social desirability bias. Descriptive statistics were generated to characterize patients' perceptions about difficulty of, importance of, and specific barriers to performing each behaviour. Regression analyses explored whether these variables were associated with performing each behaviour, controlling for potential confounders. With few exceptions, higher perceived importance and lower perceived difficulty of each behaviour were associated with more frequent performance of the behaviour. For each behaviour, several specific barriers were frequently endorsed by patients and a number of these were associated with lower levels of self-management. This study reveals that patient perceptions about the illness and its treatment influence ANCA-SVV self-management. Perceived barriers to medication, health services, diet and exercise adherence were similar to those in other illnesses. This study also provides insight into barriers experienced by patients in performing behaviours (infection avoidance, symptom monitoring, reporting symptoms and side-effects and adjusting activities) not often previously studied. How the identification of these barriers can help inform future interventions for ANCA-SVV patients is to be discussed.

  12. Major accident prevention through applying safety knowledge management approach.

    Science.gov (United States)

    Kalatpour, Omid

    2016-01-01

    Many scattered resources of knowledge are available to use for chemical accident prevention purposes. The common approach to management process safety, including using databases and referring to the available knowledge has some drawbacks. The main goal of this article was to devise a new emerged knowledge base (KB) for the chemical accident prevention domain. The scattered sources of safety knowledge were identified and scanned. Then, the collected knowledge was formalized through a computerized program. The Protégé software was used to formalize and represent the stored safety knowledge. The domain knowledge retrieved as well as data and information. This optimized approach improved safety and health knowledge management (KM) process and resolved some typical problems in the KM process. Upgrading the traditional resources of safety databases into the KBs can improve the interaction between the users and knowledge repository.

  13. Bowtie Risk Management methodology and Modern Nuclear Safety Reports

    International Nuclear Information System (INIS)

    Ilizastigui Pérez, F.

    2016-01-01

    The Safety Report (SR) plays a crucial role within the nuclear licensing regime as the principal means for demonstrating the adequacy of safety analysis for a nuclear facility to ensure that it can be constructed, operated, maintained, shut down, and decommissioned safely and in compliance with applicable laws and regulations. It serves as the basis for granting authorizations for the commencement of the main stages of the facility’s life cycle as well as decision-making processes related to safety. Historically, the majority of nuclear safety reports have operated under rather prescriptive regimes, with emphasis placed on demonstrations of the robustness of the facility’s design (design safety) against prescriptive technical requirements set by the regulatory body, and less attention paid to demonstrating the adequacy and effectiveness of Operator’s management system for managing risks to daily operation.

  14. Joint convention on the safety of spent fuel management and on the safety of radioactive waste management

    International Nuclear Information System (INIS)

    1997-01-01

    The Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management was adopted on 5 September 1997 by a Diplomatic Conference convened by the IAEA from 1 to 5 September 1997. The Joint Convention was opened for signature at Vienna on 29 September 1997 during the forty-first session of the General Conference of the IAEA. This document reproduces the text of the Convention

  15. Joint convention on the safety of spent fuel management and on the safety of radioactive waste management

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-24

    The Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management was adopted on 5 September 1997 by a Diplomatic Conference convened by the IAEA from 1 to 5 September 1997. The Joint Convention was opened for signature at Vienna on 29 September 1997 during the forty-first session of the General Conference of the IAEA. This document reproduces the text of the Convention.

  16. Memory Management for Safety-Critical Java

    DEFF Research Database (Denmark)

    Schoeberl, Martin

    2011-01-01

    Safety-Critical Java (SCJ) is based on the Real-Time Specification for Java. To simplify the certification of Java programs, SCJ supports only a restricted scoped memory model. Individual threads share only immortal memory and the newly introduced mission memory. All other scoped memories...... implementation is evaluated on an embedded Java processor....

  17. Safety Psychology Applicating on Coal Mine Safety Management Based on Information System

    Science.gov (United States)

    Hou, Baoyue; Chen, Fei

    In recent years, with the increase of intensity of coal mining, a great number of major accidents happen frequently, the reason mostly due to human factors, but human's unsafely behavior are affected by insecurity mental control. In order to reduce accidents, and to improve safety management, with the help of application security psychology, we analyse the cause of insecurity psychological factors from human perception, from personality development, from motivation incentive, from reward and punishment mechanism, and from security aspects of mental training , and put forward countermeasures to promote coal mine safety production,and to provide information for coal mining to improve the level of safety management.

  18. 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)

  19. Radiation safety management system in a radioactive facility

    International Nuclear Information System (INIS)

    Amador, Zayda H.

    2008-01-01

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

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

    International Nuclear Information System (INIS)

    Syarip; Hauptmanns, U.

    2000-01-01

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

  1. Leadership style and patient safety: implications for nurse managers.

    Science.gov (United States)

    Merrill, Katreena Collette

    2015-06-01

    The purpose of this study was to explore the relationship between nurse manager (NM) leadership style and safety climate. Nursing leaders are needed who will change the environment and increase patient safety. Hospital NMs are positioned to impact day-to-day operations. Therefore, it is essential to inform nurse executives regarding the impact of leadership style on patient safety. A descriptive correlational study was conducted in 41 nursing departments across 9 hospitals. The hospital unit safety climate survey and multifactorial leadership questionnaire were completed by 466 staff nurses. Bivariate and regression analyses were conducted to determine how well leadership style predicted safety climate. Transformational leadership style was demonstrated as a positive contributor to safety climate, whereas laissez-faire leadership style was shown to negatively contribute to unit socialization and a culture of blame. Nursing leaders must concentrate on developing transformational leadership skills while also diminishing negative leadership styles.

  2. [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.

  3. Management of health, safety and environment in process industry

    DEFF Research Database (Denmark)

    Duijm, Nijs Jan; Fiévez, C.; Gerbec, M.

    2008-01-01

    The present status of industrial HSE management in a number of EU member states is reviewed, with a focus on the integration of health, safety and environment in single management systems. The review provides insight into the standards and paradigms adopted by industry, and it identifies trends...

  4. Design for sustainable development : environmental management and safety and health

    NARCIS (Netherlands)

    Zwetsloot, G.; Bos, J.

    1998-01-01

    This is a report on the EU's environmental management and audit scheme and its interaction with the management of safety and health. The focus is on the interactions at company and at policy level. To illustrate the relevance of the interactions at company level, the Annex includes five case studies

  5. Safety of radioactive waste management. Proceedings of an international conference

    International Nuclear Information System (INIS)

    2000-01-01

    The principal objective of the Conference was to enable members of the scientific community and representatives of facilities which produce radioactive waste, of bodies responsible for radioactive waste management, of nuclear regulatory bodies and of public interest groups, among others, to engage in an open dialogue. The open dialogue which took place may, by providing policy and decision makers with a basis for political action, prove to be an important step in the search for the international consensus so essential in the area of radioactive waste management. The relevant policies and activities of the IAEA, the European Commission, the OECD Nuclear Energy Agency and the World Health Organization were presented. The evolution, under the aegis of the IAEA, of a de facto international radiation and nuclear safety regime was noted. In the area of radioactive waste safety, this regime consists of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, the body of international waste safety standards established by the IAEA and other international organizations, and the IAEA's mechanisms for providing for the application of those standards. The topics covered by the Conference were: Current international co-operative efforts; Recommendations from the International Commission on Radiological Protection; Recommendations from the International Nuclear Safety Advisory Group; Conclusions and recommendations of the International Symposium on the Restoration of Environments with Radioactive Residues; Siting of radioactive waste management facilities; Participation of interested parties; Legislative and general radiation safety aspects; Removal of material from regulatory control (exclusion, exemption and clearance); Predisposal management (dilution, recycling, transmutation, etc.); Near surface disposal; Residues from the mining and processing of radioactive ores; Long term institutional control; Geological disposal

  6. Safety management and risk assessment in chemical laboratories.

    Science.gov (United States)

    Marendaz, Jean-Luc; Friedrich, Kirstin; Meyer, Thierry

    2011-01-01

    The present paper highlights a new safety management program, MICE (Management, Information, Control and Emergency), which has been specifically adapted for the academic environment. The process starts with an exhaustive hazard inventory supported by a platform assembling specific hazards encountered in laboratories and their subsequent classification. A proof of concept is given by a series of implementations in the domain of chemistry targeting workplace health protection. The methodology is expressed through three examples to illustrate how the MICE program can be used to address safety concerns regarding chemicals, strong magnetic fields and nanoparticles in research laboratories. A comprehensive chemical management program is also depicted.

  7. Implementing process safety management in gas processing operations

    International Nuclear Information System (INIS)

    Rodman, D.L.

    1992-01-01

    The Occupational Safety and Health Administration (OSHA) standard entitled Process Safety Management of Highly Hazardous Chemicals; Explosives and Blasting Agents was finalized February 24, 1992. The purpose of the standard is to prevent or minimize consequences of catastrophic releases of toxic, flammable, or explosive chemicals. OSHA believes that its rule will accomplish this goal by requiring a comprehensive management program that integrates technologies, procedures, and management practices. Gas Processors Association (GPA) member companies are significantly impacted by this major standard, the requirements of which are extensive and complex. The purpose of this paper is to review the requirements of the standard and to discuss the elements to consider in developing and implementing a viable long term Process Safety Management Program

  8. Self arrangements in occupational safety and health management

    International Nuclear Information System (INIS)

    Ismail Bahari

    2002-01-01

    The book is written with the awareness of safe work culture where success does not lie to compliance with the law only. Instead it is more of an excellent management based on the principle of self organization. Self arrangements in the management of occupational safety and health do not rest on the shoulders of the employer or the safety management and safety communities, but are committed together with the leadership of the employer. Self arrangements will be more meaningful and successful if those involved have knowledge about the philosophy and principles of why and how this management is done, and so the method can be practiced and eventually cultivated as a working system. (author)

  9. 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)

  10. Economic Techniques of Occupational Health and Safety Management

    Science.gov (United States)

    Sidorov, Aleksandr I.; Beregovaya, Irina B.; Khanzhina, Olga A.

    2016-10-01

    The article deals with the issues on economic techniques of occupational health and safety management. Authors’ definition of safety management is given. It is represented as a task-oriented process to identify, establish and maintain such a state of work environment in which there are no possible effects of hazardous and harmful factors, or their influence does not go beyond certain limits. It was noted that management techniques that are the part of the control mechanism, are divided into administrative, organizational and administrative, social and psychological and economic. The economic management techniques are proposed to be classified depending on the management subject, management object, in relation to an enterprise environment, depending on a control action. Technoeconomic study, feasibility study, planning, financial incentives, preferential crediting of enterprises, pricing, profit sharing and equity, preferential tax treatment for enterprises, economic regulations and standards setting have been distinguished as economic techniques.

  11. A case for safety leadership team training of hospital managers.

    Science.gov (United States)

    Singer, Sara J; Hayes, Jennifer; Cooper, Jeffrey B; Vogt, Jay W; Sales, Michael; Aristidou, Angela; Gray, Garry C; Kiang, Mathew V; Meyer, Gregg S

    2011-01-01

    Delivering safe patient care remains an elusive goal. Resolving problems in complex organizations like hospitals requires managers to work together. Safety leadership training that encourages managers to exercise learning-oriented, team-based leadership behaviors could promote systemic problem solving and enhance patient safety. Despite the need for such training, few programs teach multidisciplinary groups of managers about specific behaviors that can enhance their role as leadership teams in the realm of patient safety. The aims of this study were to describe a learning-oriented, team-based, safety leadership training program composed of reinforcing exercises and to provide evidence confirming the need for such training and demonstrating behavior change among management groups after training. Twelve groups of managers from an academic medical center based in the Northeast United States were randomly selected to participate in the program and exposed to its customized, experience-based, integrated, multimodal curriculum. We extracted data from transcripts of four training sessions over 15 months with groups of managers about the need for the training in these groups and change in participants' awareness, professional behaviors, and group activity. Training transcripts confirmed the need for safety leadership team training and provided evidence of the potential for training to increase targeted behaviors. The training increased awareness and use of leadership behaviors among many managers and led to new routines and coordinated effort among most management groups. Enhanced learning-oriented leadership often helped promote a learning orientation in managers' work areas. Team-based training that promotes specific learning-oriented leader behaviors can promote behavioral change among multidisciplinary groups of hospital managers.

  12. Ethical issues in patient safety: Implications for nursing management.

    Science.gov (United States)

    Kangasniemi, Mari; Vaismoradi, Mojtaba; Jasper, Melanie; Turunen, Hannele

    2013-12-01

    The purpose of this article is to discuss the ethical issues impacting the phenomenon of patient safety and to present implications for nursing management. Previous knowledge of this perspective is fragmented. In this discussion, the main drivers are identified and formulated in 'the ethical imperative' of patient safety. Underlying values and principles are considered, with the aim of increasing their visibility for nurse managers' decision-making. The contradictory nature of individual and utilitarian safety is identified as a challenge in nurse management practice, together with the context of shared responsibility and identification of future challenges. As a conclusion, nurse managers play a strategic role in patient safety. Their role is to incorporate ethical values of patient safety into decision-making at all levels in an organization, and also to encourage clinical nurses to consider values in the provision of care to patients. Patient safety that is sensitive to ethics provides sustainable practice where the humanity and dignity of all stakeholders are respected.

  13. Knowledge management and networking for enhancing nuclear safety

    International Nuclear Information System (INIS)

    Taniguchi, T.; Lederman, L.

    2004-01-01

    Striving for innovative solutions to enhance efficiency of programme delivery and a wider outreach of its nuclear safety activities, the International Atomic Energy Agency (IAEA) has developed an Integrated Safety Approach as a platform for linking its safety related statutory functions and its many associated activities. The approach recognizes the vital importance of effective management of the knowledge base and builds on the integration between the IAEA's safety standards and all aspects of the provision for their application, including peer reviews and technical meetings to share lessons learned. The IAEA is using knowledge management techniques to develop process flows, map safety knowledge and to promote knowledge sharing. The first practical application was the establishment of a knowledge base related to safety aspects of ageing and long-term operation of nuclear power plants. The IAEA is also promoting and facilitating the establishment of regional nuclear and radiation safety networks to preserve existing knowledge and expertise as well as to strengthen sharing and creation of new knowledge in these fields. Prominent examples are the Asian Nuclear Safety Network established in the frame of the IAEA's Programme on the Safety of Nuclear Installations in South East Asia, Pacific and Far East Countries, and the Ibero-American Radiation Safety Network in the frame of the Ibero-American Forum of Nuclear Regulators. Results to date are most encouraging and suggest that this pioneer work should be extended to other regions and eventually to a global nuclear safety network. Responsive to the need of Member States, the IAEA Secretariat has prepared and made available a large number of up-to-date training packages in nuclear, radiation, transport and waste safety, using IAEA safety standards as a basis. It is also providing instruction to trainers in Member States on the use of these modules. This ensures that the material is properly used and that the IAEA

  14. Study on Food Quality and Safety Management Based on Hotel Management

    Directory of Open Access Journals (Sweden)

    Shi Zengye

    2017-12-01

    Full Text Available In recent years, with the frequent occurrence of food safety problems, people have begun to pay attention to food safety, especially the food safety of hotels. This paper proposed a Hazard Analysis and Critical Control Point (HACCP management system to analyze food safety issues of hotels in order to improve the food quality and safety in hotel management. Through the practical application of the HACCP management system in the hotel catering industry, it was found that the amount of bacteria greatly reduced and the pass rate of tableware disinfection increased significantly in the hotel's food processing links, while customer satisfaction greatly improved. Therefore, the HACCP management system had great applicability in improving the food quality and safety of hotels.

  15. Safety issues in cultural heritage management and critical infrastructures management

    Science.gov (United States)

    Soldovieri, Francesco; Masini, Nicola; Alvarez de Buergo, Monica; Dumoulin, Jean

    2013-12-01

    ížková (2013) present two methods as peeling tests, also known as the 'Scotch tape' method, and surface water uptake measurements, using a digitized micro-tube for assessing material characteristics and consolidation effects on historic stone and mortar. Both methods are reviewed by pointing out both the advantages and the drawbacks. Solimene et al (2013) present a novel data processing technique based on the inverse electromagnetic scattering for small and weak target detection and localization. They start from the idea of applying a two-stage MUSIC algorithm. In the first stage strong scatterers are detected. Then, information concerning their number and location is employed to detect and localize the weak scatterers. The role of an adequate scattering model is emphasized to drastically improve detection performance in realistic scenarios. Kadioglu et al (2013) deal with the exploitation of ground penetrating radar, enhanced by advanced data processing based on microwave tomography, for the detection and the assessment of structural damage affecting foundation healthiness, of significant relevance for safety management in cultural heritage. An interesting case of the effectiveness of the joint procedure is shown by processing measurements collected during a survey at the Great Mosque of Ilyas Bey, one of the most important cultural heritage features from ancient Miletos-Iona in Soke Aydin, Turkey. Finally, Nordebo et al (2013) provide an interesting analysis of the optimal accuracy and resolution in electrical impedance tomography (EIT), based on the Cramer-Rao lower bound. This study is very important in the set up and analysis of the regularization strategies for the linearized problem at hand. References Battaglini R, Raco B and Scozzari A 2013 Effective monitoring of landfills: flux measurements and thermography enhance efficiency and reduce environmental impact J. Geophys. Eng. 10 064002 Cascini L, Peduto D, Reale D, Arena L, Ferlisi S, Verde S and Fornaro G 2013

  16. The Safety Prevention in the Theater Management and Operation

    Institute of Scientific and Technical Information of China (English)

    WU Sheng

    2015-01-01

    Take the operation and management experience as examples, the author discussed how to formulate a set of complete and effective equipment management system, operating rules, procedures and standards, as well as the safety prevention and control measures, according to the national or trade related laws and regulations and combining the operation and performance characteristics of theatre management, in order to ensure the safe operation of theatre and stage equipment.

  17. TWRS safety and technical integration risk management plan

    International Nuclear Information System (INIS)

    Fordham, R.A.

    1996-01-01

    The objectives of the Tank Waste Remediation System (TWRS) Safety and Technical Integration (STI) programmatic risk management program are to assess, analyze, and handle risks associated with TWRS STI responsibilities and to communicate information about the actions being taken and the results to enable decision making. The objective of this TWRS STI Risk Management Plan is to communicate a consistent approach to risk management that will be used by the organization

  18. Integrating environment health and safety management at Petro-Canada

    International Nuclear Information System (INIS)

    Raymond, G.

    1993-01-01

    Petro-Canada has developed a tool to integrate, measure, and improve its management systems of environment, health, and safety (EH ampersand S). This tool, called the Total Loss Management System, is described in the areas of general management issues, policies and procedures, evaluations, organization, stewardship, issue management, and performance measures. Petro-Canada's policies on occupational health and safety are consistent with its environmental policy, being structured in the same way. An integrated audit system is used to cover health, safety, industrial hygiene, reliability, environment, and risk management. EH ampersand S matters are integrated at the corporate level in a separate department. Regional divisions review EH ampersand S performance every month, incidents are discussed, and preventive measures are taken as necessary. Regional performances are combined every quarter for ultimate presentation to the Petro-Canada board. New or emerging issues that may affect divisions are assigned an issue sponsor, a member of divisional management who makes sure the issue receives the resources necessary to study and define its impact. Examples of issues include soil contamination, process hazard management, and benzene exposure limits. Performance measures flow from the corporate environment and occupational health and safety policies, and come in two types: those that measure activities to improve performance and those that measure the outcome of the activities

  19. Predisposal management of high level radioactive waste. Safety guide

    International Nuclear Information System (INIS)

    2005-01-01

    Radioactive waste is generated in the generation of electricity in nuclear power plants and in the use of radioactive material in industry, research and medicine. The importance of the safe management of radioactive waste for the protection of human health and the environment has long been recognized. The principles and requirements that govern the safety of the management of radioactive waste are presented in 'The Principles of Radioactive Waste Management', 'Legal and Governmental Infrastructure for Nuclear, Radiation, Radioactive Waste and Transport Safety' and 'Predisposal Management of Radioactive Waste, Including Decommissioning'. The objective of this Safety Guide is to provide regulatory bodies and the operators that generate and manage radioactive waste with recommendations on how to meet the principles and requirements established in Refs for the predisposal management of HLW. This Safety Guide applies to the predisposal management of HLW. For liquid HLW arising from the reprocessing of spent fuel the recommendations of this Safety Guide apply from when liquid waste from the first extraction process is collected for storage and subsequent processing. Recommendations and guidance on the storage of spent fuel, whether or not declared as waste, subsequent to its removal from the storage facility of a reactor are provided in Refs. For spent fuel declared as waste this Safety Guide applies to all activities subsequent to its removal from the storage facility of a reactor and prior to its disposal. Requirements pertaining to the transport of spent fuel, whether or not declared as waste, and of all forms of HLW are established. This Safety Guide provides recommendations on the safety aspects of managing HLW, including the planning, design, construction, commissioning, operation and decommissioning of equipment or facilities for the predisposal management of HLW. It addresses the following elements: (a) The characterization and processing (i.e. pretreatment

  20. 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.

  1. Institutional failure: are safety management systems the answer?

    Energy Technology Data Exchange (ETDEWEB)

    Waddington, J.G.; Lafortune, J.F. [International Safety Research, Ottawa, Ontario (Canada); Duffey, R.B. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)

    2009-07-01

    In spite of an overwhelming number of safety management programs, incidents and accidents that could seemingly, in hindsight, have been prevented, still occur. Institutional failure is seen as a major contributor in almost all cases. With the anticipated significant increase in the number of nuclear plants around the world, a drastic step in the way we manage safety is deemed essential to further reduce the currently already very low rate of accidents to levels that will not cause undue public concern and threaten the success of the nuclear 'renaissance'. To achieve this, many industries have already started implementing a Safety Management System (SMS) approach, aimed at harmonizing, rationalizing and integrating management processes, safety culture and operational risk assessment. This paper discusses the origins and the nature of SMS based in part on the experience of the aviation industry, and shows how SMS is poised to be the next generation in the way the nuclear industry manages safety. It also discusses the need for better direct measures of risk to demonstrate the success of SMS implementation. (author)

  2. Institutional failure: are safety management systems the answer?

    International Nuclear Information System (INIS)

    Waddington, J.G.; Lafortune, J.F.; Duffey, R.B.

    2009-01-01

    In spite of an overwhelming number of safety management programs, incidents and accidents that could seemingly, in hindsight, have been prevented, still occur. Institutional failure is seen as a major contributor in almost all cases. With the anticipated significant increase in the number of nuclear plants around the world, a drastic step in the way we manage safety is deemed essential to further reduce the currently already very low rate of accidents to levels that will not cause undue public concern and threaten the success of the nuclear 'renaissance'. To achieve this, many industries have already started implementing a Safety Management System (SMS) approach, aimed at harmonizing, rationalizing and integrating management processes, safety culture and operational risk assessment. This paper discusses the origins and the nature of SMS based in part on the experience of the aviation industry, and shows how SMS is poised to be the next generation in the way the nuclear industry manages safety. It also discusses the need for better direct measures of risk to demonstrate the success of SMS implementation. (author)

  3. 77 FR 34123 - Pipeline Safety: Public Meeting on Integrity Management of Gas Distribution Pipelines

    Science.gov (United States)

    2012-06-08

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No. PHMSA-2012-0100] Pipeline Safety: Public Meeting on Integrity Management of Gas Distribution Pipelines AGENCY: Office of Pipeline Safety, Pipeline and Hazardous Materials Safety Administration, DOT. ACTION...

  4. Safety behavior: Job demands, job resources, and perceived management commitment to safety.

    Science.gov (United States)

    Hansez, Isabelle; Chmiel, Nik

    2010-07-01

    The job demands-resources model posits that job demands and resources influence outcomes through job strain and work engagement processes. We test whether the model can be extended to effort-related "routine" safety violations and "situational" safety violations provoked by the organization. In addition we test more directly the involvement of job strain than previous studies which have used burnout measures. Structural equation modeling provided, for the first time, evidence of predicted relationships between job strain and "routine" violations and work engagement with "routine" and "situational" violations, thereby supporting the extension of the job demands-resources model to safety behaviors. In addition our results showed that a key safety-specific construct 'perceived management commitment to safety' added to the explanatory power of the job demands-resources model. A predicted path from job resources to perceived management commitment to safety was highly significant, supporting the view that job resources can influence safety behavior through both general motivational involvement in work (work engagement) and through safety-specific processes.

  5. Establishing management information system to solve the information management problem of nuclear safety related personnel's qualification management

    International Nuclear Information System (INIS)

    Sun Haipeng; Liu Zhijun; Li Tianshu

    2013-01-01

    With the rapid progress of nuclear energy and nuclear technology utilization, nuclear safety related personnel play an increasingly important role in ensuring nuclear safety. NNSA personnel qualification management information system conducts a multi-faceted, effective, real-time monitoring and information collection for nuclear safety staff practice unit management, knowledge management, license application, appraisal management or supervision, training management or supervision and certified staff management, and also is a milestone for NNSA to build the state department with 'five-feature' (learning-oriented, service-oriented, economical, innovative, clean-type). (authors)

  6. Limitations of Managing Safety by Numbers

    International Nuclear Information System (INIS)

    Engström, D.

    2016-01-01

    Work, especially in a complex, dynamic workplaces, often requires subtle, local judgment with regard to timing of subtasks, relevance, importance, prioritization, etc. Still, people in the nuclear industry seem to think safety results from error counts and people just following procedures. In the wake of failure it can be tempting to introduce new procedures and an even stricter “rule following culture”. None, or at least very little, attention is given to tacit knowledge and individual skills. I am aiming to highlight the inadequacy of putting too much trust in formalization and that reporting and trending of events will contribute to increased learning, an increased nuclear safety and an efficient operational experience. The ability to interpret a situation concrete depends on proven experience in similar situations, analogical thinking and tacit knowledge. I intend to problematize the introduction and use of so-called Corrective Action Program (CAP) and computerised reporting systems linked to CAP in the nuclear industry. Categorization and trending in computerised reporting systems is only based on the direct or triggering cause and not based on any analyzes, so the question we have to ask is what the trends are really telling us, if anything at all.

  7. Integrated Management System Incorporating Quality Management and Management of Environment, Health and Occupational Safety

    International Nuclear Information System (INIS)

    Manchev, B.; Nenkova, B.; Tomov, E.

    2012-01-01

    Risk Engineering Ltd is a Bulgarian private company founded in 1990 to provide engineering and consulting services applicable to each and every field of the energy sector. Since its establishment Risk Engineering Ltd develops, implement and apply a System for quality assurance, certified for the first time by BVQI (now Bureau Veritas Certification) in 1999 for conformity with the standard ISO 9001:1994. Later on, in connection with the revision of the standards of ISO 9000 series and introduction of the standard ISO 9001:2000 a Quality Management System in conformity with the standard ISO 9001:2000 was developed, introduced and certified. At present, Risk Engineering Ltd has got developed, documented, introduced and certified by Lloyd's Register Quality Assurance (LRQA) Quality Management System in compliance with ISO 9001:2008 on the process approach basis. On this basis and including the requirements of the ISO 14001:2004 (regarding the environment) and OHSAS 18001:2007 (regarding the health and occupational safety), Risk Engineering Ltd has developed and introduced Integrated Management System aim at achieving and demonstrating good results regarding protection of the environment, health and occupational safety. The processes under control by the Integrated Management System and applicable at the company are divided in two general types: A) Management processes: Strategic management and Management of the human resources. B) Processes describing the main activities: design/development process; project management; management of industrial projects and technical infrastructure project; construction, installation, repair and operation of power industry facilities; commercial activities and marketing; investigation of energy efficiency of industrial systems and certification of buildings regarding energy efficiency; consulting activity in the field of industry and energy as well as consultant in accordance with the Law of the Spatial Planning; management of the

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

    Science.gov (United States)

    Wang, Li

    2004-04-01

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

  9. Safety Culture for Regulator Competence Management in Embarking States

    International Nuclear Information System (INIS)

    Kandil, M.

    2016-01-01

    Full text: Safety is based on preventive actions where the ability of a regulatory body to fulfill its responsibilities depends largely on the competence of its staff. Building employees’ skills and knowledge is an investment for each employee and in the future of the organization. This building must be the competence of its staff integration with their safety culture, the essential to ensure competent human resources as required in the IAEA safety standards and other documents, in which the need and importance of ensuring regulatory competence is emphasized. As it involves both operational and management issues, safety culture is a sensitive topic for regulators whose role is to ensure compliance with safety requirements and not to intervene in management decisions. A number of embarking States are aspiring to develop nuclear power generation and this means that, among other things, regulatory bodies have to be established and rapidly expanded. This paper reports major considerations on the integration of safety culture with an adequate competence management system for regulators in embarking states. (author

  10. Protection of environment, health and safety using risk management

    Energy Technology Data Exchange (ETDEWEB)

    Abraham, G [Ghafari Associates, Inc. 17101 Michegan Avenue Dearborn, MI 48126-2736 (United States); Kummler, R H [Department of Chemical engineering Wayne Stae University Detroit, MI 48202 (United States); louvar, J [Research Services Basf Corporation Wyandotte, MI 48192 (United States)

    1997-12-31

    Section 304 of the 1990 clean air amendments (CAAA) directed the US occupational safety and health administration (OSFA) to develop a chemical process safety standard to protect workers on-site from accidents involving hazardous substances. OSHA issued 29 CFR 1910.119, process safety management of Highly hazardous chemicals (PSM) in 1992. Section 112 r of the CAAA further mandated that a standard be developed to protect the environment from accidental releases of hazardous substances. The US environmental protection agency (EPA) proposed such a standard in 1993 (58 Fr 54190) and revised their proposal in 1995). The final rule for risk management and accidental release prevention is more comprehensive and extensive than OSHA`s PSM standard. In this paper we will discuss the concepts of both programs, the classes of substances that would trigger a facility`s need for compliance and review the regulations for risk management.

  11. Protection of environment, health and safety using risk management

    International Nuclear Information System (INIS)

    Abraham, G.; Kummler, R.H.; louvar, J.

    1996-01-01

    Section 304 of the 1990 clean air amendments (CAAA) directed the US occupational safety and health administration (OSFA) to develop a chemical process safety standard to protect workers on-site from accidents involving hazardous substances. OSHA issued 29 CFR 1910.119, process safety management of Highly hazardous chemicals (PSM) in 1992. Section 112 r of the CAAA further mandated that a standard be developed to protect the environment from accidental releases of hazardous substances. The US environmental protection agency (EPA) proposed such a standard in 1993 (58 Fr 54190) and revised their proposal in 1995). The final rule for risk management and accidental release prevention is more comprehensive and extensive than OSHA's PSM standard. In this paper we will discuss the concepts of both programs, the classes of substances that would trigger a facility's need for compliance and review the regulations for risk management

  12. Management and organization in nuclear power plant safety

    International Nuclear Information System (INIS)

    Osborn, R.N.

    1983-08-01

    In the immediate aftermath of the Three Mile Island accident, the Nuclear Regulatory Commission-sponsored investigations of the relation between human issues and safety tended to focus on individual and, at most, group level phenomena. This initial bottom up view of organizational safety has continued to be investigated by the Nuclear Regulatory Commission, as evidence by the four previous papers. Recently, however, work has begun which adopts a top down management/organization approach to nuclear power plant safety. This paper reports on the research, to date, on this focus

  13. Quality procedure management for improved nuclear safety

    International Nuclear Information System (INIS)

    Forzano, P.; Castagna, P.

    1995-01-01

    Emergency Operating Procedures and Accident Management Procedures are the next step in the computerization of NPP control rooms. Different improvements are presently conceivable for this operator aid tool, and research activities are in development. Undergoing activities regard especially formal aspects of knowledge representation, Human-Machine interface and procedure life cycle management. These aspects have been investigated deeply by Ansaldo, and partially incorporated in the DIAM prototype. Nuclear Power Plant Procedures can be seen from essentially two viewpoints: the process and the information management. From the first point of view, it is important to supply the knowledge apt to solve problems connected with the control of the process, from the second one the focus of attention is on the knowledge representation, its structure, elicitation and maintenance, and formal quality assurance. These two aspects of procedure representation can be considered and solved separately. In particular, methodological, formal and management issues require long and tedious activities, that in most cases constitute a great barrier for procedures development and upgrade. To solve these problems, Ansaldo is developing DIAM, a wide integrated tool for procedure management to support in procedure writing, updating, usage, and documentation. One of the most challenging features of DIAM is AUTO-LAY, a CASE sub-tool that, in a complete automatical way, structures parts or complete flow diagram. This is the feature that is partial present in some other CASE products, that, anyway, do not allow complex graph handling and isomorphism between video and paper representation. AUTO-LAY has the unique prerogative to draw graphs of any complexity to section them in pages, and to automatically compose a document. This has been recognized in the literature as the most important a second-generation CASE improvement. (Author) 9 Figs., 5 Refs

  14. Stringent cost management and preservation of safety culture, a contradiction?

    International Nuclear Information System (INIS)

    Petersen, Klaus; Pamme, H.

    2002-01-01

    Full text: Competition in the deregulated electricity market does not leave nuclear power plants unaffected. Hence the question is to answer, whether the safety is going to suffer under the cost pressure on the market. Therefore the target of NPP operator's cost management is to run plants at maximum availability and with optimized cost structures that lead to minimized specific generating costs. The c osts of safety , with their fixed-cost character, are elements of this cost structure. The process of economic optimization of the cost structure does not permit cost minimization on its own sake in the area of operation cost and fuel cost (front and back end). The basis of economical assessment rather must be the minimization of potential risks which could entail losses of availability. However, many investments like plant modifications or preventive maintenance efforts made in order to avoid losses of availability to a large extent also imply at least a preservation or even higher levels of safety. Thus, economic efficiency and safety are closely correlated. Public opinion is very sensible as soon as the high level of plant safety seems to be touched by economic pressure. But realizing that German NPP are endowed with mature design and safety features, improvements of safety standards can only marginally be increased by further technical optimizations. Therefore plant management, man-machine-interface and the individual behaviour of the employees are targets for improvement of nuclear safety and economic efficiency by increasing the efficiency of processes. An even more efficient use of scarce funds and a tolerable political environment should allow the safety level of NPP to be upheld, and safety culture could be maintained and even be improved. (author)

  15. 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.

  16. Management of construction safety at RR site

    International Nuclear Information System (INIS)

    Pathak, B.C.; Khatsuriya, J.R.

    2016-01-01

    Construction industries are one of the most hazardous industries and hence, promotion of safety remains one of the greatest challenges facing construction industry today. According to ILO estimates: Each year at least 60,000 fatal accidents occur on construction sites around the world or one fatal accident every ten minutes. One in six fatal accidents at work occurs on a construction site. In industrialized countries, as many as 25-40 per cent of work related deaths occur on construction sites, even though the sector employs only 6-10 per cent of the workforce. The number of fatalities occurring from construction work in India is also quite disturbing. Though, the fall of person from height and through openings were the major causes for fatal /serious accidents, the risk of fatal accident involving material handling equipment, either during handling or its maintenance is also significantly high due to use of large number of material handling equipments during construction work. (author)

  17. FLIGHT SAFETY MANAGEMENT PROBLEMS AND EVALUATION OF FLIGHT SAFETY LEVEL OF AN AVIATION ENTERPRISE

    OpenAIRE

    B. V. Zubkov; H. E. Fourar

    2017-01-01

    This article is devoted to studying the problem of safety management system (SMS) and evaluating safety level of an aviation enterprise.This article discusses the problems of SMS, presented at the 41st meeting of the Russian Aviation Production Commanders Club in June 2014 in St. Petersburg in connection with the verification of the status of the CA of the Russian Federation by the International Civil Aviation Organization (ICAO) in the same year, a set of urgent measures to eliminate the def...

  18. Implementation of safety management systems in Hong Kong construction industry - A safety practitioner's perspective.

    Science.gov (United States)

    Yiu, Nicole S N; Sze, N N; Chan, Daniel W M

    2018-02-01

    In the 1980s, the safety management system (SMS) was introduced in the construction industry to mitigate against workplaces hazards, reduce the risk of injuries, and minimize property damage. Also, the Factories and Industrial Undertakings (Safety Management) Regulation was introduced on 24 November 1999 in Hong Kong to empower the mandatory implementation of a SMS in certain industries including building construction. Therefore, it is essential to evaluate the effectiveness of the SMS in improving construction safety and identify the factors that influence its implementation in Hong Kong. A review of the current state-of-the-practice helped to establish the critical success factors (CSFs), benefits, and difficulties of implementing the SMS in the construction industry, while structured interviews were used to establish the key factors of the SMS implementation. Results of the state-of-the-practice review and structured interviews indicated that visible senior commitment, in terms of manpower and cost allocation, and competency of safety manager as key drivers for the SMS implementation. More so, reduced accident rates and accident costs, improved organization framework, and increased safety audit ratings were identified as core benefits of implementing the SMS. Meanwhile, factors such as insufficient resources, tight working schedule, and high labor turnover rate were the key challenges to the effective SMS implementation in Hong Kong. The findings of the study were consistent and indicative of the future development of safety management practice and the sustainable safety improvement of Hong Kong construction industry in the long run. Copyright © 2018 National Safety Council and Elsevier Ltd. All rights reserved.

  19. Experimental and Numerical Study of Effect of Thermal Management on Storage Capacity of the Adsorbed Natural Gas Vessel

    KAUST Repository

    Ybyraiymkul, Doskhan

    2017-07-08

    One of the main challenges in the adsorbed natural gas (ANG) storage system is the thermal effect of adsorption, which significantly lowers storage capacity. These challenges can be solved by efficient thermal management system. In this paper, influence of thermal management on storage capacity of the ANG vessel was studied experimentally and numerically. 3D numerical model was considered in order to understand heat transfer phenomena and analyze influence of thermal control comprehensively. In addition, a detailed 2D axisymmetric unit cell model of adsorbent layer with heat exchanger was developed, followed by optimization of heat exchanging device design to minimize volume occupied by fins and tubes. Heat transfer, mass transfer and adsorption kinetics, which occur in ANG vessel during charging process, are accounted for in models. Nelder-Mead method is implemented to obtain the geometrical parameters, which lead to the optimal characteristics of heat exchange. A new optimized configuration of ANG vessel was developed with compact heat exchanger. Results show that storage capacity of the ANG vessel increased significantly due to lowering of heat exchanger volume for 3 times from 13.5% to 4.3% and effective temperature control.

  20. A proactive method for safety management in nuclear facilities

    International Nuclear Information System (INIS)

    Grecco, Claudio Henrique dos Santos; Carvalho, Paulo Victor Rodrigues de; Santos, Isaac Antonio Luquetti dos

    2014-01-01

    Due to the modern approach to address the safety of nuclear facilities which highlights that these organizations must be able to assess and proactively manage their activities becomes increasingly important the need for instruments to evaluate working conditions. In this context, this work presents a proactive method of managing organizational safety, which has three innovative features: 1) the use of predictive indicators that provide current information on the performance of activities, allowing preventive actions and not just reactive in safety management, different from safety indicators traditionally used (reactive indicators) that are obtained after the occurrence of undesired events; 2) the adoption of resilience engineering approach in the development of indicators - indicators are based on six principles of resilience engineering: top management commitment, learning, flexibility, awareness, culture of justice and preparation for the problems; 3) the adoption of the concepts and properties of fuzzy set theory to deal with subjectivity and consistency of human trials in the evaluation of the indicators. The fuzzy theory is used primarily to map qualitative models of decision-making, and inaccurate representation methods. The results of this study aim an improvement in performance and safety in organizations. The method was applied in a radiopharmaceutical shipping sector of a nuclear facility. The results showed that the method is a good monitoring tool objectively and proactively of the working conditions of an organizational domain

  1. 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

  2. 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

  3. 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

  4. 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.

  5. Intranet-based safety documentation in management of major hazards and occupational health and safety.

    Science.gov (United States)

    Leino, Antti

    2002-01-01

    In the European Union, Council Directive 96/82/EC requires operators producing, using, or handling significant amounts of dangerous substances to improve their safety management systems in order to better manage the major accident potentials deriving from human error. A new safety management system for the Viikinmäki wastewater treatment plant in Helsinki, Finland, was implemented in this study. The system was designed to comply with both the new safety liabilities and the requirements of OHSAS 18001 (British Standards Institute, 1999). During the implementation phase experiences were gathered from the development processes in this small organisation. The complete documentation was placed in the intranet of the plant. Hyperlinks between documents were created to ensure convenience of use. Documentation was made accessible for all workers from every workstation.

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

    International Nuclear Information System (INIS)

    Lim, Nam-Jin; Park, Chan-Gook; Nam, Ji-Hee; Kim, Kwan-Hyun; Kwon, Hyuk-il; Lee, Young-Gun Lee

    2006-01-01

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

  7. Improving safety in small enterprises through an integrated safety management intervention.

    Science.gov (United States)

    Kines, Pete; Andersen, Dorte; Andersen, Lars Peter; Nielsen, Kent; Pedersen, Louise

    2013-02-01

    This study tests the applicability of a participatory behavior-based injury prevention approach integrated with safety culture initiatives. Sixteen small metal industry enterprises (10-19 employees) are randomly assigned to receive the intervention or not. Safety coaching of owners/managers result in the identification of 48 safety tasks, 85% of which are solved at follow-up. Owner/manager led constructive dialogue meetings with workers result in the prioritization of 29 tasks, 79% of which are accomplished at follow-up. Intervention enterprises have significant increases on six of eight safety-perception-survey factors, while comparisons increase on only one factor. Both intervention and comparison enterprises demonstrate significant increases in their safety observation scores. Interview data validate and supplement these results, providing some evidence for behavior change and the initiation of safety culture change. Given that over 95% of enterprises in most countries have less than 20 employees, there is great potential for adapting this integrated approach to other industries. Copyright © 2012 National Safety Council and Elsevier Ltd. All rights reserved.

  8. Safety of radioactive waste management in France

    International Nuclear Information System (INIS)

    Raimbault, P.

    2002-01-01

    Radioactive waste produced in France vary considerably by their activity level, their half lives, their volume or even their nature. In order to manage them safely, the treatment and final disposal solution must be adapted to the type of waste considered by setting up specific waste management channels. A strong principle in France is that it is the responsibility of the nuclear operators as waste producers to dispose of their waste or have them disposed of in a suitable manner. The competent authorities regulate and control the radioactive waste management activities. At present, only short-lived low and intermediate level waste have a definitive solution, the surface repository, where adequate waste packages are disposed of in concrete structures. Other types of radioactive waste are in interim storage facilities at the production sites. For very low level waste coming mainly from dismantling of nuclear facilities a dedicated repository is planned to be built in the coming years. Dedicated repositories are also planned for radiferous, tritiated and graphite waste. As for high level waste and long-lived waste coming mainly from reprocessing of spent nuclear fuel the disposal options are being sought along the lines specified by law 91-1381 concerning research on radioactive waste management, passed on December 30, 1991: research of solutions to partition and transmute long-lived radionuclides in the waste; studies of retrievable and non retrievable disposal in deep geological layers with the help of underground laboratories; studies of processes for conditioning and long term surface storage of these waste. In 2006, the French Parliament will assess the results of the research conducted by ANDRA relative to deep geological disposal as well as the work conducted by CEA in the two other areas of research and, if this research is conclusive, pass a law defining the final disposal option. (author)

  9. Safety Culture Perspective. Managing the pre Managing the pre-operational phases of new NPPs and creating the safety culture

    International Nuclear Information System (INIS)

    Cowan, Pamela B.; Oh, Chaewoon; Dahlgren Persson, Kerstin; Carnino, Annick

    2008-01-01

    Nuclear safety is a key for the revival of nuclear energy future programmes. Lots of competent people will be needed worldwide for ensuring the safety of the installations both existing ones and future ones. Their expertise should range from design to operation, from regulatory role to operators, from fuel fabrication to waste disposal. The challenge in front of us will be to prepare for the right recruitment, the development of the needed expertise in order to face the demand in developed countries, in countries with economies in transition and in developing countries. Time allocated for the panel does not allow for covering all aspects but the panelists will cover some of the important aspects of the challenge in terms of needs, of new competencies, of learning from operation and licensing requirements including for new designs. The key objectives of the panel are: 1- Maintaining safe operation, learning from experience, licensing including aging management and re-licensing with safety improvements for existing installations: - Presentation by Junko Ogawa of the experience and lessons learned from the earthquake on Kashiwasaki Kariwa NPP: effects in terms of manpower involved in the investigation, effects on regulations and licensing, expertise used. - Presentation by Pamela Cowan of her experience in preparing licensing actions, regulatory compliance and interface with the Regulator for both operating plants and modern requirements for constructing new ones. 2 - Special training needed for the human aspect of safety: what are the challenges in areas of safety culture and management of safety: - Presentation by Chae Woon Oh of the Korean safety culture features developed nationally, at the regulator and at the operating organizations and their integration within the safety training programmes. - Presentation by Kerstin Dahlgren Person of the needs in terms of safety culture and safety management, in terms of expertise, practitioners and assessors. 3 - How to

  10. Safety Culture Perspective. Managing the pre Managing the pre-operational phases of new NPPs and creating the safety culture

    Energy Technology Data Exchange (ETDEWEB)

    Cowan, Pamela B. [Exelon Generation, 200 Exelon Way, 19348 Kennett Square, PA 19348 (United States); Oh, Chaewoon [Korea Institute of Nuclear Safety, 19 Gusung-Dong, Yuseong-Ku, 305-338 Daejeon (Korea, Republic of); Dahlgren Persson, Kerstin [International Atomic Energy Agency, Wagramer Strasse 5, PO BOX 100 A-1400 Vienna (Austria); Carnino, Annick [IAEA, Division of Nuclear Installation Safety, Wagramer Strasse 5, PO BOX 100 A-1400 Vienna (Austria)

    2008-07-01

    Nuclear safety is a key for the revival of nuclear energy future programmes. Lots of competent people will be needed worldwide for ensuring the safety of the installations both existing ones and future ones. Their expertise should range from design to operation, from regulatory role to operators, from fuel fabrication to waste disposal. The challenge in front of us will be to prepare for the right recruitment, the development of the needed expertise in order to face the demand in developed countries, in countries with economies in transition and in developing countries. Time allocated for the panel does not allow for covering all aspects but the panelists will cover some of the important aspects of the challenge in terms of needs, of new competencies, of learning from operation and licensing requirements including for new designs. The key objectives of the panel are: 1- Maintaining safe operation, learning from experience, licensing including aging management and re-licensing with safety improvements for existing installations: - Presentation by Junko Ogawa of the experience and lessons learned from the earthquake on Kashiwasaki Kariwa NPP: effects in terms of manpower involved in the investigation, effects on regulations and licensing, expertise used. - Presentation by Pamela Cowan of her experience in preparing licensing actions, regulatory compliance and interface with the Regulator for both operating plants and modern requirements for constructing new ones. 2 - Special training needed for the human aspect of safety: what are the challenges in areas of safety culture and management of safety: - Presentation by Chae Woon Oh of the Korean safety culture features developed nationally, at the regulator and at the operating organizations and their integration within the safety training programmes. - Presentation by Kerstin Dahlgren Person of the needs in terms of safety culture and safety management, in terms of expertise, practitioners and assessors. 3 - How to

  11. Predisposal management of radioactive waste. General safety requirements. Pt. 5

    International Nuclear Information System (INIS)

    2009-01-01

    The objective of this Safety Requirements publication is to establish, the requirements that must be satisfied in the predisposal management of radioactive waste. This publication sets out the objectives, criteria and requirements for the protection of human health and the environment that apply to the siting, design, construction, commissioning, operation and shutdown of facilities for the predisposal management of radioactive waste, and the requirements that must be met to ensure the safety of such facilities and activities. This Safety Requirements publication applies to the predisposal management of radioactive waste of all types and covers all the steps in its management from its generation up to its disposal, including its processing (pretreatment, treatment and conditioning), storage and transport. Such waste may arise from the commissioning, operation and decommissioning of nuclear facilities; the use of radionuclides in medicine, industry, agriculture, research and education; the processing of materials that contain naturally occurring radionuclides; and the remediation of contaminated areas. The introduction of the document (Section 1) informs about its objective, scope and structure. The protection of human health and the environment is considered in Section 2 of this publication. Section 3 establishes requirements for the responsibilities associated with the predisposal management of radioactive waste. Requirements for the principal approaches to and the elements of the predisposal management of radioactive waste are established in Section 4. Section 5 establishes requirements for the safe development and operation of predisposal radioactive waste management facilities and safe conduct of activities. The Annex presents a discussion of the consistency of the safety requirements established in this publication with the fundamental safety principles

  12. Workplace road safety risk management: An investigation into Australian practices.

    Science.gov (United States)

    Warmerdam, Amanda; Newnam, Sharon; Sheppard, Dianne; Griffin, Mark; Stevenson, Mark

    2017-01-01

    In Australia, more than 30% of the traffic volume can be attributed to work-related vehicles. Although work-related driver safety has been given increasing attention in the scientific literature, it is uncertain how well this knowledge has been translated into practice in industry. It is also unclear how current practice in industry can inform scientific knowledge. The aim of the research was to use a benchmarking tool developed by the National Road Safety Partnership Program to assess industry maturity in relation to risk management practices. A total of 83 managers from a range of small, medium and large organisations were recruited through the Victorian Work Authority. Semi-structured interviews aimed at eliciting information on current organisational practices, as well as policy and procedures around work-related driving were conducted and the data mapped onto the benchmarking tool. Overall, the results demonstrated varying levels of maturity of risk management practices across organisations, highlighting the need to build accountability within organisations, improve communication practices, improve journey management, reduce vehicle-related risk, improve driver competency through an effective workplace road safety management program and review organisational incident and infringement management. The findings of the study have important implications for industry and highlight the need to review current risk management practices. Copyright © 2016 Elsevier Ltd. All rights reserved.

  13. Safety in the management of radioactive substances

    International Nuclear Information System (INIS)

    Balter, Henia; Rey, Ana; Leon, Alba; Jelen, Miguel

    1994-01-01

    A brief explanation of radiation protection,external irradiation,internal contamination,risk factors, active laboratory design,localization,ventilation,working surfaces,area distribution,classification of active laboratory.Radiopharmacy laboratory,shielding, area monitoring,personal dosimetry,rules for management of open sources,maximum admitted limits for radionuclides currently used in radiopharmacy.Decontamination of active areas and materials,surfaces,equipment s.Decontamination of hands.Waste disposal.Radioactive materials transportation.Reception of radioactive materials.Bibliography

  14. Regulatory changes in the management of the structural integrity of the vessel

    International Nuclear Information System (INIS)

    Colomer, M.; Jardi, X.; Cueto-Felgueroso, C.; Marcelles, I.

    2012-01-01

    In this paper we present the changes that have recently occurred in both the normative and ASME code, affecting the monitoring programs of the vessel. Also, the changes will be discussed in the future are envisaged in codes and regulations.

  15. First insights into the functional role of vasicentric tracheids and parenchyma in eucalyptus species with solitary vessels: do they contribute to xylem efficiency or safety?

    Science.gov (United States)

    Barotto, Antonio José; Fernandez, María Elena; Gyenge, Javier; Meyra, Ariel; Martinez-Meier, Alejandro; Monteoliva, Silvia

    2016-12-01

    The relationship between hydraulic specific conductivity (k s ) and vulnerability to cavitation (VC) with size and number of vessels has been studied in many angiosperms. However, few of the studies link other cell types (vasicentric tracheids (VT), fibre-tracheids, parenchyma) with these hydraulic functions. Eucalyptus is one of the most important genera in forestry worldwide. It exhibits a complex wood anatomy, with solitary vessels surrounded by VT and parenchyma, which could serve as a good model to investigate the functional role of the different cell types in xylem functioning. Wood anatomy (several traits of vessels, VT, fibres and parenchyma) in conjunction with maximum k s and VC was studied in adult trees of commercial species with medium-to-high wood density (Eucalyptus globulus Labill., Eucalyptus viminalis Labill. and Eucalyptus camaldulensis Dehnh.). Traits of cells accompanying vessels presented correlations with functional variables suggesting that they contribute to both increasing connectivity between adjacent vessels-and, therefore, to xylem conduction efficiency-and decreasing the probability of embolism propagation into the tissue, i.e., xylem safety. All three species presented moderate-to-high resistance to cavitation (mean P 50 values = -2.4 to -4.2 MPa) with no general trade-off between efficiency and safety at the interspecific level. The results in these species do not support some well-established hypotheses of the functional meaning of wood anatomy. © The Author 2016. Published by Oxford University Press. All rights reserved. For Permissions, please e-mail: journals.permissions@oup.com.

  16. Therapeutic risk management of the suicidal patient: safety planning.

    Science.gov (United States)

    Matarazzo, Bridget B; Homaifar, Beeta Y; Wortzel, Hal S

    2014-05-01

    This column is the fourth in a series describing a model for therapeutic risk management of the suicidal patient. Previous columns presented an overview of the therapeutic risk management model, provided recommendations for how to augment risk assessment using structured assessments, and discussed the importance of risk stratification in terms of both severity and temporality. This final column in the series discusses the safety planning intervention as a critical component of therapeutic risk management of suicide risk. We first present concerns related to the relatively common practice of using no-suicide contracts to manage risk. We then present the safety planning intervention as an alternative approach and provide recommendations for how to use this innovative strategy to therapeutically mitigate risk in the suicidal patient.

  17. Automatic road traffic safety management system in urban areas

    Directory of Open Access Journals (Sweden)

    Oskarbski Jacek

    2017-01-01

    Full Text Available Traffic incidents and accidents contribute to decreasing levels of transport system reliability and safety. Traffic management and emergency systems on the road, using, among others, automatic detection, video surveillance, communication technologies and institutional solutions improve the organization of the work of various departments involved in traffic and safety management. Automation of incident management helps to reduce the time of a rescue operation as well as of the normalization of the flow of traffic after completion of a rescue operation, which also affects the reduction of the risk of secondary accidents and contributes to reducing their severity. The paper presents the possibility of including city traffic departments in the process of incident management. The results of research on the automatic incident detection in cities are also presented.

  18. FLIGHT SAFETY MANAGEMENT PROBLEMS AND EVALUATION OF FLIGHT SAFETY LEVEL OF AN AVIATION ENTERPRISE

    Directory of Open Access Journals (Sweden)

    B. V. Zubkov

    2017-01-01

    Full Text Available This article is devoted to studying the problem of safety management system (SMS and evaluating safety level of an aviation enterprise.This article discusses the problems of SMS, presented at the 41st meeting of the Russian Aviation Production Commanders Club in June 2014 in St. Petersburg in connection with the verification of the status of the CA of the Russian Federation by the International Civil Aviation Organization (ICAO in the same year, a set of urgent measures to eliminate the deficiencies identified in the current safety management system by participants of this meeting were proposed.In addition, the problems of evaluating flight safety level based on operation data of an aviation enterprise were analyzed. This analysis made it possible to take into account the problems listed in this article as a tool for a comprehensive study of SMS parameters and allows to analyze the quantitative indicators of the flights safety level.The concepts of Acceptable Safety Level (ASL indicators are interpreted differently depending on the available/applicable methods of their evaluation and how to implement them in SMS. However, the indicators for assessing ASL under operational condition at the aviation enterprise should become universal. Currently, defined safety levels and safety indicators are not yet established functionally and often with distorted underrepresented models describing their contextual contents, as well as ways of integrating them into SMS aviation enterprise.The results obtained can be used for better implementation of SMS and solving problems determining the aviation enterprise technical level of flight safety.

  19. 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.

  20. Linking better shiftwork arrangements with safety and health management systems

    OpenAIRE

    Kogi, Kazutaka

    2004-01-01

    OBJECTIVE: Various support measures useful for promoting joint change approaches to the improvement of both shiftworking arrangements and safety and health management systems were reviewed. A particular focus was placed on enterprise-level risk reduction measures linking working hours and management systems. METHODS: Voluntary industry-based guidelines on night and shift work for department stores and the chemical, automobile and electrical equipment industries were examined. Survey results t...

  1. The impact of 18F-FDG PET on the management of patients with suspected large vessel vasculitis

    International Nuclear Information System (INIS)

    Fuchs, Martin; Rasch, Helmut; Berg, Scott; Ng, Quinn K.T.; Mueller-Brand, Jan; Walter, Martin A.; Briel, Matthias; Daikeler, Thomas; Tyndall, Alan; Walker, Ulrich A.; Raatz, Heike; Jayne, David; Koetter, Ina; Blockmans, Daniel; Cid, Maria C.; Prieto-Gonzalez, Sergio; Lamprecht, Peter; Salvarani, Carlo; Karageorgaki, Zaharenia; Watts, Richard; Luqmani, Raashid

    2012-01-01

    We aimed to assess the impact of 18 F-fluorodeoxyglucose (FDG) positron emission tomography (PET) on the management of patients with suspected large vessel vasculitis. An international expert panel determined diagnoses and clinical management in patients with suspected large vessel vasculitis, with and without the results of 18 F-FDG PET, respectively. The accuracy of the clinical diagnosis and the resulting clinical management with and without the 18 F-FDG PET results were compared using logistic regression models. The analysis included 30 patients referred to a tertiary care centre with large vessel vasculitis and 31 controls. 18 F-FDG PET had an overall sensitivity of 73.3% [95% confidence interval (CI) 54.1-87.7%], a specificity of 83.9% (95% CI 66.3-94.5%), a positive predictive value of 81.5% (95% CI 61.9-93.7%) and a negative predictive value of 76.5% (95% CI 58.8-89.3%). The diagnostic accuracy of 18 F-FDG PET was higher in patients not receiving immunosuppressive drugs (93.3 vs 64.5%, p = 0.006). Taken in context with other available diagnostic modalities, the addition of 18 F-FDG PET increased the clinical diagnostic accuracy from 54.1 to 70.5% (p = 0.04). The addition of 18 F-FDG PET increased the number of indicated biopsies from 22 of 61 patients (36.1%) to 25 of 61 patients (41.0%) and changed the treatment recommendation in 8 of 30 patients (26.7%) not receiving immunosuppressive medication and in 7 of 31 patients (22.6%) receiving immunosuppressive medication. 18 F-FDG PET is a sensitive and specific imaging tool for large vessel vasculitis, especially when performed in patients not receiving immunosuppressive drugs. It increases the overall diagnostic accuracy and has an impact on the clinical management in a significant proportion of patients. (orig.)

  2. Biomedical waste management: Incineration vs. environmental safety

    Directory of Open Access Journals (Sweden)

    Gautam V

    2010-01-01

    Full Text Available Public concerns about incinerator emissions, as well as the creation of federal regulations for medical waste incinerators, are causing many health care facilities to rethink their choices in medical waste treatment. As stated by Health Care Without Harm, non-incineration treatment technologies are a growing and developing field. Most medical waste is incinerated, a practice that is short-lived because of environmental considerations. The burning of solid and regulated medical waste generated by health care creates many problems. Medical waste incinerators emit toxic air pollutants and toxic ash residues that are the major source of dioxins in the environment. International Agency for Research on Cancer, an arm of WHO, acknowledged dioxins cancer causing potential and classified it as human carcinogen. Development of waste management policies, careful waste segregation and training programs, as well as attention to materials purchased, are essential in minimizing the environmental and health impacts of any technology.

  3. 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

  4. Evaluation of food safety management systems in Serbian dairy industry

    Directory of Open Access Journals (Sweden)

    Igor Tomašević

    2016-01-01

    Full Text Available This paper reports incentives, costs, difficulties and benefits of food safety management systems implementation in the Serbian dairy industry. The survey involved 27 food business operators with the national milk and dairy market share of 65 %. Almost two thirds of the assessed dairy producers (70.4 % claimed that they had a fully operational and certified HACCP system in place, while 29.6 % implemented HACCP, but had no third party certification. ISO 22000 was implemented and certified in 29.6 % of the companies, while only 11.1 % had implemented and certified IFS standard. The most important incentive for implementing food safety management systems for Serbian dairy producers was to increase and improve safety and quality of dairy products. The cost of product investigation/analysis and hiring external consultants were related to the initial set-up of food safety management system with the greatest importance. Serbian dairy industry was not greatly concerned by the financial side of implementing food safety management systems due to the fact that majority of prerequisite programmes were in place and regularly used by almost 100 % of the producers surveyed. The presence of competency gap between the generic knowledge for manufacturing food products and the knowledge necessary to develop and implement food safety management systems was confirmed, despite the fact that 58.8 % of Serbian dairy managers had university level of education. Our study brings about the innovation emphasizing the attitudes and the motivation of the food production staff as the most important barrier for the development and implementation of HACCP. The most important identified benefit was increased safety of dairy products with the mean rank scores of 6.85. The increased customer confidence and working discipline of staff employed in food processing were also found as important benefits of implementing/operating HACCP. The study shows that the level of HACCP

  5. Quality management of pharmacology and safety pharmacology studies

    DEFF Research Database (Denmark)

    Spindler, Per; Seiler, Jürg P

    2002-01-01

    to safety pharmacology studies, and, when indicated, to secondary pharmacodynamic studies, does not influence the scientific standards of studies. However, applying formal GLP standards will ensure the quality, reliability and integrity of studies, which reflect sound study management. It is important...... to encourage a positive attitude among researchers and academics towards these lines, whenever possible. GLP principles applied to the management of non-clinical safety studies are appropriate quality standards when studies are used in the context of protecting public health, and these quality standards...... of pharmacology studies (ICH S7A): primary pharmacodynamic, secondary pharmacodynamic and safety pharmacology studies, and guidance on the quality standards (expectations for GLP conformity) for these study types have been provided. Primary pharmacodynamic studies are the only study types that are fully exempt...

  6. Comprehensive safety cases for radioactive waste management facilities

    International Nuclear Information System (INIS)

    Woollam, P.B.; Cameron, H.M.; Davies, A.R.; Hiscox, A.W.

    1995-01-01

    Probabilistic safety assessment methodology has been applied by Nuclear Electric plc (NE) to the development of comprehensive safety cases for the radioactive waste management processing and accumulation facilities associated with its 26 reactor systems. This paper describes the methodology and the safety case assessment criteria employed by NE. An overview of the results is presented, together with more detail of a specific safety analysis: storage of fuel element debris. No risk to the public greater than 10 -6 /y has been identified and the more significant risks arise from the potential for radioactive waste fires. There are no unacceptable risks from external hazards such as flooding, aircrash or seismic events. Some operations previously expected to have significant risks in fact have negligible risks, while the few faults with risks exceeding the assessment criteria were only identified as a result of this study

  7. Comprehensive safety cases for radioactive waste management facilities

    International Nuclear Information System (INIS)

    Woollam, P.B.

    1993-01-01

    Probabilistic safety assessment methodology is being applied by Nuclear Electric plc (NE) to the development of comprehensive safety cases for the radioactive waste management processing and accumulation facilities associated with its 26 reactor systems. This paper describes the methodology and the safety case assessment criteria employed by NE. An overview of the results from facilities used by the first 16 reactors is presented, together with more detail of a specific safety analysis: storage of fuel element debris. No risk to the public greater than 10 -6 /y has been identified and the more significant risks arise from the potential for radioactive waste fires. There are no unacceptable risks from external hazards such as flooding, aircrash or seismic events. Some operations previously expected to have significant risks in fact have negligible risks, while the few faults with risks exceeding the assessment criteria were only identified as a result of this study

  8. Medication Management, Use and Safety in Non- Communicable ...

    African Journals Online (AJOL)

    ... combination of the efforts from government, health professionals and the individual patients. Adequate education of the patients and the public can lead to behavioral change and reduction in NCDs while at the same time improving medication use behaviours. Keywords: NCDs, Drug management, Drug safety, Drug Use, ...

  9. Food safety management systems performance in the lamb production chain

    NARCIS (Netherlands)

    Oses, S.M.; Luning, P.A.; Jacxsens, L.; Jaime, I.; Rovira, J.

    2012-01-01

    This study describes a performance measurement of implemented food safety management system (FSMS) along the lamb chain using an FSMS-diagnostic instrument (FSMS-DI) and a Microbiological Assessment Scheme (MAS). Three slaughterhouses, 1 processing plant and 5 butcher shops were evaluated. All the

  10. Gun Safety Management with Patients at Risk for Suicide

    Science.gov (United States)

    Simon, Robert I.

    2007-01-01

    Guns in the home are associated with a five-fold increase in suicide. All patients at risk for suicide must be asked if guns are available at home or easily accessible elsewhere, or if they have intent to buy or purchase a gun. Gun safety management requires a collaborative team approach including the clinician, patient, and designated person…

  11. 75 FR 67450 - Pipeline Safety: Control Room Management Implementation Workshop

    Science.gov (United States)

    2010-11-02

    ... regulations to address human factors and other aspects of control room management for certain pipelines where controllers use supervisory control and data acquisition (SCADA) systems. Under the final rule, pipeline... Washington, DC on October 22, 2010. Jeffrey D. Wiese, Associate Administrator for Pipeline Safety. [FR Doc...

  12. Management capacity to promote nurse workplace health and safety.

    Science.gov (United States)

    Fang, Yaxuan; McDonald, Tracey

    2018-04-01

    To investigate regarding workplace health and safety factors, and to identify strategies to preserve and promote a healthy nursing workplace. Data collected using the Delphi technique with input from 41 key informants across four participant categories drawn from a Chinese university and four hospitals were thematically analysed. Most respondents agreed on the importance of nurses' health and safety, and that nurse managers should act to protect nurses, but not enough on workplace safety. Hospital policies, staff disempowerment, workload and workplace conflicts are major obstacles. The reality of Chinese nurses' workplaces is that health and safety risks abound and relate to socio-cultural expectations of women. Self-management of risks is neccessary, gaps exist in understanding of workplace risks among different nursing groups and their perceptions of the professional status, and the value of nurses' contribution to ongoing risks in the hospital workplace. The Chinese hospital system must make these changes to produce a safer working environment for nurses. This research, based in China, presents an instructive tale for all countries that need support on the types and amounts of management for nurses working at the clinical interface, and on the consequences of management neglect of relevant policies and procedures. © 2017 John Wiley & Sons Ltd.

  13. 76 FR 64110 - Safety and Health Management Programs for Mines

    Science.gov (United States)

    2011-10-17

    ... section of this notice. Comment Dates: MSHA will hold the date for comments open until all meetings are... Identification, including workplace inspections for violations of mandatory health and safety standards. Hazard.... Improved communication. Increased productivity. Increased and improved worker and management involvement in...

  14. Occupational safety and health management and risk governance

    NARCIS (Netherlands)

    Dijkman, A.; Terwoert, J.

    2014-01-01

    The advancement in new technologies, substances and new ways of working make it necessary to look beyond traditional methods of risk management. General drivers to emerging occupational safety and health (OSH) risks are: globalisation; demographic changes; technical innovations; changes in risk

  15. Risk Management: Earning Recognition with an Automated Safety Program

    Science.gov (United States)

    Lansberry, Linden; Strasburger, Tom

    2012-01-01

    Risk management is a huge task that requires diligent oversight to avoid penalties, fines, or lawsuits. Add in the burden of limited resources that schools face today, and the challenge of meeting the required training, reporting, compliance, and other administrative issues associated with a safety program is almost insurmountable. Despite an…

  16. Safety Management Practices in Small and Medium Enterprises in India

    Science.gov (United States)

    Unnikrishnan, Seema; Iqbal, Rauf; Singh, Anju; Nimkar, Indrayani M.

    2014-01-01

    Background Small and medium enterprises (SMEs) are often the main pillar of an economy. Minor accidents, ergonomics problems, old and outdated machinery, and lack of awareness have created a need for implementation of safety practices in SMEs. Implementation of healthy working conditions creates positive impacts on economic and social development. Methods In this study, a questionnaire was developed and administered to 30 randomly chosen SMEs in and around Mumbai, Maharashtra, and other states in India to evaluate safety practices implemented in their facilities. The study also looked into the barriers and drivers for technology innovation and suggestions were also received from the respondent SMEs for best practices on safety issues. Results In some SMEs, risks associated with safety issues were increased whereas risks were decreased in others. Safety management practices are inadequate in most SMEs. Market competitiveness, better efficiency, less risk, and stringent laws were found to be most significant drivers; and financial constraints, lack of awareness, resistance to change, and lack of training for employees were found to be main barriers. Conclusion Competition between SMEs was found to be major reason for implementation of safety practices in the SMEs. The major contribution of the study has been awareness building on safety issues in the SMEs that participated in the project. PMID:25830070

  17. Vessel Operating Units (Vessels)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — This data set contains data for vessels that are greater than five net tons and have a current US Coast Guard documentation number. Beginning in1979, the NMFS...

  18. Management by process based systems and safety focus

    International Nuclear Information System (INIS)

    Rydnert, Bo; Groenlund, Bjoern

    2005-12-01

    An initiative from The Swedish Nuclear Power Inspectorate led to this study carried out in the late autumn of 2005. The objective was to understand in more detail how an increasing use of process management affects organisations, on the one hand regarding risks and security, on the other hand regarding management by objectives and other management and operative effects. The main method was interviewing representatives of companies and independent experts. More than 20 interviews were carried out. In addition a literature study was made. All participating companies are using Management Systems based on processes. However, the methods chosen, and the results achieved, vary extensively. Thus, there are surprisingly few examples of complete and effective management by processes. Yet there is no doubt that management by processes is effective and efficient. Overall goals are reached, business results are achieved in more reliable ways and customers are more satisfied. The weaknesses found can be translated into a few comprehensive recommendations. A clear, structured and acknowledged model should be used and the processes should be described unambiguously. The changed management roles should be described and obeyed extremely legibly. New types of process objectives need to be formulated. In addition one fact needs to be observed and effectively fended off. Changes are often met by mental opposition on management level, as well as among co-workers. This fact needs attention and leadership. Safety development is closely related to the design and operation of a business management system and its continual improvement. A deep understanding of what constitutes an efficient and effective management system affects the understanding of safety. safety culture and abilities to achieve safety goals. Concerning risk, the opinions were unambiguous. Management by processes as such does not result in any further risks. On the contrary. Processes give a clear view of production and

  19. Nuclear materials management for safety and efficiency

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1965-12-15

    The use of nuclear materials in industrial processes presents management with some special problems which are peculiar to the atomic energy industry. If reactor fuel costs are to be kept low, too, each fuel element must yield the maximum economic 'bum-up' before it is withdrawn from service, and this calls for reliable non-destructive methods of measurement of 'burn-up' and appropriate records and fuel-changing schedules. The special hazards of radioactive materials call for special precautions and appropriate systems of handling and storage. A further danger unique to atomic energy is that of criticality - the possibility that an excessive concentration of fissile material may result in a chain reaction. Every part of the processing plant must be surveyed and checked to ensure that there is no build-up of fissile residues; in storage or transit there must be no aggregation of small lots. In the nuclear energy industry, too, the standards of purity required are much higher than in most other large-scale operation, so that stringent quality checks are needed

  20. Achievements and Perspectives of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management

    International Nuclear Information System (INIS)

    Louvat, D.; Lacoste, A.C.

    2006-01-01

    The Joint Convention on the Safety of Spent Fuel management and on the Safety of Radioactive Waste Management is the first legal instrument to directly address the safety of spent fuel and radioactive waste management on a global scale. The Joint Convention entered into force in 2001. This paper describes its process and its main achievements to date. The perspectives to establish of a Global Waste Safety Regime based on the Joint Convention are also discussed. (authors)

  1. Data fusion and sensor management for nuclear power plant safety

    Energy Technology Data Exchange (ETDEWEB)

    Ciftcioglu, O [Istanbul Technical Univ., Istanbul (Turkey). Nuclear Power Dept.; Turkcan, E [Netherlands Energy Research Foundation (ECN), Petten (Netherlands)

    1997-12-31

    The paper describes the implementation of the data-sensor fusion and sensor management technology for accident management through simulated severe accident (SA) scenarios subjected to study. The organization of the present paper is as follows. As the data-sensor fusion and sensor management is an emerging technology which is not widely known, in Sec. 2, the definition and goals of data-sensor fusion and sensor management technology is described. In Sec. 3 fits, with reference to Kalman filtering as an information filter, statistical data-sensor fusion technology is described. This is followed by deterministic data-sensor fusion technology using gross plant state variables and neural networks (NN) and the implementation for severe accident management in NPPs. In Sec. 4, the sensor management technology is described. Finally, the performance of the data-sensor fusion technology for NPP safety is discussed. 12 refs, 6 figs.

  2. Data fusion and sensor management for nuclear power plant safety

    International Nuclear Information System (INIS)

    Ciftcioglu, O.

    1996-01-01

    The paper describes the implementation of the data-sensor fusion and sensor management technology for accident management through simulated severe accident (SA) scenarios subjected to study. The organization of the present paper is as follows. As the data-sensor fusion and sensor management is an emerging technology which is not widely known, in Sec. 2, the definition and goals of data-sensor fusion and sensor management technology is described. In Sec. 3 fits, with reference to Kalman filtering as an information filter, statistical data-sensor fusion technology is described. This is followed by deterministic data-sensor fusion technology using gross plant state variables and neural networks (NN) and the implementation for severe accident management in NPPs. In Sec. 4, the sensor management technology is described. Finally, the performance of the data-sensor fusion technology for NPP safety is discussed. 12 refs, 6 figs

  3. Safety culture aspects of managing for safety. Experience of a large nuclear reprocessing site

    International Nuclear Information System (INIS)

    Rycraft, H.S.

    1996-01-01

    The Nuclear Industry is going through turbulent times both in terms of public acceptance and business issues. Safety is one area which impacts on whether the business is allowed to continue, and how an organisation organizes itself. The need to cut costs to make nuclear power a viable energy resource, has forced the nuclear utilities to review manning policies, and management style, and in particular how to maintain safety standards during a period of change, and ultimately support continuing improvement of standards. The shrinking workforce requires a new style of management, one that depends more on the people of the organisation taking responsibility for safety at all levels of the organisation. Not only personal safety but the safety of their colleagues, general public and the environment. The safety culture of an organisation is indivisible from the company culture, each aspect of a culture influences the whole and so the balance between business, safety and quality, has to be managed. BNFL provides a full fuel cycle service to nuclear power plants, and associated services to many national and international organisations. The following notes are taken from the work carried out in the company, and mostly at the Nuclear Reprocessing and Waste storage Site at Sellafield, based in the North West of England. Following the recent re-organisation, the site now employs 6200 people and has a further 1500 contractors working on construction activities on the site. Activities on the site range from remote handling to hands on tasks, involving highly active materials to low level waste. (author)

  4. Knowledge management for assuring high standards in nuclear safety

    International Nuclear Information System (INIS)

    Hahn, L.

    2004-01-01

    The primary incentives for introducing knowledge management in organisations active in the nuclear field are the impending loss of knowledge due to an ageing workforce and the necessity to transfer knowledge to the next generation. However, knowledge management may reach much further, and it is shown that ultimately, the goals of knowledge management are congruent with establishing, maintaining and further developing high standards of safety. Knowledge-based activities to reach these goals are discussed, and examples given for producing, utilising and sharing knowledge in organisations and in national and international networks. (author)

  5. Increase of Technogenic Safety of a Waste Management Company

    Directory of Open Access Journals (Sweden)

    Cudečka-Puriņa Natālija

    2017-11-01

    Full Text Available Waste management is often recognised in the society as an activity sector possessing an extensive potential harm on technogenic safety. As most of the European Union countries have experienced at least theoretical shift from waste management to resource management, it is now extremely important to implement this shift in practice, moving from disposing waste or by-products to developing a cooperation network that allows different industries to use each other’s waste as resources. This shift will lead to saving of primary resources and raw materials and develop recycling and reuse, bringing them to a higher level.

  6. Chemical process safety management within the Department of Energy

    International Nuclear Information System (INIS)

    Piatt, J.A.

    1995-07-01

    Although the Department of Energy (DOE) is not well known for its chemical processing activities, the DOE does have a variety of chemical processes covered under OSHA's Rule for Process Safety Management of Highly Hazardous Chemicals (the PSM Standard). DOE, like industry, is obligated to comply with the PSM Standard. The shift in the mission of DOE away from defense programs toward environmental restoration and waste management has affected these newly forming process safety management programs within DOE. This paper describes the progress made in implementing effective process safety management programs required by the PSM Standard and discusses some of the trends that have supported efforts to reduce chemical process risks within the DOE. In June of 1994, a survey of chemicals exceeding OSHA PSM or EPA Risk Management Program threshold quantities (TQs) at DOE sites found that there were 22 processes that utilized toxic or reactive chemicals over TQs; there were 13 processes involving flammable gases and liquids over TQs; and explosives manufacturing occurred at 4 sites. Examination of the survey results showed that 12 of the 22 processes involving toxic chemicals involved the use of chlorine for water treatment systems. The processes involving flammable gases and liquids were located at the Strategic Petroleum Reserve and Naval petroleum Reserve sites

  7. Regulatory safety aspects of nuclear waste management operations in India

    International Nuclear Information System (INIS)

    Sundararajan, A.R.

    2000-01-01

    The Department of Atomic Energy in India as part of its programme to harness the nuclear energy for generation of nuclear power has been operating a whole range of nuclear fuel cycle facilities including waste management plants for more than four decades. The waste management plants include three high level waste immobilisation plants, one in operation, one under commissioning and one more under construction. Atomic Energy Regulatory Board is mandated to review and authorise from the safety angle the siting, the design, the construction and the operation of the waste management plants. The regulatory procedures, which involve multi-tier review adopted for ensuring the safety of these facilities, are described in this paper. (author)

  8. RW management safety assessment in Armenia

    International Nuclear Information System (INIS)

    Avetisyan, A.

    2003-01-01

    The paper presents: the legislation in respect of radioactive waste management; various types of radioactive waste generators; waste streams and inventory; existing storage and disposal facilities; plans and strategies for evaluation of existing facilities and waste acceptance criteria for Radon type facility. Armenian NPP generates solid radioactive wastes per year: low level wastes - approx. 107 m 3 ; medium level wastes - approx. 0.3 m 3 ; high level wastes - approx. 0.24 m 3 . Isotopic inventory of solid wastes are as follows; Cs-137, Cs-134, Co-60 , Mn-54, Ag-110m, Sr-90. Medical, industrial and other wastes are from approximately 10 ionizing sources per year. The inventory of municipal type of radioactive wastes disposed in RADON type facility is as follows: H-3, Cs-137, Co-60, Am-241, C-14, Pu-238,239, Sr-90, Tc-99. The amount of total activity of disposed and stored wastes are 20.1 TBq. Storage for low level solid wastes in the Armenian NPP is in a typical near surface disposal facility, with engineered barriers, below the ground surface 10 m. The Radon type facility is a near surface disposal facility, with engineered barriers, below the ground surface 3 m. The design volume capacity is 2520 m 3 with 3 separate disposal facilities each one with 840 m 3 volume. For the spend sources are foreseen 2 boreholes, made by rotary drilling devices. Due to absence of mechanical manipulators, the high level spend sources are stored in the ANPP high level waste storage facility. For the waste treatment, the cementation device has been installed during construction, but due to mistake in device design, it never had been operated. The waste acceptance criteria for the facility are: regarding the origin of waste - non-nuclear wastes (medical, industrial, research and etc); permissible mass activity and volume activity of entered wastes must not exit 3.7 E+6Bq/(l, kg); permissible total activity of disposed disused sources must not exit (for 2 bore halls ) 40.000 g

  9. The use of GIS tools for road infrastructure safety management

    Science.gov (United States)

    Budzyński, Marcin; Kustra, Wojciech; Okraszewska, Romanika; Jamroz, Kazimierz; Pyrchla, Jerzy

    2018-01-01

    There are many factors that influence accidents and their severity. They can be grouped within the system of man, vehicle and environment. The article focuses on how GIS tools can be used to manage road infrastructure safety. To ensure a better understanding and identification of road factors, GIS tools help with the acquisition of road parameter data. Their other role is helping with a clear and effective presentation of risk ranking. GIS is key to identifying high-risk sections and supports the effective communication of safety levels. This makes it a vital element of safety management. The article describes the use of GIS for the collection and visualisation of road parameter data which are not available in any of the existing databases, i.e. horizontal curve parameters. As we know from research and statistics, they are important factors that determine the safety of road infrastructure. Finally, new research is proposed as well as the possibilities for applying GIS tools for the purposes of road safety inspection.

  10. 2011 Vessel Density

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Automatic Identification Systems (AIS) are a navigation safety device that transmits and monitors the location and characteristics of many vessels in U.S. and...

  11. 2011 Fishing Vessel Density

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Automatic Identification Systems (AIS) are a navigation safety device that transmits and monitors the location and characteristics of many vessels in U.S. and...

  12. 2013 Tanker Vessel Density

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Automatic Identification Systems (AIS) are a navigation safety device that transmits and monitors the location and characteristics of many vessels in U.S. and...

  13. 2013 Cargo Vessel Density

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Automatic Identification Systems (AIS) are a navigation safety device that transmits and monitors the location and characteristics of many vessels in U.S. and...

  14. 2013 Fishing Vessel Density

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Automatic Identification Systems (AIS) are a navigation safety device that transmits and monitors the location and characteristics of many vessels in U.S. and...

  15. 2013 Vessel Density

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Automatic Identification Systems (AIS) are a navigation safety device that transmits and monitors the location and characteristics of many vessels in U.S. and...

  16. Assembly and gap management strategy for the ITER NBI vessel passive magnetic shield

    Energy Technology Data Exchange (ETDEWEB)

    Ríos, Luis, E-mail: luis.rios@ciemat.es [CIEMAT Laboratorio Nacional de Fusión, Avda. Complutense 22, 28040 Madrid (Spain); Ahedo, Begoña; Alonso, Javier; Barrera, Germán; Cabrera, Santiago; Rincón, Esther; Ramos, Francisco [CIEMAT Laboratorio Nacional de Fusión, Avda. Complutense 22, 28040 Madrid (Spain); El-Ouazzani, Anass; Graceffa, Joseph; Urbani, Marc; Shah, Darshan [ITER Organization, Route de Vinon-sur-Verdon – CS 90 046, 13067 St Paul Lez Durance Cedex (France); Agarici, Gilbert [Fusion for Energy, Josep Pla 2, Torres Diagonal Litoral B3 – 07/08, 08019 Barcelona (Spain)

    2015-10-15

    The neutral beam system for ITER consists of two heating and current drive neutral ion beam injectors (HNB) and a diagnostic neutral beam (DNB) injector. The proposed physical plant layout allows a possible third HNB injector to be installed later. The HNB Passive Magnetic Shield (PMS) works in conjunction with the active compensation/correction coils to limit the magnetic field inside the Beam Line Vessel (BLV), Beam Source Vessel (BSV), High Voltage Bushing (HVB) and Transmission Line (TL) elbow to acceptable levels that do not interfere with the operation of the HNB components. This paper describes the current design of the PMS, having had only minor modifications since the preliminary design review (PDR) held in IO in April 2013, and the assembly strategy for the vessel PMS.

  17. 30 CFR 285.810 - What must I include in my Safety Management System?

    Science.gov (United States)

    2010-07-01

    ... 30 Mineral Resources 2 2010-07-01 2010-07-01 false What must I include in my Safety Management System? 285.810 Section 285.810 Mineral Resources MINERALS MANAGEMENT SERVICE, DEPARTMENT OF THE INTERIOR..., COPs and GAPs Safety Management Systems § 285.810 What must I include in my Safety Management System...

  18. Integrated Safety Management System Phase I Verification for the Plutonium Finishing Plant (PFP) [VOL 1 & 2

    Energy Technology Data Exchange (ETDEWEB)

    SETH, S.S.

    2000-01-10

    U.S. Department of Energy (DOE) Policy 450.4, Safety Management System Policy commits to institutionalizing an Integrated Safety Management System (ISMS) throughout the DOE complex as a means of accomplishing its missions safely. DOE Acquisition Regulation 970.5204-2 requires that contractors manage and perform work in accordance with a documented safety management system.

  19. On Safety Management. A Frame of Reference for Studies of Safety Management with Examples From Non-Nuclear Contexts of Relevance for Nuclear Safety

    International Nuclear Information System (INIS)

    Svensson, Ola; Salo, Ilkka; Allwin, Pernilla

    2004-11-01

    A good knowledge about safety management from risk technologies outside the area of nuclear power may contribute to both broaden the perspectives on safety management in general, and point at new opportunities for improving safety measures within the nuclear industry. First, a theoretical framework for the study of safety management in general is presented, followed by three case studies on safety management from different non-nuclear areas with potential relevance for nuclear safety. The chapters are written as separate reports and can be read independently of each other. The nuclear industry has a long experience about the management of risky activities, involving all the stages from planing to implementation, both on a more generalized level and in the specific branches of activities (management, administration, operation, maintenance, etc.). Here, safety management is a key concept related to these areas of activities. Outside the field of nuclear power there exist a number of different non-nuclear risk technologies, each one with their own specific needs and experiences about safety management. The differences between the areas consist partly of the different experiences caused by the different technologies. Besides using own experiences in safety practices within the own areas of activities, it may be profitable to take advantage in knowledge and experiences from one area and put it in practice in another area. In order to facilitate knowledge transfer from one technological area to another it may be possible to adapt a common theoretical model, for descriptions and explanations, to the different technologies. Such a model should admit that common denominators for safety management across the areas might be identified and described with common concepts. Systems theory gives the opportunity to not only create models that are descriptive for events within the limits of a given technology, but also to generate knowledge that can be transferred to other

  20. Department of Energy safety management: A need for change

    International Nuclear Information System (INIS)

    McCoy, F.B. III

    1995-01-01

    The U.S. Department of Energy's (DOE's) approach to safety management is undergoing fundamental change that should improve effective implementation of requirements throughout the complex. The most significant conveyor of this change is the open-quotes necessary and sufficientclose quotes closure process. The necessary and sufficient closure process draws upon the many and varied laws, requirements, and standards that exist in today's world to systematically derive a necessary and sufficient set of requirements for the particular work at hand to provide adequate protection for the associated hazards. The set is implemented through a system of management controls that convey fundamental safety principles and include design and analyses, engineered safety features, and procedures for the particular work. Assurance that an adequate level of protection is afforded by the set demands a need for competent, disciplined, and rigorous implementation. When properly done, the necessary and sufficient closure process enables such implementation. The focus of this paper is to provide an understanding of why the necessary and sufficient closure process is a necessary safety management program change and how integrity of this process can be assured

  1. DART - for design basis justification and safety related information management

    International Nuclear Information System (INIS)

    Billington, A.; Blondiaux, P.; Boucau, J.; Cantineau, B.; Doumont, C.; Mared, A.

    2000-01-01

    DART is the acronym for Design Analysis Re-engineering Tool. It embodies a systematic and integrated approach to NPP safety re-assessment and configuration management, that makes use of Reverse Failure Mode and Effect Analysis in conjunction with a state-of-the-art relational database and a standardized data format, to permit long-term management of plant safety related information. The plant design is reviewed in a step-by-step logical fashion by constructing fault trees that identify the link between undesired consequences and their causes. Each failure cause identified in a fault tree is addressed by defining functional requirements, which are in turn addressed by documenting the specific manner in which the plant complies with the requirement. The database can be used to generate up-to-date plant safety related documents, including: SAR, Systems Descriptions, Technical Specifications and plant procedures. The approach is open-minded by nature and therefore is not regulatory driven, however the plant licensing basis will also be reviewed and documented within the same database such that a Regulatory Conformance Program may be integrated with the other safety documentation. This methodology can thus reconstitute the plant design bases in a comprehensive and systematic way, while allowing to uncover weaknesses in design. The original feature of the DART methodology is that it links all the safety related documents together, facilitating the evaluation of the safety impact resulting from any plant modification. Due to its capability to retrieve the basic justifications of the plant design, it is also a useful tool for training the young generation of plant personnel. The DART methodology has been developed for application to units 2, 3 and 4 at Vattenfall's Ringhals site in Sweden. It may be applied to any nuclear power plant or industrial facility where public safety is a concern. (author)

  2. DART - for design basis justification and safety related information management

    International Nuclear Information System (INIS)

    Billington, A.; Blondiaux, B.; Boucau, J.; Cantineau, B.; Mared, A.

    2001-01-01

    DART is the acronym for Design Analysis Re-Engineering Tool. It embodies a systematic and integrated approach to NPP safety re-assessment and configuration management, that makes use of Reverse Failure Mode and Effect Analysis in conjunction with a state-of-the-art relational database and a standardized data format, to permit long-term management of plant safety related information. The plant design is reviewed in a step-by-step logical fashion by constructing fault trees that identify the link between undesired consequences and their causes. Each failure cause identified in a fault tree is addressed by defining functional requirements, which are in turn addressed by documenting the specific manner in which the plant complies with the requirement. The database can then be used to generate up-to-date plant safety related documents, including: SAR, Systems Descriptions, Technical Specifications and plant procedures. The approach is open-minded by nature and therefore is not regulatory driven, however the plant licensing basis will also be reviewed and documented within the same database such that a Regulatory Conformance Program may be integrated with the other safety documentation. This methodology can thus reconstitute the plant design bases in a comprehensive and systematic way, while allowing to uncover weaknesses in design. The original feature of the DART methodology is that it links all the safety related documents together, facilitating the evaluation of the safety impact resulting from any plant modification. Due to its capability to retrieve the basic justifications of the plant design, it is also a useful tool for training the young generation of plant personnel. The DART methodology has been developed for application to units 2, 3 and 4 at Vattenfall's Ringhals site in Sweden. It may be applied to any nuclear power plant or industrial facility where public safety is a concern. (author)

  3. Safe patient care - safety culture and risk management in otorhinolaryngology.

    Science.gov (United States)

    St Pierre, Michael

    2013-12-13

    Safety culture is positioned at the heart of an organization's vulnerability to error because of its role in framing organizational awareness to risk and in providing and sustaining effective strategies of risk management. Safety related attitudes of leadership and management play a crucial role in the development of a mature safety culture ("top-down process"). A type marker for organizational culture and thus a predictor for an organization's maturity in respect to safety is information flow and in particular an organization's general way of coping with information that suggests anomaly. As all values and beliefs, relationships, learning, and other aspects of organizational safety culture are about sharing and processing information, safety culture has been termed "informed culture". An informed culture is free of blame and open for information provided by incidents. "Incident reporting systems" are the backbone of a reporting culture, where good information flow is likely to support and encourage other kinds of cooperative behavior, such as problem solving, innovation, and inter-departmental bridging. Another facet of an informed culture is the free flow of information during perioperative patient care. The World Health Organization's safe surgery checklist" is the most prevalent example of a standardized information exchange aimed at preventing patient harm due to information deficit. In routine tasks mandatory standard operating procedures have gained widespread acceptance in guaranteeing the highest possible process quality. Technical and non-technical skills of healthcare professionals are the decisive human resource for an efficient and safe delivery of patient care and the avoidance of errors. The systematic enhancement of staff qualification by providing training opportunities can be a major investment in patient safety. In recent years several otorhinolaryngology departments have started to incorporate stimulation based team trainings into their

  4. [Safe patient care: safety culture and risk management in otorhinolaryngology].

    Science.gov (United States)

    St Pierre, M

    2013-04-01

    Safety culture is positioned at the heart of an organisation's vulnerability to error because of its role in framing organizational awareness to risk and in providing and sustaining effective strategies of risk management. Safety related attitudes of leadership and management play a crucial role in the development of a mature safety culture ("top-down process"). A type marker for organizational culture and thus a predictor for an organizations maturity in respect to safety is information flow and in particular an organization's general way of coping with information that suggests anomaly. As all values and beliefs, relationships, learning, and other aspects of organizational safety culture are about sharing and processing information, safety culture has been termed "informed culture". An informed culture is free of blame and open for information provided by incidents. "Incident reporting systems" are the backbone of a reporting culture, where good information flow is likely to support and encourage other kinds of cooperative behavior, such as problem solving, innovation, and inter-departmental bridging. Another facet of an informed culture is the free flow of information during perioperative patient care. The World Health Organisation's "safe surgery checklist" is the most prevalent example of a standardized information exchange aimed at preventing patient harm due to information deficit. In routine tasks mandatory standard operating procedures have gained widespread acceptance in guaranteeing the highest possible process quality.Technical and non-technical skills of healthcare professionals are the decisive human resource for an efficient and safe delivery of patient care and the avoidance of errors. The systematic enhancement of staff qualification by providing training opportunities can be a major investment in patient safety. In recent years several otorhinolaryngology departments have started to incorporate simulation based team trainings into their curriculum

  5. Production management and quality assurance for the fabrication of the In-Vessel Components of the stellarator Wendelstein 7-X

    Energy Technology Data Exchange (ETDEWEB)

    Li, C., E-mail: chuanfei.li@ipp.mpg.de; Boscary, J.; Dekorsy, N.; Junghanns, P.; Mendelevitch, B.; Peacock, A.; Pirsch, H.; Sellmeier, O.; Springer, J.; Stadler, R.; Streibl, B.

    2014-10-15

    Highlights: • Thousand parts for the divertor, first wall, cooling supply and diagnostics as W7-X In-Vessel Components. • Database building including part and assembly data, work and capacity organization, quality assurance documents. • Production management system to organize the fabrication and the associated quality assurance. • Successful use of an efficient and flexible product planning and scheduling tool for W7-X In-Vessel Components. - Abstract: The In-Vessel Components (IVC) of the stellarator Wendelstein 7-X consist of the divertor components and the first wall (FW) with their internal water cooling supply and a set of diagnostics. Due to the significant amount of different components, including many variants, a tool called Production Managing System (PMS) has been developed to organize the fabrication and the associated quality assurance. The PMS works by building a database containing the basic parts and assembly data, manufacturing and quality control plans, and available machine capacity. The creation of this database is based mainly on the parts lists, the manufacturing drawings, and details of the working flow organization. As a consequence of the learning process and technical adjustments during the design and manufacturing phase, the database needed to be permanently updated. Therefore an interface tool to optimize the data preparation has been developed. PMS has been demonstrated to be an efficient tool to support the IVC production activities providing reliable planning estimates, easily adaptable to problems encountered during the fabrication and provided a basis for the integration of quality assurance requirements.

  6. Production management and quality assurance for the fabrication of the In-Vessel Components of the stellarator Wendelstein 7-X

    International Nuclear Information System (INIS)

    Li, C.; Boscary, J.; Dekorsy, N.; Junghanns, P.; Mendelevitch, B.; Peacock, A.; Pirsch, H.; Sellmeier, O.; Springer, J.; Stadler, R.; Streibl, B.

    2014-01-01

    Highlights: • Thousand parts for the divertor, first wall, cooling supply and diagnostics as W7-X In-Vessel Components. • Database building including part and assembly data, work and capacity organization, quality assurance documents. • Production management system to organize the fabrication and the associated quality assurance. • Successful use of an efficient and flexible product planning and scheduling tool for W7-X In-Vessel Components. - Abstract: The In-Vessel Components (IVC) of the stellarator Wendelstein 7-X consist of the divertor components and the first wall (FW) with their internal water cooling supply and a set of diagnostics. Due to the significant amount of different components, including many variants, a tool called Production Managing System (PMS) has been developed to organize the fabrication and the associated quality assurance. The PMS works by building a database containing the basic parts and assembly data, manufacturing and quality control plans, and available machine capacity. The creation of this database is based mainly on the parts lists, the manufacturing drawings, and details of the working flow organization. As a consequence of the learning process and technical adjustments during the design and manufacturing phase, the database needed to be permanently updated. Therefore an interface tool to optimize the data preparation has been developed. PMS has been demonstrated to be an efficient tool to support the IVC production activities providing reliable planning estimates, easily adaptable to problems encountered during the fabrication and provided a basis for the integration of quality assurance requirements

  7. Risk and Work Configuration Management as a Function of Integrated Safety Management

    International Nuclear Information System (INIS)

    Lana Buehrer; Michele Kelly; Fran Lemieux; Fred Williams

    2007-01-01

    National Security Technologies, LLC (NSTec), has established a work management program and corresponding electronic Facilities and Operations Management Information System (e-FOM) to implement Integrated Safety Management (ISM). The management of work scopes, the identification of hazards, and the establishment of implementing controls are reviewed and approved through electronic signatures. Through the execution of the program and the implementation of the electronic system, NSTec staff work within controls and utilize feedback and improvement process. The Integrated Work Control Manual further implements the five functions of ISM at the Activity level. By adding the Risk and Work Configuration Management program, NSTec establishes risk acceptance (business and physical) for liabilities within the performance direction and work management processes. Requirements, roles, and responsibilities are specifically identified in the program while e-FOM provides the interface and establishes the flowdown from the Safety Chain to work and facilities management processes to company work-related directives, and finally to Subject Matter Expert concurrence. The Program establishes, within the defined management structure, management levels for risk identification, risk mitigation (controls), and risk acceptance (business and physical) within the Safety Chain of Responsibility. The Program also implements Integrated Safeguards and Security Management within the NSTec Safety Chain of Responsibility. Once all information has been entered into e-FOM, approved, and captured as data, the information becomes searchable and sortable by hazard, location, organization, mitigating controls, etc

  8. Generic analyses for evaluation of low Charpy upper-shelf energy effects on safety margins against fracture of reactor pressure vessel materials

    International Nuclear Information System (INIS)

    Dickson, T.L.

    1993-07-01

    Appendix G to 10 CFR Part 50 requires that reactor pressure vessel beltline material maintain Charpy upper-shelf energies of no less than 50 ft-lb during the plant operating life, unless it is demonstrated in a manner approved by the Nuclear Regulatory Commission (NRC), that lower values of Charpy upper-shelf energy provide margins of safety against fracture equivalent to those in Appendix G to Section XI of the ASME Code. Analyses based on acceptance criteria and analysis methods adopted in the ASME Code Case N-512 are described herein. Additional information on material properties was provided by the NRC, Office of Nuclear Regulatory Research, Materials Engineering Branch. These cases, specified by the NRC, represent generic applications to boiling water reactor and pressurized water reactor vessels. This report is designated as HSST Report No. 140

  9. 60th Anniversary of electricity production from light water reactors: Historical review of the contribution of materials science to the safety of the pressure vessel

    International Nuclear Information System (INIS)

    Duysen, J.C. van; Meric de Bellefon, G.

    2017-01-01

    The first light water nuclear reactor dedicated to electricity production was commissioned in Shippingport, Pennsylvania in the United States in 1957. Sixty years after the event, it is clear that this type of reactor will be a major source of electricity and one of the key solutions to limit climate change in the 21st century. This article pays homage to the teams that contributed to this achievement by their involvement in research and development and their determination to push back the frontiers of knowledge. Via a few examples of scientific or technological milestones, it describes the evolution of ideas, models, and techniques during the last 60 years, and gives the current state-of-the-art in areas related to the safety of the reactor pressure vessel. Among other topics, it focuses on vessel manufacturing, steel fracture mechanics analysis, and understanding of irradiation-induced damage.

  10. 60th Anniversary of electricity production from light water reactors: Historical review of the contribution of materials science to the safety of the pressure vessel

    Energy Technology Data Exchange (ETDEWEB)

    Duysen, J.C. van, E-mail: jean-claude.van-duysen@ensc-lille.fr [Department of Nuclear Engineering University of Tennessee Knoxville (United States); Unité Matériaux et Transformation (UMET) CNRS, Université de Lille 1 (France); Meric de Bellefon, G., E-mail: mericdebelle@wisc.edu [Department of Nuclear Engineering, University of Wisconsin, Madison (United States)

    2017-02-15

    The first light water nuclear reactor dedicated to electricity production was commissioned in Shippingport, Pennsylvania in the United States in 1957. Sixty years after the event, it is clear that this type of reactor will be a major source of electricity and one of the key solutions to limit climate change in the 21st century. This article pays homage to the teams that contributed to this achievement by their involvement in research and development and their determination to push back the frontiers of knowledge. Via a few examples of scientific or technological milestones, it describes the evolution of ideas, models, and techniques during the last 60 years, and gives the current state-of-the-art in areas related to the safety of the reactor pressure vessel. Among other topics, it focuses on vessel manufacturing, steel fracture mechanics analysis, and understanding of irradiation-induced damage.

  11. Influence of safety limitations on the fuel cycle management

    Energy Technology Data Exchange (ETDEWEB)

    Mancini, G

    1972-05-03

    The choice of an optimum fuel cycle has been up to now governed from the safety point of view, by the setting of very general limitations on few parameters, as for instance on the fuel temperature and on the surface temperature. As a better understanding of the design and materials limitations become available, the philosophy of the fuel cycle optimisation can be improved. The aim of this contribution is to shortly revise the safety aspects involved in the choice of a fuel cycle management and thereafter try to draw some general conclusions.

  12. Safety Incident Management Team Report for NIMLT Case 50796

    LENUS (Irish Health Repository)

    2017-01-17

    This is a report on the management of a patient safety incident involving BowelScreen and symptomatic colonoscopy services at Wexford General Hospital (WGH). The patient safety incident relates to the work of a Consultant Endoscopist (referred to as Clinician Y) employed by WGH who undertook screening colonoscopies on behalf of the BowelScreen Programme since the commencement of the screening programme in WGH in March 2013. Clinician Y also performed non-screening colonoscopies for the diagnosis of symptomatic patients as part of routine surgical service provision at WGH.\\r\

  13. Procedures for initiation, cost-sharing and management of OECD projects in nuclear safety

    International Nuclear Information System (INIS)

    2002-01-01

    The OECD (CSNI) projects aim to produce results relevant for the safe operation of nuclear power plants through international collaborative projects. In general, the projects consist of advanced experimental programmes that are conducted at specialized facilities. At present, the following OECD (CSNI) projects are in operation: - The Halden Project, covering fuel/materials and I and C/Human Factors issues; - The Cabri Project, addressing reactivity transients on high burnup fuels; - The MASCA Project, which deals with in-vessel corium phenomena; - The OLHF Project, dealing with lower head failure mechanisms; - The SETH Project addressing thermal-hydraulics issues, started in 2001; - The MCCI Project on ex-vessel coolability and melt-concrete interaction. There are significant differences among these projects in terms of their motivation, size and scope. The Halden Project and the Cabri Water Loop Project are large undertakings where the host organisations assume full and direct responsibility for the project establishment and administration - as well as for the negotiation with relevant parties on the terms of participation. In the other cases, instead, the NEA secretariat has a more direct responsibility, conferred by the CSNI, in establishing the project technical and financial basis, as well as for its implementation and administration. The objective of this procedure is to provide a common basis for the establishment and management of the OECD projects in the area of nuclear safety. It is a follow-up of a recommendation expressed by the CSNI Bureau during its meeting in October 2001, where the procedures for the establishment and management of the OECD (CSNI) projects in nuclear safety were addressed. While this procedure attempts at defining general guidelines for project initiation, financing and management, one should bear in mind that each project has its own motivation, background and framework. Thus, some degree of flexibility in project structure

  14. Vessel traffic patterns in the Port of Kaohsiung and the management implications for preventing the introduction of non-indigenous aquatic species.

    Science.gov (United States)

    Liu, Ta-Kang; Tsai, Tzung-Kuen

    2011-03-01

    Data on shipping traffic in one of the busiest seaports in the world, the Port of Kaohsiung, were analyzed to evaluate the implications for ballast water management. Results show that 67% of the arriving vessels were registered to a flag of convenience, which typically have a lower degree of environmental records. The top five donor countries historically suffer from harmful algal bloom problems. The short journey and busy trading between these countries and Taiwan lead to a higher risk of inoculation. In addition, only 1.4% of all vessels visited more than once every year during the 9-year span, indicating that the port authority encounters many new vessels each year. These findings could influence the design and application of ballast water management strategies as well as highlight the challenges in their implementation. We suggest that an analysis of vessel traffic patterns should be coupled with other useful vessel information to make risk assessment successful. Copyright © 2010. Published by Elsevier Ltd.

  15. 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

  16. Towards servitization in the management of occupational safety

    Directory of Open Access Journals (Sweden)

    Jasmina Berbegal

    2014-04-01

    Full Text Available Purpose: This article aims to examine the relationship between occupational accidents and the type of occupational safety resources that the company implements. Design/methodology/approach: Using a sample of 4750 firms gathered from the National Survey of Safety Management and Health Enterprises (ENGE for 2009, we first carried out a descriptive analysis of the data, and second we run an empirical analysis based on logistic and Tobit regressions. Findings and Originality/value: The results allow us to identify which companies and what kind of preventive activities are usually outsourced to an external firm specialized at providing occupational safety services. Second, the empirical analysis shows that outsourcing part of occupational safety activities also helps reduce the index of workplace accidents. Research limitations/implications: The present case focuses on Spanish companies and for a particular period (years 2007 and 2008. Because each country has specific regulations regarding the implementation of occupational safety services, the conclusions cannot be directly extrapolated to other countries. Practical implications: The results obtained are hoped to assist companies in choosing those prevention services that best suits their needs. Furthermore, this study is expected to contribute to the current debate on the design of prevention policies by public authorities, encouraging the outsourcing of occupational safety services as a way to take advantage of their expertise and reduce the number of accidents. Originality/value: Most of the academic literature on occupational safety has ignored the study of the impact that prevention services have on the firm’s performance, in terms of occupational accidents. This article contributes to filling this gap by demonstrating that the servitization trend is also impacting in the field of occupational safety.

  17. Knowledge management: the cornerstone of a 21. century safety case

    International Nuclear Information System (INIS)

    Umeki, H.; Osawa, H.; Naito, M.; Nakano, K.; Makino, H.; Mc Kinley, I.G.

    2008-01-01

    The safety case for a radioactive waste repository involves many complex, multi-disciplinary issues; these must be summarised in a comprehensive and concise manner, with links to all supporting information. The safety case can thus be considered an edifice built on structured knowledge. Knowledge is defined here in the very widest sense; including all of the information underpinning a repository project. Knowledge management covers all aspects of the development, integration, quality assurance, communication and maintenance/archiving of such knowledge. When seen from this perspective, the exponential expansion of the knowledge base represents a little-discussed challenge to safety case development. Indeed, knowledge production rates in this area are rapidly reaching, if not already surpassing, the limits of traditional management methods. This problem has been recognised in Japan and thus a project has been initiated to develop a next generation knowledge management system (KMS). This will utilize advanced electronic information management technology to handle the vast quantity of material involved. Autonomic systems will perform many of the information processing functions, helping ensure that required knowledge is accessible to all stakeholders and that gaps can be identified and supporting R and D prioritized. In a departure from conventional structuring by technical discipline, the prototype KMS utilizes a safety case structure. This should facilitate use of the core of neutral scientific and technical knowledge by both the implementer and the regulator. Flexibility is built into the system, to allow it to be restructured to match the user needs or even interfaced directly to a formal requirements management system. (authors)

  18. Managing risk in healthcare: understanding your safety culture using the Manchester Patient Safety Framework (MaPSaF).

    Science.gov (United States)

    Parker, Dianne

    2009-03-01

    To provide sufficient information about the Manchester Patient Safety Framework (MaPSaF) to allow healthcare professionals to assess its potential usefulness. The assessment of safety culture is an important aspect of risk management, and one in which there is increasing interest among healthcare organizations. Manchester Patient Safety Framework offers a theory-based framework for assessing safety culture, designed specifically for use in the NHS. The framework covers multiple dimensions of safety culture, and five levels of safety culture development. This allows the generation of a profile of an organization's safety culture in terms of areas of relative strength and challenge, which can be used to identify focus issues for change and improvement. Manchester Patient Safety Framework provides a useful method for engaging healthcare professionals in assessing and improving the safety culture in their organization, as part of a programme of risk management.

  19. Linking better shiftwork arrangements with safety and health management systems.

    Science.gov (United States)

    Kogi, Kazutaka

    2004-12-01

    Various support measures useful for promoting joint change approaches to the improvement of both shiftworking arrangements and safety and health management systems were reviewed. A particular focus was placed on enterprise-level risk reduction measures linking working hours and management systems. Voluntary industry-based guidelines on night and shift work for department stores and the chemical, automobile and electrical equipment industries were examined. Survey results that had led to the compilation of practicable measures to be included in these guidelines were also examined. The common support measures were then compared with ergonomic checkpoints for plant maintenance work involving irregular nightshifts. On the basis of this analysis, a new night and shift work checklist was designed. Both the guidelines and the plant maintenance work checkpoints were found to commonly cover multiple issues including work schedules and various job-related risks. This close link between shiftwork arrangements and risk management was important as shiftworkers in these industries considered teamwork and welfare services to be essential for managing risks associated with night and shift work. Four areas found suitable for participatory improvement by managers and workers were work schedules, ergonomic work tasks, work environment and training. The checklist designed to facilitate participatory change processes covered all these areas. The checklist developed to describe feasible workplace actions was suitable for integration with comprehensive safety and health management systems and offered valuable opportunities for improving working time arrangements and job content together.

  20. Improving operational safety management through probabilistic safety assessment on personal computers

    International Nuclear Information System (INIS)

    1988-10-01

    The Technical Committee Meeting considered the current effort in the implementation and use of PSA information for day-to-day operational safety management on Personal Computers. Due to the very recent development of the necessary hardware and software for Personal Computers, the application of PSA information for day-to-day operational safety management on PCs is essentially still in a pioneering stage. There is at present only one such system for end users existing, the PRISIM (Plant Risk Status Information Management) program for which a limited practical application experience is available. Others are still in the development stage. The main aim of the Technical Committee Meeting was to discuss the present status of PSA based systems for operational safety management support on small computers, to consider practical aspects when implementing these systems into a nuclear installation and to address problems related to the further work in the area. A separate abstract was prepared for the summary of the Technical Committee Meeting and for the 8 papers presented by the participants. Refs, figs and tabs