WorldWideScience

Sample records for safety measures inspecting

  1. Job safety in magnetic particle inspection

    International Nuclear Information System (INIS)

    Gallardo, Gerald S.

    2007-01-01

    Safety in the workplace is utmost importance to both employees and employers. It is a shared responsibility to make safety a way of life. General precautions to be exercised when performing magnetic particle inspection include consideration of exposure to oils, paste, and electrical current. It is important that the following minimum safety requirement to be observed when performing magnetic particle inspection. Always consult the Material Safety Data Sheet (MSDS) for the specific product or products you will be using to insure all necessary safety precautions are taken for potential health effects, first aid, fire hazard, accidental release measures, exposure controls, personal protection, physical properties,stability, reactivity toxicological information, disposal and transportation. (author)

  2. 3D optical measuring technologies for dimensional inspection

    International Nuclear Information System (INIS)

    Chugui, Yu V

    2005-01-01

    The results of the R and D activity of TDI SIE SB RAS in the field of the 3D optical measuring technologies and systems for noncontact 3D optical dimensional inspection applied to atomic and railway industry safety problems are presented. This activity includes investigations of diffraction phenomena on some 3D objects, using the original constructive calculation method, development of hole inspection method on the base of diffractive optical elements. Ensuring the safety of nuclear reactors and running trains as well as their high exploitation reliability takes a noncontact inspection of geometrical parameters of their components. For this tasks we have developed methods and produced the technical vision measuring systems LMM, CONTROL, PROFILE, and technologies for non-contact 3D dimensional inspection of grid spacers and fuel elements for the nuclear reactor VVER-1000 and VVER-440, as well as automatic laser diagnostic system COMPLEX for noncontact inspection of geometrical parameters of running freight car wheel pairs. The performances of these systems and the results of the industrial testing at atomic and railway companies are presented

  3. Safety guidance and inspection program for particle accelerator

    Energy Technology Data Exchange (ETDEWEB)

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

    2001-03-15

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

  4. The road safety audit and road safety inspection.

    NARCIS (Netherlands)

    2007-01-01

    A road safety audit (RSA) and a road safety inspection (RSI) are used to test the safety level of the road infrastructure. The RSA tests the design of new roads or the reconstruction of existing roads, whereas the RSI is used for testing existing roads. An RSA, therefore, aims to 'improve' the road

  5. Laser Safety Inspection Criteria

    International Nuclear Information System (INIS)

    Barat, K.

    2005-01-01

    A responsibility of the Laser Safety Officer (LSO) is to perform laser audits. The American National Standard Z136.1 Safe Use of Lasers references this requirement through several sections. One such reference is Section 1.3.2.8, Safety Features Audits, ''The LSO shall ensure that the safety features of the laser installation facilities and laser equipment are audited periodically to assure proper operation''. The composition, frequency and rigor of that inspection/audit rests in the hands of the LSO. A common practice for institutions is to develop laser audit checklists or survey forms It is common for audit findings from one inspector or inspection to the next to vary even when reviewing the same material. How often has one heard a comment, ''well this area has been inspected several times over the years and no one ever said this or that was a problem before''. A great number of audit items, and therefore findings, are subjective because they are based on the experience and interest of the auditor to particular items on the checklist. Beam block usage, to one set of eyes might be completely adequate, while to another, inadequate. In order to provide consistency, the Laser Safety Office of the National Ignition Facility Directorate has established criteria for a number of items found on the typical laser safety audit form. The criteria are distributed to laser users. It serves two broad purposes; first, it gives the user an expectation of what will be reviewed by an auditor. Second, it is an opportunity to explain audit items to the laser user and thus the reasons for some of these items, such as labelling of beam blocks

  6. 7 CFR 2.53 - Administrator, Food Safety and Inspection Service.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 1 2010-01-01 2010-01-01 false Administrator, Food Safety and Inspection Service. 2... Secretary for Food Safety § 2.53 Administrator, Food Safety and Inspection Service. (a) Delegations... to the Administrator, Food Safety and Inspection Service: (1) Exercise the functions of the Secretary...

  7. Discussion on unpacking inspection of imported civil nuclear safety equipment

    International Nuclear Information System (INIS)

    Li Chan; Zhang Wenguang; Li Maolin; Li Shixin; Jin Gang; Yao Yuan

    2014-01-01

    This paper introduces the purpose, contents, process and requirements of unpacking inspection which is the second stage of safety inspection of imported civil nuclear safety equipment, expresses review key points on application documents of unpacking inspection, processes of witness on-the-spot before unpacking inspection outside the civil nuclear facilities by the test agency, discusses understanding of unpacking inspection, supervision of manufacture, inspection prior to shipment, supervision of loading and acceptance by the unit operating civil nuclear facilities, reports on unpacking inspection. Some suggestions on reinforcing the unpacking inspection in China are concerned. (authors)

  8. Safety inspection guide, Mod III (a systematic approach to conducting a safety inspection)

    International Nuclear Information System (INIS)

    Davidson, J.E.

    1977-06-01

    This guide was developed as a comprehensive/systematic approach to the problem of performing a safety inspection. Five basic sections (categories) are considered in the guide: physical work place; machines/mechanical equipment; hazardous materials/processes/environments; energy sources; and management hazard . control factors. The basic concept is that one starts evaluating hazard potentials from the physical work place and continues considering other elements as they are added to the physical work place. This approach provides a better understanding of the interfaces of each section to the entire group. The guide is supported by an Area Safety Inspection Result form to record defects or conditions found, the evaluation (best estimate) of the urgency or priority for correcting deficiencies or areas of noncompliance, and the status of corrective action. Additionally, the guide serves as an educational tool in accident prevention for supervisors and employees

  9. Development of inspection safety evaluation technology

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, Seok Chul; Yoon, Yeo Chang; Kim, Jong Soo; Lee, Tae Young; Kim, Chang Ryol; Lee, Hyung Sub; Kim, Jong Soo

    1995-12-01

    The purpose of this project is to protection nation inspector`s over exposure from radiation that can be occurred by inspection activity at nuclear facilities and its environment, and to ensure the safety of inspection activity at the nuclear facilities. To effectively carry out the domestic inspection task to be enforced from 1996, the evaluation for special radiation exposure rate of nuclear facilities, air and surface contamination level, and measurement and monitoring of water contamination level were made to determine whether these measured values exceeded permissible limitations, and to protect the inspector`s over exposure from radiation at domestic nuclear facilities. Management of inspector`s exposure was carried out under assistance of the Department of Health Physics. Performance tests of two gamma detectors, one neutron detector, alpha and beta detector, and gamma spectroscopy analyzer were carried out to control dose on extremity, the characteristic test for extremity dosimeter was carried out and the theoretical calculation of gamma dose conversion factors based on ANSI N13.32 standard was performed. Under the 93+2 program, IAEA began to recognize the necessity of environmental observation technology development of air-borne particulates travelled from long distance location. Associated with the necessity of this technology development, a proposal of international joint research for development of the special radiation measurement and analysis has been prepared. (author). 21 tabs., 24 figs., 20 refs.

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

    International Nuclear Information System (INIS)

    Billington, A.; Monette, P.

    2001-01-01

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

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

    International Nuclear Information System (INIS)

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

    2000-01-01

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

  12. Laser Safety Inspection Criteria

    International Nuclear Information System (INIS)

    Barat, K

    2005-01-01

    A responsibility of the Laser Safety Officer (LSO) is to perform laser safety audits. The American National Standard Z136.1 Safe use of Lasers references this requirement in several sections: (1) Section 1.3.2 LSO Specific Responsibilities states under Hazard Evaluation, ''The LSO shall be responsible for hazards evaluation of laser work areas''; (2) Section 1.3.2.8, Safety Features Audits, ''The LSO shall ensure that the safety features of the laser installation facilities and laser equipment are audited periodically to assure proper operation''; and (3) Appendix D, under Survey and Inspections, it states, ''the LSO will survey by inspection, as considered necessary, all areas where laser equipment is used''. Therefore, for facilities using Class 3B and or Class 4 lasers, audits for laser safety compliance are expected to be conducted. The composition, frequency and rigueur of that inspection/audit rests in the hands of the LSO. A common practice for institutions is to develop laser audit checklists or survey forms. In many institutions, a sole Laser Safety Officer (LSO) or a number of Deputy LSO's perform these audits. For that matter, there are institutions that request users to perform a self-assessment audit. Many items on the common audit list and the associated findings are subjective because they are based on the experience and interest of the LSO or auditor in particular items on the checklist. Beam block usage is an example; to one set of eyes a particular arrangement might be completely adequate, while to another the installation may be inadequate. In order to provide more consistency, the National Ignition Facility Directorate at Lawrence Livermore National Laboratory (NIF-LLNL) has established criteria for a number of items found on the typical laser safety audit form. These criteria are distributed to laser users, and they serve two broad purposes: first, it gives the user an expectation of what will be reviewed by an auditor, and second, it is an

  13. 49 CFR 174.9 - Safety and security inspection and acceptance.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 2 2010-10-01 2010-10-01 false Safety and security inspection and acceptance. 174... RAIL General Requirements § 174.9 Safety and security inspection and acceptance. (a) At each location... not conform to the safety and security requirements of this subchapter, the carrier may not forward or...

  14. Technological progress, safety, and the guardian role of inspection

    Energy Technology Data Exchange (ETDEWEB)

    Critchley, O H

    1981-08-01

    Technological innovation is accompanied by unforeseen human consequences as well as benefits, and progress has produced a public awareness of the potential for hazards that has led to efficient safety-inspection procedures. Because no safety procedure is foolproof, the public learns to tolerate certain levels of risk from technology if it concludes that the benefits are worthwhile. The perception of values often transcends simple cost/benefit analysis. Safety technology and regulation developed during the past 50 years has benefited from earlier disastrous accidents enough to give the nuclear power industry an unprecedented safety record. Efforts to understand and anticipate human error have refined the role of inspection without achieving absolute reliability. Well-directed inspections that accept human fallibility will achieve more than design and organizational improvements. 42 references. (DCK)

  15. Safety inspections to TRIGA reactors

    International Nuclear Information System (INIS)

    Byszewski, W.

    1988-01-01

    The operational safety advisory programme was created to provide useful assistance and advice from an international perspective to research reactor operators and regulators on how to enhance operational safety and radiation protection on their reactors. Safety missions cover not only the operational safety of reactors themselves, but also the safety of associated experimental loops, isotope laboratories and other experimental facilities. Safety missions are also performed on request in other Member States which are interested in receiving impartial advice and assistance in order to enhance the safety of research reactors. The results of the inspections have shown that in some countries there are problems with radiation protection practices and nuclear safety. Very often the Safety Analysis Report is not updated, regulatory supervision needs clarification and improvement, maintenance procedures should be more formalised and records and reports are not maintained properly. In many cases population density around the facility has increased affecting the validity of the original safety analysis

  16. Maintenance, surveillance and in-service inspection in nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2002-01-01

    Effective maintenance, surveillance and in-service inspection (MS and I) are essential for the safe operation of a nuclear power plant. The objective of this Safety Guide is to provide recommendations and guidance for MS and I activities to ensure that SSCs important to safety are available to perform their functions in accordance with the assumptions and intent of the design. This Safety Guide covers the organizational and procedural aspects of MS and I. However, it does not give detailed technical advice in relation to particular items of plant equipment, nor does it cover inspections made for and/or by the regulatory body. This Safety Guide provides recommendations and guidance for preventive and remedial measures, including testing, surveillance and in-service inspection, that are necessary to ensure that all plant structures, systems and components (SSCs) important to safety are capable of performing as intended. This Safety Guide covers measures for fulfilling the organizational and administrative requirements for: establishing and implementing schedules for preventive and predictive maintenance, repairing defective plant items, selecting and training personnel, providing related facilities and equipment, procuring stores and spare parts, and generating, collecting and retaining maintenance records for establishing and implementing an adequate feedback system for information on maintenance. MS and I should be subject to quality assurance in relation to all aspects important to safety. Quality assurance has been dealt with in detail in other IAEA safety standards and is covered here only in specific instances, for emphasis. In Section 2, a concept of MS and I is presented and the interrelationship between maintenance, surveillance and inspection is discussed. Section 3 concerns the functions and responsibilities of different organizations involved in MS and I activities. Section 4 provides recommendations and guidance on such organizational aspects as

  17. Maintenance, surveillance and in-service inspection in nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2005-01-01

    Effective maintenance, surveillance and in-service inspection (MS and I) are essential for the safe operation of a nuclear power plant. The objective of this Safety Guide is to provide recommendations and guidance for MS and I activities to ensure that SSCs important to safety are available to perform their functions in accordance with the assumptions and intent of the design. This Safety Guide covers the organizational and procedural aspects of MS and I. However, it does not give detailed technical advice in relation to particular items of plant equipment, nor does it cover inspections made for and/or by the regulatory body. This Safety Guide provides recommendations and guidance for preventive and remedial measures, including testing, surveillance and in-service inspection, that are necessary to ensure that all plant structures, systems and components (SSCs) important to safety are capable of performing as intended. This Safety Guide covers measures for fulfilling the organizational and administrative requirements for: establishing and implementing schedules for preventive and predictive maintenance, repairing defective plant items, selecting and training personnel, providing related facilities and equipment, procuring stores and spare parts, and generating, collecting and retaining maintenance records for establishing and implementing an adequate feedback system for information on maintenance. MS and I should be subject to quality assurance in relation to all aspects important to safety. Quality assurance has been dealt with in detail in other IAEA safety standards and is covered here only in specific instances, for emphasis. In Section 2, a concept of MS and I is presented and the interrelationship between maintenance, surveillance and inspection is discussed. Section 3 concerns the functions and responsibilities of different organizations involved in MS and I activities. Section 4 provides recommendations and guidance on such organizational aspects as

  18. Regulatory inspection activities related to inspection planning, plant maintenance and assessment of safety. Proceedings of an international workshop

    International Nuclear Information System (INIS)

    Van Binnebeek, J.J.; Aubrey, Richard; Grandame, Melvyn; Aro, Ilari; Balloffet, Yves; Klonk, Hartmut; Manzella, Pietro; Koizumi, Hiroyoshi; Bouvrie, E.C. des; Forsberg, Staffan; Lang, Hans-Guenter; Mehew, Robert; Warren, Thomas; Woodhouse, Paul; Gallo, Robert M.; Campbell, Rob; )

    1997-01-01

    The NEA Committee on Nuclear Regulatory Activities (CNRA) believes that an essential factor in ensuring the safety of nuclear installations is the continuing exchange and analysis of technical information and data. To facilitate this exchange the Committee has established Working Groups and Groups of Experts in specialised topics. CNRA believes that safety inspections are a major element in the regulatory authority's efforts to ensure the safe operation of nuclear facilities. Considering the importance of these issues, the Committee has established a special Working Group on Inspection Practices (WGIP). The purpose of WGIP, is to facilitate the exchange of information and experience related to regulatory safety inspections between CNRA Member countries. This was the 3. international workshop held by the WGIP on regulatory inspection activities. The focus of this workshop was on 3 main topics; Inspection Planning, Plant Maintenance and Assessment of Safety. This document presents the proceedings from the workshop, including: workshop programme, results and conclusions, papers and presentations and the list of participants. The main purpose of the Workshop is to provide a forum of exchange of information on the regulatory inspection activities

  19. Regulatory inspection activities related to inspection planning, plant maintenance and assessment of safety. Proceedings of an international workshop

    Energy Technology Data Exchange (ETDEWEB)

    Van Binnebeek, J. J. [AIB-Vincotte Nuclear - AVN, Avenue du Roi, 157, B-1060 Brussels (Belgium); Aubrey, Richard; Grandame, Melvyn [Atomic Energy Control Board - AECB, P.O. Box 1046, Station B, 280 Slater Street, Ottawa, Ontario K1P 5S9 (Canada); Aro, Ilari [Finnish Centre for Radiation and Nuclear Safety - STUK, P.O. Box 14, FIN-00881 Helsinki (Finland); Balloffet, Yves [DRIRE Rhone Alpes, 146, rue Pierre Corneille, 69426 Lyon CEDEX 03 (France); Klonk, Hartmut [Bundesamt fuer Strahlenschutz - BfS, Federal Office for Radiation Protection, Postbox 10 01 49, 38201 Salzgitter 1 (Germany); Manzella, Pietro [A.N.P.A., Via V. Brancati, 48, 1-00144 Roma EUR (Italy); Koizumi, Hiroyoshi [Tech. Stan. Dept. - JAPEIC, Shin-Toranomon Bldg., 1-5-11, Akasaka, Minato-ku, Tokyo 107 (Japan); Bouvrie, E.C. des [Ministry of Social Affairs and Employment, Nuclear Safety Dept. KFD, P.O. Box 90804, 2509 LV The Hague (Netherlands); Forsberg, Staffan [Swedish Nuclear Power Inspectorate - SKI, Klarabergsviadukten 90, S-10658 Stockholm (Sweden); Lang, Hans-Guenter [Section Plant Coordination and Inspection, Swiss Federal Nuclear Safety Inspectorate - HSK, CH-5232 Villigen-HSK (Switzerland); Mehew, Robert; Warren, Thomas; Woodhouse, Paul [Health and Safety Executive - NII, St. Peter' s House, Balliol Road, Bootle, Merseyside L20 3LZ (United Kingdom); Gallo, Robert M. [Special Inspection Branch, US Nuclear Regulatory Commission - US NRC, Mail Stop 0-9A1, Washington, DC 20555 (United States); Campbell, Rob [International Atomic Energy Agency - IAEA, P.O. Box 100, A-1400 Vienna (International Atomic Energy Agency (IAEA))

    1997-07-01

    The NEA Committee on Nuclear Regulatory Activities (CNRA) believes that an essential factor in ensuring the safety of nuclear installations is the continuing exchange and analysis of technical information and data. To facilitate this exchange the Committee has established Working Groups and Groups of Experts in specialised topics. CNRA believes that safety inspections are a major element in the regulatory authority's efforts to ensure the safe operation of nuclear facilities. Considering the importance of these issues, the Committee has established a special Working Group on Inspection Practices (WGIP). The purpose of WGIP, is to facilitate the exchange of information and experience related to regulatory safety inspections between CNRA Member countries. This was the 3. international workshop held by the WGIP on regulatory inspection activities. The focus of this workshop was on 3 main topics; Inspection Planning, Plant Maintenance and Assessment of Safety. This document presents the proceedings from the workshop, including: workshop programme, results and conclusions, papers and presentations and the list of participants. The main purpose of the Workshop is to provide a forum of exchange of information on the regulatory inspection activities.

  20. Promoting radiation protection and safety for X-ray inspection systems

    International Nuclear Information System (INIS)

    Maharaj, Harri P.

    2008-01-01

    This paper aims to present a regulatory perspective on radiation protection and safety relevant to facilities utilizing baggage X-ray inspection systems. Over the past several years there has been rapid growth in the acquisition and utilization of X-ray tube based inspection systems for security screening purposes worldwide. In addition to ensuring compliance with prescribed standards applicable to such X-ray systems, facilities subject to federal jurisdiction in Canada are required to comply with established codes of practice, which, not only are in accordance with occupational health and safety legislation but also are consistent with international guidance. Overall, these measures are aimed at reducing radiation risks and adverse health effects. Data, acquired in the past several years in a number of facilities through various instruments, namely, monitoring and surveillance, radiation safety audits, onsite evaluations, device registration processes and information developed, were considered in conjunction with detrimental traits. Changes are necessary to reduce radiation and safety risks from both an ALARA point of view and an accountability perspective. Establishing, developing, implementing and following a radiation protection program is warranted and advocated. Minimally, such a program shall be managed by a radiation safety officer. It shall promote and sustain a radiation safety culture in the workplace; shall ensure properly qualified individuals operate and service the X-ray systems in accordance with established and authorized procedures; and shall incorporate data recording and life cycle management principles. Such a program should be the norm for a facility that utilizes baggage X-ray inspection systems for security purposes, and it shall be subject to continuous regulatory oversight. (author)

  1. Safety inspections in construction sites: A systems thinking perspective.

    Science.gov (United States)

    Saurin, Tarcisio Abreu

    2016-08-01

    Although safety inspections carried out by government officers are important for the prevention of accidents, there is little in-depth knowledge on their outcomes and processes leading to these. This research deals with this gap by using systems thinking (ST) as a lens for obtaining insights into safety inspections in construction sites. Thirteen case studies of sites with prohibited works were carried out, discussing how four attributes of ST were used in the inspections. The studies were undertaken over 6 years, and sources of evidence involved participant observation, direct observations, analysis of documents and interviews. Two complementary ways for obtaining insights into inspections, based on ST, were identified: (i) the design of the study itself needs to be in line with ST; and (ii) data collection and analysis should focus on the agents involved in the inspections, the interactions between agents, the constraints and opportunities faced by agents, the outcomes of interactions, and the recommendations for influencing interactions. Copyright © 2015 Elsevier Ltd. All rights reserved.

  2. Department of Agriculture, Food Safety and Inspection Service

    Science.gov (United States)

    ... Standard Forms FSIS United States Department of Agriculture Food Safety and Inspection Service About FSIS District Offices Careers Contact Us Ask ... Reports Fact Sheets Food Defense and Emergency Response Food Safety Education FSIS ... Assistance Contact Centers Cooperative Agreements Email Subscription ...

  3. Remote Inspection, Measurement and Handling for LHC

    CERN Document Server

    Kershaw, K; Coin, A; Delsaux, F; Feniet, T; Grenard, J L; Valbuena, R

    2007-01-01

    Personnel access to the LHC tunnel will be restricted to varying extents during the life of the machine due to radiation, cryogenic and pressure hazards. The ability to carry out visual inspection, measurement and handling activities remotely during periods when the LHC tunnel is potentially hazardous offers advantages in terms of safety, accelerator down time, and costs. The first applications identified were remote measurement of radiation levels at the start of shut-down, remote geometrical survey measurements in the collimation regions, and remote visual inspection during pressure testing and initial machine cool-down. In addition, for remote handling operations, it will be necessary to be able to transmit several real-time video images from the tunnel to the control room. The paper describes the design, development and use of a remotely controlled vehicle to demonstrate the feasibility of meeting the above requirements in the LHC tunnel. Design choices are explained along with operating experience to-dat...

  4. Post-earthquake building safety inspection: Lessons from the Canterbury, New Zealand, earthquakes

    Science.gov (United States)

    Marshall, J.; Jaiswal, Kishor; Gould, N.; Turner, F.; Lizundia, B.; Barnes, J.

    2013-01-01

    The authors discuss some of the unique aspects and lessons of the New Zealand post-earthquake building safety inspection program that was implemented following the Canterbury earthquake sequence of 2010–2011. The post-event safety assessment program was one of the largest and longest programs undertaken in recent times anywhere in the world. The effort engaged hundreds of engineering professionals throughout the country, and also sought expertise from outside, to perform post-earthquake structural safety inspections of more than 100,000 buildings in the city of Christchurch and the surrounding suburbs. While the building safety inspection procedure implemented was analogous to the ATC 20 program in the United States, many modifications were proposed and implemented in order to assess the large number of buildings that were subjected to strong and variable shaking during a period of two years. This note discusses some of the key aspects of the post-earthquake building safety inspection program and summarizes important lessons that can improve future earthquake response.

  5. Safety assessment plans for authorization and inspection of radiation sources

    International Nuclear Information System (INIS)

    2002-05-01

    The objective of this TECDOC is to enhance the efficacy, quality and efficiency of the whole regulatory process. It provides advice on good practice administrative procedures for the regulatory process for preparation of applications, granting of authorizations, inspection, and enforcement. It also provides information on the development and use of standard safety assessment plans for authorization and inspection. The plans are intended to be used in conjunction with more detailed advice related to specific practices. In this sense, this TECDOC provides advice on a systematic approach to evaluations of protection and safety while other IAEA Safety Guides assist the user to distinguish between the acceptable and the unacceptable. This TECDOC covers administrative advice to facilitate the regulatory process governing authorization and inspection. It also covers the use of standard assessment and inspection plans and provides simplified plans for the more common, well established uses of radiation sources in medicine and industry, i.e. sources for irradiation facilities, industrial radiography, well logging, industrial gauging, unsealed sources in industry, X ray diagnosis, nuclear medicine, teletherapy and brachytherapy

  6. Safety assessment plans for authorization and inspection of radiation sources

    International Nuclear Information System (INIS)

    1999-09-01

    The objective of this TECDOC is to enhance the efficacy, quality and efficiency of the whole regulatory process. It provides advice on good practice administrative procedures for the regulatory process for preparation of applications, granting of authorizations, inspection, and enforcement. It also provides information on the development and use of standard safety assessment plans for authorization and inspection. The plans are intended to be used in conjunction with more detailed advice related to specific practices. In this sense, this TECDOC provides advice on a systematic approach to evaluations of protection and safety while other IAEA Safety Guides assist the user to distinguish between the acceptable and the unacceptable. This TECDOC covers administrative advice to facilitate the regulatory process governing authorization and inspection. It also covers the use of standard assessment and inspection plans and provides simplified plans for the more common, well established uses of radiation sources in medicine and industry, i.e. sources for irradiation facilities, industrial radiography, well logging, industrial gauging, unsealed sources in industry, X ray diagnosis, nuclear medicine, teletherapy and brachytherapy

  7. 5 CFR 8301.104 - Additional rules for employees of the Food Safety and Inspection Service.

    Science.gov (United States)

    2010-01-01

    ... Food Safety and Inspection Service. 8301.104 Section 8301.104 Administrative Personnel DEPARTMENT OF....104 Additional rules for employees of the Food Safety and Inspection Service. Any employee of the Food Safety and Inspection Service not otherwise required to obtain approval for outside employment under...

  8. Regulatory inspection of nuclear facilities and enforcement by the regulatory body. Safety guide

    International Nuclear Information System (INIS)

    2002-01-01

    The purpose of this Safety Guide is to provide recommendations for regulatory bodies on the inspection of nuclear facilities, regulatory enforcement and related matters. The objective is to provide the regulatory body with a high level of confidence that operators have the processes in place to ensure compliance and that they do comply with legal requirements, including meeting the safety objectives and requirements of the regulatory body. However, in the event of non-compliance, the regulatory body should take appropriate enforcement action. This Safety Guide covers regulatory inspection and enforcement in relation to nuclear facilities such as: enrichment and fuel manufacturing plants; nuclear power plants; other reactors such as research reactors and critical assemblies; spent fuel reprocessing plants; and facilities for radioactive waste management, such as treatment, storage and disposal facilities. This Safety Guide also covers issues relating to the decommissioning of nuclear facilities, the closure of waste disposal facilities and site rehabilitation. Section 2 sets out the objectives of regulatory inspection and enforcement. Section 3 covers the management of regulatory inspections. Section 4 covers the performance of regulatory inspections, including internal guidance, planning and preparation, methods of inspection and reports of inspections. Section 5 deals with regulatory enforcement actions. Section 6 covers the assessment of regulatory inspections and enforcement activities. The Appendix provides further details on inspection areas for nuclear facilities

  9. Flamanville 3 EPR, Safety Assessment and On-site Inspections

    International Nuclear Information System (INIS)

    Piedagnel, Corinne; Tarallo, Francois; Monnot, Bernard

    2011-01-01

    As a Technical Support Organisation of the French Safety Authority (ASN), the IRSN carries out the safety assessment of EPR project design and participates in the ASN inspections performed at the construction site and in factories. The design assessment consists in defining the safety functions which should be ensured by civil structures, evaluating the EPR Technical Code for Civil works (ETC-C) in which EdF has defined design criteria and construction rules, and carrying out a detailed assessment of a selection of safety-related structures. Those detailed assessments do not consist of a technical control but of an analysis whose objectives are to ensure that design and demonstrations are robust, in accordance with safety and regulatory rules. Most assessments led IRSN to ask EdF to provide additional justification sometimes involving significant modifications. In the light of those complementary justifications and modifications, IRSN concluded that assessments carried out on design studies were globally satisfactory. The participation of IRSN to the on-site inspections led by ASN is a part of the global control of the compliance of the reactor with its safety objectives. For that purpose IRSN has defined a methodology and an inspection program intended to ASN: based on safety functions associated with civil works (confinement and resistance to aggressions), the corresponding behaviour requirements are identified and linked to a list of main civil works elements. During the inspections, deviations to the project's technical specifications or to the rules of the art were pointed out by IRSN. Those deviations cover various items, such as concrete fabrication, concrete pouring methodology, lack of reinforcement in some structures, unadapted welding procedures of the containment leak-tight steel liner and unsatisfactory treatment of concreting joints. The analysis of those problems has revealed flaws in the organisation of the contractors teams together with an

  10. Strategic environmental safety inspection for the National disposal program. Description of the inspection volume. Documentation for the scoping team

    International Nuclear Information System (INIS)

    2015-01-01

    The Strategic environmental safety inspection for the National disposal program covers the following topics: Legal framework: determination of the requirement for an environmental inspection program, coordination of the scoping team into the overall context; environmental targets; approach for assessment and evaluation of environmental impact, description of the inspection targets for the strategic environmental inspection; consideration of alternatives.

  11. Generic safety insights for inspection of boiling water reactors

    International Nuclear Information System (INIS)

    Higgins, J.C.; Taylor, J.H.; Fresco, A.N.; Hillman, B.M.

    1987-01-01

    As the number of operating nuclear power plants (NPP) increases, safety inspection has increased in importance. However, precisely what is important, and what is not important? What should one focus inspection efforts on. Over the last two years Probabilistic Risk Assessment (PR) techniques have been developed to aid in the inspection process. Broad interest in generic PRA-based methods has arisen in the past year, since only about 25% of the US nuclear power plants have completed PRAs, and also, inspectors want PRA-based tools for these plants. This paper describes the BNL program to develop generic BWR PRA-based inspection insights or inspection guidance designed to be applied to plants without PRAs

  12. [Recommendations for inspections of the French nuclear safety authority].

    Science.gov (United States)

    Rousse, C; Chauvet, B

    2015-10-01

    The French nuclear safety authority is responsible for the control of radiation protection in radiotherapy since 2002. Controls are based on the public health and the labour codes and on the procedures defined by the controlled health care facility for its quality and safety management system according to ASN decision No. 2008-DC-0103. Inspectors verify the adequacy of the quality and safety management procedures and their implementation, and select process steps on the basis of feedback from events notified to ASN. Topics of the inspection are communicated to the facility at the launch of a campaign, which enables them to anticipate the inspectors' expectations. In cases where they are not physicians, inspectors are not allowed to access information covered by medical confidentiality. The consulted documents must therefore be expunged of any patient-identifying information. Exchanges before the inspection are intended to facilitate the provision of documents that may be consulted. Finally, exchange slots between inspectors and the local professionals must be organized. Based on improvements achieved by the health care centres and on recommendations from a joint working group of radiotherapy professionals and the nuclear safety authority, changes will be made in the control procedure that will be implemented when developing the inspection program for 2016-2019. Copyright © 2015. Published by Elsevier SAS.

  13. Occupational health and safety inspection of the Ranger Uranium Mine

    International Nuclear Information System (INIS)

    Rosen, R.

    1987-04-01

    The principal purpose of the inspection was to assess all aspects of occupational health and safety at the Ranger Uranium Mine. A major objective was to identify actual and potential hazards under normal and abnormal conditions, particularly in relation to those topics about which the unions had expressed some concern. An assessment was made of current safety policies, procedures and practices at the site; and, as far as practicable, those tasks which involved risks to workers were identified. The results and recommendations of the inspection are contained in this report

  14. [Legislation and inspection for the health and safety of workers. Efficacy and limits].

    Science.gov (United States)

    Tozzi, G A

    2009-01-01

    To provide information regarding Occupational Health and Safety (OHS) Inspections in Europe. The dynamics that are transforming regulatory subsystems and complementary inspection services are described. Simplification initiatives, the limits and difficulties of applying the different models of Health and Safety Management Systems are discussed. Examples are given on how to evaluate legislation and technical standards during planning and enforcement. Different approaches for studying characteristics, methodologies and efficacy in practice of OHS Inspection are provided. Targeted inspections need to respond to the needs of enterprises and workers. Impartiality must be guaranteed and workers' participation should be facilitated.

  15. Spectroscopic imaging technologies for online food safety and sanitation inspection

    Science.gov (United States)

    The Environmental Microbial and Food Safety Laboratory, ARS, USDA is one of the leading groups for the development of optoelectronic sensing technologies and methodologies for food quality, safety, and sanitation inspection. High throughput hyperspectral and multispectral imaging techniques use Ram...

  16. The French nuclear safety authority's experience with radioactive transport inspection

    International Nuclear Information System (INIS)

    Jacob, E.; Aguilar, J.

    2004-01-01

    About 300,000 radioactive material packages are transported annually in France. Most consist of radioisotopes for medical, pharmaceutical or industrial use. On the other hand, the nuclear industry deals with the transport of fuel cycle materials (uranium, fuel assemblies, etc.) and waste from power plants, reprocessing plants and research centers. France is also a transit country for shipments such as spent fuel packages from Switzerland or Germany, which are bound for Sellafield in Great Britain. The French nuclear safety authority (DGSNR: Directorate General for Nuclear Safety and Radioprotection) has been responsible since 1997 for the safety of radioactive material transport. This paper presents DGNSR's experience with transport inspection: a feedback of key points based on 300 inspections achieved during the past five years is given

  17. Regulatory inspection practices for industrial safety (electrical, mechanical, material handling and conventional aspects)

    International Nuclear Information System (INIS)

    Agarwal, K.

    2017-01-01

    Regulatory Inspection (RI) of BARC facilities and projects are carried out under the guidance of BARC Safety Council (BSC) Secretariat. Basically facilities and projects have been divided into two board categories viz. radiological facilities and non-radiological facilities. The Rls of radiological facilities should be carried out under OPSRC and of non-radiological facilities under CFSRC. Periodicity of inspection shall be at least once in a year. The RI of projects is carried out under concerned DSRC. RI practices with industrial safety which includes electrical, mechanical, material handling and conventional aspect for these facilities starts with check lists. The inspection areas are prepared in the form of checklists which includes availability of approved documents, compliance status of previous RIT and various safety committee's recommendations, radiological status of facilities, prompt reporting of safety related unusual occurrences, major incident, site visit for verification of actual status of system/plant. The practices for inspection in the area of electrical safety shall include checking of maintenance procedure for all critical class IV system equipment's such as HT panel, LT panel, transformer and motors. Load testing of Class III system such as D.G. set etc. shall be carried out as technical specification surveillance schedule. Status of aviation lights, number of qualified staff, availability of qualified staff etc. shall be form of inspection

  18. Ship inspection strategies: effects on maritime safety and environmental protection

    NARCIS (Netherlands)

    Heij, C.; Bijwaard, G.E.; Knapp, S.

    2011-01-01

    Global trade largely depends on maritime transport, and appropriate ships are needed to protect cargo but to minimize environmental damage and to this end, flag and port state authorities expend considerable effort in ship safety inspections. This paper investigates the safety gains of current

  19. Assisting New York Dairy Farms with Preparing for OSHA Safety Inspections.

    Science.gov (United States)

    Tinc, Pamela J; Carrabba, Jim; Meyerhoff, Anna; Horsman, Melissa

    2018-01-01

    In 2013, the Occupational Safety and Health Administration announced a Local Emphasis Program targeted at New York farmers. This program involved random inspections of dairy farms across the state. This article provides an overview of the efforts made in New York to prepare farmers for these inspections. As a result of this program launch, several safety services offered by the New York Center for Agricultural Medicine and Health were significantly impacted, and required expansion and modification in order to meet the needs of New York farmers.

  20. Natural Gas Vehicle Cylinder Safety, Training and Inspection Project

    Energy Technology Data Exchange (ETDEWEB)

    Hank Seiff

    2008-12-31

    Under the auspices of the National Energy Technology Laboratory and the US Department of Energy, the Clean Vehicle Education Foundation conducted a three-year program to increase the understanding of the safe and proper use and maintenance of vehicular compressed natural gas (CNG) fuel systems. High-pressure fuel systems require periodic inspection and maintenance to insure safe and proper operation. The project addressed the needs of CNG fuel containers (cylinders) and associated high-pressure fuel system components related to existing law, codes and standards (C&S), available training and inspection programs, and assured coordination among vehicle users, public safety officials, fueling station operators and training providers. The program included a public and industry awareness campaign, establishment and administration of a cylinder inspector certification training scholarship program, evaluation of current safety training and testing practices, monitoring and investigation of CNG vehicle incidents, evaluation of a cylinder recertification program and the migration of CNG vehicle safety knowledge to the nascent hydrogen vehicle community.

  1. Ship Inspection Strategies: Effects on Maritime Safety and Environmental Protection

    NARCIS (Netherlands)

    C. Heij (Christiaan); G.E. Bijwaard (Govert); S. Knapp (Sabine)

    2010-01-01

    textabstractGlobal trade depends for a large part on maritime transport, and safe ships are needed not only to protect precious cargo but also to prevent environmental damage. Flag state and port state authorities spend much effort in ship safety inspections to ensure a minimum safety level and to

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

    Science.gov (United States)

    Sparer, Emily; Dennerlein, Jack

    2013-01-01

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

  3. LHC train control system for autonomous inspections and measurements

    OpenAIRE

    Di Castro, Mario; Baiguera Tambutti, Maria Laura; Gilardoni, Simone; Losito, Roberto; Lunghi, Giacomo; Masi, Alessandro

    2018-01-01

    Intelligent robotic systems are becoming essential for inspection and measurements in harsh environments, such as the European Organization for Nuclear Research (CERN) accelerators complex. Aiming at increasing safety and machine availability, robots can help to perform repetitive or dangerous tasks, reducing the risk for the personnel as the exposure to radiation. The Large Hadron Collider (LHC) tunnel at CERN has been equipped with fail-safe trains on monorail able to perform autonomously d...

  4. Radiation protection and safety guide no. GRPB-G-4: inspection

    International Nuclear Information System (INIS)

    Schandorf, C.; Darko, O.; Yeboah, J.; Osei, E.K.; Asiamah, S.D.

    1995-01-01

    The use of ionizing radiation and radiation sources in Ghana is on the increase due to national developmental efforts in Health Care, Food and Agriculture, Industry, Science and Technology. This regulatory Guide has been developed to assist both the Regulatory Body (Radiation Protection Board) and operating organizations to perform systematic inspections commensurate with the level of hazard associated with the application of radiation sources and radioactive materials. The present Guide applies to the Radiation Protection and Safety inspection and/or audit conducted by the Radiation Protection Board or Radiation Safety Officer. The present Guide is applicable in Ghana and to foreign suppliers of radiation sources. The present Guide applies to notifying person, licensee, or registrant and unauthorized practice

  5. Tank waste remediation system nuclear criticality safety inspection and assessment plan

    International Nuclear Information System (INIS)

    VAIL, T.S.

    1999-01-01

    This plan provides a management approved procedure for inspections and assessments of sufficient depth to validate that the Tank Waste Remediation System (TWRS) facility complies with the requirements of the Project Hanford criticality safety program, NHF-PRO-334, ''Criticality Safety General, Requirements''

  6. Calibration of the CCD photonic measuring system for railway inspection

    Science.gov (United States)

    Popov, D. V.; Ryabichenko, R. B.; Krivosheina, E. A.

    2005-08-01

    Increasing of traffic speed is the most important task in Moscow Metro. Requirements for traffic safety grow up simultaneously with the speed increasing. Currently for track inspection in Moscow Metro is used track measurement car has built in 1954. The main drawbacks of this system are absence of automated data processing and low accuracy. Non-contact photonic measurement system (KSIR) is developed for solving this problem. New track inspection car will be built in several months. This car will use two different track inspection systems and car locating subsystem based on track circuit counting. The KSIR consists of four subsystems: rail wear, height and track gauge measurement (BFSM); rail slump measurement (FIP); contact rail measurement (FKR); speed, level and car locating (USI). Currently new subsystem for wheel flange wear (IRK) is developed. The KSIR carry out measurements in real-time mode. The BFSM subsystem contains 4 matrix CCD cameras and 4 infrared stripe illuminators. The FIP subsystem contains 4 line CCD cameras and 4 spot illuminators. The FKR subsystem contains 2 matrix CCD cameras and 2 stripe illuminators. The IRK subsystem contains 2 CCD cameras and 2 stripe illuminators. Each system calibration was carried out for their adjustment. On the first step KSIR obtains data from photonic sensors which is valued in internal measurement units. Due to the calibration on the second step non-contact system converts the data to metric measurement system.

  7. A strategy for the risk-based inspection of pressure safety valves

    International Nuclear Information System (INIS)

    Chien, C.-H.; Chen, C.-H.; Chao, Y.J.

    2009-01-01

    The purpose of a pressure safety valve (PSV) is to protect the life and safety of pressure vessels in a pressurized system. If a weakened PSV fails to function properly, a catastrophic event might occur if no other protective means are provided. By utilizing the as-received test data and statistical analysis of the aging conditions of PSVs in lubricant process units, a risk-based inspection (RBI) system was developed in this study. First of all, the characteristics of PSV were discussed from the practical viewpoint of engineering inspection and maintenance. The as-received test data, which shows obvious PSV damage, will be separated from the data used in the following statistical analysis. Then, the relationship between the aging conditions and the corresponding PSV parameters was analyzed by using the statistical technique-analysis of variance (ANOVA). Finally, a strategy for semi-quantitative RBI is proposed. Also, a definitive estimated inspection interval for every PSV is suggested. The outcome indicated most of the risks result from a few PSVs, for which the corresponding inspection intervals will be shorter than the 2 years in accordance with relative standards and local government regulations

  8. Noncontacting Optical Measurement And Inspection Systems

    Science.gov (United States)

    Asher, Jeffrey A.; Jackson, Robert L.

    1986-10-01

    Product inspection continues to play a growing role in the improvement of quality and reduction of scrap. Recent emphasis on precision measurements and in-process inspection have been a driving force for the development of noncontacting sensors. Noncontacting sensors can provide long term, unattended use due to the lack of sensor wear. Further, in applications where, sensor contact can damage or geometrically change the part to be measured or inspected, noncontacting sensors are the only technical approach available. MTI is involved in the development and sale of noncontacting sensors and custom inspection systems. This paper will review the recent advances in noncontacting sensor development. Machine vision and fiber optics sensor systems are finding a wide variety of industrial inspection applications. This paper will provide detailed examples of several state-of-the-art applications for these noncontacting sensors.

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

    Science.gov (United States)

    2016-02-01

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

  10. Plant specific safety inspection of German nuclear power plants taking into account the Fukushima-I (Japan) events

    International Nuclear Information System (INIS)

    2011-01-01

    The German Parliament requested (17 March 2011) a comprehensive inspection of German nuclear power plants. For this purpose independent expert commissions should perform a new risk analysis of all German NPPS and nuclear installations with respect to the lessons learned from the Fukushima (Japan) events and other extraordinary damage scenarios. The Reactor safety commission (RSK) was assigned by the German Bundesamt fuer Strahlenschutz to develop a catalogue of requirements for this safety inspection. The contribution summarizes the required inspection volume (status 30.03.2011) including the following events: natural events like earth quakes, floods, weather-based consequences and possible superposition. Additionally the following assumptions have to be considered: event independent postulated common failures or systematic faults, station blackout larger than 2 hours, long-term failure of the auxiliary cooling water supply; aggravating boundary conditions for the performance of emergency measures (non-availability of power supply), hydrogen generation and detonation hazard, restricted personnel availability, non-accessibility due to high radiation levels, impeded technical support from outside. (orig.)

  11. Optical technologies for measurement and inspection

    International Nuclear Information System (INIS)

    Mader, D.L.

    1997-01-01

    Ontario Hydro has benefited from specialized optical measurement techniques such as FRILS (fret replica inspection laser system), which permits in-house inspections of pressure tube replicas and has been estimated to save $2M per year. This paper presents a brief overview of (1) FRILS, (2) OPIT (in-reactor Optical Profilometry Inspection Tool), (3) miniature optical probe for steam generator tubes, (4) laser vibrometer used for end-fitting vibration, and (5) computer vision to recognize the ends of fuel bundles and automatically measure their lengths. (author)

  12. Effect of a Publicly Accessible Disclosure System on Food Safety Inspection Scores in Retail and Food Service Establishments.

    Science.gov (United States)

    Choi, Jihee; Scharff, Robert L

    2017-07-01

    The increased frequency with which people are dining out coupled with an increase in the publicity of foodborne disease outbreaks has led the public to an increased awareness of food safety issues associated with food service establishments. To accommodate consumer needs, local health departments have increasingly publicized food establishments' health inspection scores. The objective of this study was to estimate the effect of the color-coded inspection score disclosure system in place since 2006 in Columbus, OH, by controlling for several confounding factors. This study incorporated cross-sectional time series data from food safety inspections performed from the Columbus Public Health Department. An ordinary least squares regression was used to assess the effect of the new inspection regime. The introduction of the new color-coded food safety inspection disclosure system increased inspection scores for all types of establishments and for most types of inspections, although significant differences were found in the degree of improvement. Overall, scores increased significantly by 1.14 points (of 100 possible). An exception to the positive results was found for inspections in response to foodborne disease complaints. Scores for these inspections declined significantly by 10.2 points. These results should be useful for both food safety researchers and public health decision makers.

  13. Periodic inspection for safety of CANDU heat transport piping systems

    International Nuclear Information System (INIS)

    Ellyin, F.

    1979-10-01

    Periodic inspection of heat transport and emergency core cooling piping systems is intended to maintain an adequate level of safety throughout the life of the plant, and to protect plant personnel and the public from the consequences of a failure and release of fission products. This report outlines a rational approach to the periodic inspection based on a fully probabilistic model. It demonstrates the methodology based on theoretical treatment and experimental data whereby the strength of a pressurized pipe or vessel containing a defect could be evaluated. It also shows how the extension of the defect at various lifetimes could be predicted. These relationships are prerequisite for the probabilistic formulation and analysis for the periodic inspection of piping systems

  14. FMCSA safety program effectiveness measurement: intervention model fiscal year 2009.

    Science.gov (United States)

    2013-04-01

    The Federal Motor Carrier Safety Administration (FMCSA), in cooperation with the researcher, has developed an analytic model to measure the effectiveness of roadside inspections and traffic enforcements in terms of crashes avoided, injuries avoided, ...

  15. Cooperative Behaviours with Swarm Intelligence in Multirobot Systems for Safety Inspections in Underground Terrains

    Directory of Open Access Journals (Sweden)

    Chika Yinka-Banjo

    2014-01-01

    Full Text Available Underground mining operations are carried out in hazardous environments. To prevent disasters from occurring, as often as they do in underground mines, and to prevent safety routine checkers from disasters during safety inspection checks, multirobots are suggested to do the job of safety inspection rather than human beings and single robots. Multirobots are preferred because the inspection task will be done in the minimum amount of time. This paper proposes a cooperative behaviour for a multirobot system (MRS to achieve a preentry safety inspection in underground terrains. A hybrid QLACS swarm intelligent model based on Q-Learning (QL and the Ant Colony System (ACS was proposed to achieve this cooperative behaviour in MRS. The intelligent model was developed by harnessing the strengths of both QL and ACS algorithms. The ACS optimizes the routes used for each robot while the QL algorithm enhances the cooperation between the autonomous robots. A description of a communicating variation within the QLACS model for cooperative behavioural purposes is presented. The performance of the algorithms in terms of without communication, with communication, computation time, path costs, and the number of robots used was evaluated by using a simulation approach. Simulation results show achieved cooperative behaviour between robots.

  16. Radioactive waste storage facilities, involvement of AVN in inspection and safety assessment

    International Nuclear Information System (INIS)

    Simenon, R.; Smidts, O.

    2006-01-01

    The legislative and regulatory framework in Belgium for the licensing and the operation of radioactive waste storage buildings are defined by the Royal Decree of 20 July 2001 (hereby providing the general regulations regarding to the protection of the population, the workers and the environment against the dangers of ionising radiation). This RD introduces in the Belgian law the radiological protection and ALARA-policy concepts. The licence of each nuclear facility takes the form of a Royal Decree of Authorization. It stipulates that the plant has to be in conformity with its Safety Analysis Report. This report is however not a public document but is legally binding. Up to now, the safety assessment for radioactive waste storage facilities, which is implemented in this Safety Analysis Report, has been judged on a case-by-case basis. AVN is an authorized inspection organisation to carry out the surveillance of the Belgian nuclear installations and performs hereby nuclear safety assessments. AVN has a role in the nuclear safety and radiation protection during all the phases of a nuclear facility: issuance of licenses, during design and construction phase, operation (including reviewing and formal approval of modifications) and finally the decommissioning. Permanent inspections are performed on a regular basis by AVN, this by a dedicated site inspector, who is responsible for a site of an operator with nuclear facilities. Besides the day-to-day inspections during operation there are also the periodic safety reviews. AVN assesses the methodological approaches for the analyses, reviews and approves the final studies and results. The conditioned waste in Belgium is stored on the Belgoprocess' sites (region Mol-Dessel) for an intermediate period (about 80 years). In the meantime, a well-defined inspection programme is being implemented to ensure that the conditioned waste continues to be stored safely during this temporary storage period. This programme was draw up by

  17. FAA National Aviation Safety Inspection Program. Annual Report FY90

    Science.gov (United States)

    1991-06-01

    This report was undertaken to document, analyze, and place : into national perspective the findings from the 1990 National : Aviation Safety Inspection Program (NASIP). This report is the : fifth in a series of annual reports covering the results of ...

  18. Allegheny County Weights and Measures Inspections

    Data.gov (United States)

    Allegheny County / City of Pittsburgh / Western PA Regional Data Center — Inspections conducted by the Allegheny County Bureau of Weights and Measures. The Bureau inspects weighing and timing devices such as gas pumps, laundromat timers,...

  19. Inspection and enforcement by the regulatory body for nuclear power plants. A safety guide. A publication within the NUSS programme

    International Nuclear Information System (INIS)

    1996-01-01

    The purpose of this Safety Guide is to provide guidance on fulfilling the requirements for inspection and enforcement by the regulatory body, as set out in the Code on the Safety of Nuclear Power Plants; Governmental Organization. This Safety Guide deals with the responsibilities of the regulatory body, the organization of inspection programmes, the inspection resources of the regulatory body, methods of inspection, requirements on the applicant/licensee in regard to regulatory inspection, inspection reports, and regulatory action and enforcement. It is recognized that many of the provisions of this Safety Guide may be applicable to the regulations of other nuclear facilities and related activities including research reactors, fuel processing and manufacturing plants, irradiated fuel processing plants and radioactive waste management facilities. This Safety Guide does not deal specifically with the functions of a regulatory body responsible for such matters; however, the guidance presented here may be applied as appropriate to these activities. 11 refs, 1 fig

  20. Car seat inspection among children older than 3 years: Using data to drive practice in child passenger safety.

    Science.gov (United States)

    Kroeker, Amber M; Teddy, Amy J; Macy, Michelle L

    2015-09-01

    Motor vehicle crashes are the leading cause of unintentional death and disability among children 4 years to 12 years of age in the United States. Despite the high risk of injury from motor vehicle crashes in this age group, parental awareness and child passenger safety programs in particular may lack focus on this age group. This is a retrospective cross-sectional analysis of child passenger safety seat checklist forms from two Safe Kids coalitions in Michigan (2013) to identify restraint type upon arrival to car seat inspections. Other variables were included if the coalition provided a new child safety seat and if the child had a sibling who underwent a car seat inspection. χ statistics were used to compare change in restraint use on arrival and at departure, the proportion of children attending a car seat inspection event by age, the age category of children by site, the proportion of children with siblings also undergoing a car seat inspection by age, and the distribution of a new child safety seat by age. Data were available from 1,316 Safe Kids Huron Valley and 3,215 Safe Kids Greater Grand Rapids car seat inspections. Just 10.8% of the total seats inspected were booster seats. Child safety seats for infant and young children were more commonly inspected (rear-facing carrier [40.3%], rear-facing convertible [10.2%], and forward-facing [19.3%] car seats). Few children at inspections used a seat belt only (5.4%) or had no restraint (13.8%). Children 4 years and older were found to be in a suboptimal restraint at least 30% of the time. Low proportions of parents use car seat inspections for children in the booster seat age group. The proportion of children departing the inspection in a more protective restraint increased with increasing age. This highlights an area of weakness in child passenger safety programs and signals an opportunity to strengthen efforts on The Booster Age Child. Epidemiologic/prognostic study, level III.

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

    Science.gov (United States)

    2015-06-01

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

  2. Inspection of fire protection measures and fire fighting capability at nuclear power plants. A publication within the NUSS programme

    International Nuclear Information System (INIS)

    1994-01-01

    The present publication has been developed with the help of experts from regulatory, operating and engineering organizations, all with practical experience in the field of fire protection of nuclear power plants. The publication outlines practices for inspecting the fire protection measures at nuclear power plants in accordance with Safety Series No.50-SG-D2(Rev.1), Fire Protection in Nuclear Power Plants, and includes a comprehensive fire safety inspection checklist of the specific elements to be addressed when evaluating the adequacy and effectiveness of the fire protection measures and manual fire fighting capability available at operating nuclear power plants. The publication will be useful not only to regulators and safety assessors but also to operators and designers. The book addresses a specialized topic and it is recommended that it be used in conjunction with Safety Guide No.50-SG-D2(Rev.1)

  3. Restaurant inspection frequency: The RestoFreq Study.

    Science.gov (United States)

    Medu, Olanrewaju; Turner, Hollie; Cushon, Jennifer A; Melis, Deborah; Rea, Leslie; Abdellatif, Treena; Neudorf, Cory O; Schwandt, Michael

    2017-03-01

    Foodborne illness is an important contributor to morbidity and health system costs in Canada. Using number of critical hazards as a proxy for food safety, we sought to better understand how to improve food safety in restaurants. We compared the current standard of annual inspections to twice-yearly inspections among restaurants "at risk" for food safety infractions. These were restaurants that had three or more elevated-risk inspection ratings in the preceding 36 months. We conducted a two-arm randomized controlled trial between November 2012 and October 2014. The intervention was twice-yearly routine restaurant inspection compared to standard once-yearly routine inspection. Included were all restaurants within Saskatoon Health Region that were assessed as "at risk", with 73 restaurants in the intervention arm and 78 in the control arm. Independent sample t-tests were conducted between groups to compare: i) average number of critical hazards per inspection; and ii) proportion of inspections resulting in a rating indicating an elevated hazard. Over time we noted statistically significant improvements across both study arms, in number of both critical food safety hazards (decreased by 61%) and elevated-risk inspection ratings (decreased by 45%) (p < 0.0001). We observed no significant differences between the two groups pre- or post-intervention. Results suggest increasing the number of annual routine inspections in high-risk restaurants was not associated with a significant difference in measures of compliance with food safety regulations. Findings of this study do not provide evidence supporting increased frequency of restaurant inspection from annually to twice annually.

  4. Synthesis of the IRSN report on the second safety re-inspection of the Orphee research reactor

    International Nuclear Information System (INIS)

    2010-01-01

    The second safety inspection of the Orphee base nuclear installation notably relies on international and French return on experience. This inspection addressed the robustness of the installation against extreme aggressions, organisational processes, radiation protection, waste and effluent management, the security of the reactor operation, handling operation security, nuclear waste warehousing safety, internal aggressions, the third confinement barrier, and the radiological consequences of incidental and accidental situations

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

    Science.gov (United States)

    2014-11-01

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

  6. Inspection planning

    International Nuclear Information System (INIS)

    Korosec, D.; Levstek, M.F.

    2001-01-01

    Slovenian Nuclear Safety Administration (SNSA) division of nuclear and radiological safety inspection has developed systematic approach to their inspections. To be efficient in their efforts regarding regular and other types of inspections, in past years, the inspection plan has been developed. It is yearly based and organized on a such systematic way, that all areas of nuclear safety important activities of the licensee are covered. The inspection plan assures appropriate preparation for conducting the inspections, allows the overview of the progress regarding the areas to be covered during the year. Depending on the licensee activities and nature of facility (nuclear power plant, research reactor, radioactive waste storage, others), the plan has different levels of intensity of inspections and also their frequency. One of the basic approaches of the plan is to cover all nuclear and radiological important activities on such way, that all regulatory requests are fulfilled. In addition, the inspection plan is a good tool to improve inspection effectiveness based on previous experience and allows to have the oversight of the current status of fulfillment of planned inspections. Future improvement of the plan is necessary in the light of newest achievements on this field in the nuclear world, that means, new types of inspections are planned and will be incorporated into plan in next year.(author)

  7. Present state of 'Mutsu', the general inspection of safety and the repair of shielding

    International Nuclear Information System (INIS)

    1980-01-01

    The Agency has carried out the works based on the plan for the repair of shielding and the general inspection of safety in the nuclear ship ''Mutsu'' also in 1979. As for the repair of shielding, the permission by the prime minister to alter the nuclear reactor installation was obtained. The contents of the alteration are the repair of primary and secondary shieldings and the additional construction of a tank for storing liquid waste. As for the general inspection of safety, the tests for confirming the functions of main machinery and equipments have been carried out since January, 1979. A set of testing apparatuses was made as the preparation for the flaw detection test of steam generator tubes. As for the general inspection of softwares, the re-evaluation of the design of nuclear reactor plant and the analysis of the accidents in nuclear reactor plant were almost completed. Considering the accident of TMI No. 2 reactor, the inspection of softwares is in progress. The contract for these repair and inspection is not yet made, and the negotiations are under way. The nuclear ship ''Mutsu'' was brought to Sasebo Port in October, 1978, and dry-docked in July, 1979. As the result of inspection, any rust and wear were not found on the bottom plates, rudder and propeller. The survey of environmental radioactivity in Sasebo and Ominato, the budget for the repair and inspection, and the movement of the government are also reported. (Kako, I.)

  8. FMCSA safety program effectiveness measurement : Roadside Intervention Effectiveness Model, fiscal year 2012.

    Science.gov (United States)

    2016-02-01

    The Federal Motor Carrier Safety Administration (FMCSA), in cooperation with the John A. Volpe National : Transportation Systems Center, has developed an analytic model to measure the effectiveness of roadside : inspections and traffic enforcements i...

  9. FMCSA safety program effectiveness measurement : Roadside Intervention Effectiveness Model, fiscal year 2010.

    Science.gov (United States)

    2014-11-01

    The Federal Motor Carrier Safety Administration (FMCSA), in cooperation with the John A. Volpe National Transportation Systems Center, has developed an analytic model to measure the effectiveness of roadside inspections and traffic enforcements in te...

  10. FMCSA safety program effectiveness measurement : roadside intervention effectiveness model fiscal year 2011.

    Science.gov (United States)

    2015-06-01

    The Federal Motor Carrier Safety Administration (FMCSA), in cooperation with the John A. Volpe National Transportation Systems Center, has developed an analytic model to measure the effectiveness of roadside inspections and traffic enforcements in te...

  11. FMCSA safety program effectiveness measurement : roadside intervention effectiveness model, fiscal year 2013.

    Science.gov (United States)

    2017-08-01

    The Federal Motor Carrier Safety Administration (FMCSA), in cooperation with the John A. Volpe National Transportation Systems Center, has developed an analytic model to measure the effectiveness of roadside inspections and traffic enforcements in te...

  12. National Dam Safety Program. Lakeview Estates Dam (MO 11004), Mississippi - Kaskaskia - St. Louis Basin, Warren County, Missouri. Phase I Inspection Report.

    Science.gov (United States)

    1979-09-01

    ificatiozh Distributon/ Availabilit oe LAKEVIEW ESTATES DAM WARREN COUNTY, MISSOURI MISSOURI INVENTORY NO. 11004 PHASE I INSPECTION REPORT NATIONAL DAM SAFETY...and *impounds less than 1,000 acre-feet of water . Our inspection and evaluation indicates that the spill- way of Lakeview Estates Dam does not meet...not be measured because of high reservoir level, scalloping near the crest and a berm just under the water surface. Limestone riprap in sizes from sand

  13. Inspection Frequency, Sociodemographic Factors, and Food Safety Violations in Chain and Nonchain Restaurants, Philadelphia, Pennsylvania, 2013-2014.

    Science.gov (United States)

    Leinwand, Sarah E; Glanz, Karen; Keenan, Brendan T; Branas, Charles C

    We explored how restaurant inspection frequency and restaurant neighborhood sociodemographic characteristics are related to food safety inspection outcomes in chain and nonchain restaurants to better understand external factors that may influence inspection outcomes. We categorized the results of restaurant inspections in Philadelphia, Pennsylvania, in 2013 and 2014 by restaurant type (chain or nonchain), inspection frequency (1, 2, or ≥3 per 2-year study period), and violation type (total number of violations, foodborne-illness risk factor violation, or good retail practice violation). We collected 2013 US Census block group sociodemographic data for each restaurant neighborhood. We used nested mixed-effects regression analyses to determine the association between restaurant inspection frequency and inspection violations, as well as between inspection violations and restaurant neighborhood sociodemographic variables, stratified by restaurant type. Compared with nonchain restaurants, chain restaurants had significantly fewer total violations per inspection (mean [SD]: 6.5 [4.6] vs 9.6 [6.8] violations, P chain restaurants. For nonchain restaurants, a higher proportion of black residents in a restaurant neighborhood was associated with 0.6 ( P food safety inspection frequency, based on whether or not restaurants are part of chains, could reduce the frequency of violations, particularly in restaurants with the most violations.

  14. Nuclear safety inspection in treatment process for SG heat exchange tubes deficiency of unit 1, TNPS

    International Nuclear Information System (INIS)

    Zhang Chunming; Song Chenxiu; Zhao Pengyu; Hou Wei

    2006-01-01

    This paper describes treatment process for SG heat exchange tubes deficiency of Unit 1, TNPS, nuclear safety inspection of Northern Regional Office during treatment process for deficiency and further inspection after deficiency had been treated. (authors)

  15. Remotely-operated equipment for inspection, measurement and handling

    CERN Document Server

    Bertone, C; CERN. Geneva. TS Department

    2008-01-01

    As part of the application of ALARA radiation dose reduction principles at CERN, inspection, measurement and handling interventions in controlled areas are being studied in detail. A number of activities which could be carried out as remote operations have already been identified and equipment is being developed. Example applications include visual inspection to check for ice formation on LHC components or water leaks, measurement of radiation levels before allowing personnel access, measurement of collimator or magnet alignment, visual inspection or measurements before fire service access in the event of fire, gas leak or oxygen deficiency. For these applications, a modular monorail train, TIM, has been developed with inspection and measurement wagons. In addition TIM provides traction, power and data communication for lifting and handling units such as the remote collimator exchange module and vision for other remotely operated units such as the TAN detector exchange mini-cranes. This paper describes the eq...

  16. Analisis Kepatuhan Supervisor Terhadap Implementasi Program Occupational Health & Safety (Ohs) Planned Inspection Di PT. Ccai

    OpenAIRE

    Sarah, Dewi; Ekawati, Ekawati; Widjasena, Baju

    2015-01-01

    The Government has issued Regulation Legislation No. 50 Year 2012 on Health and Safety Management System (SMK3). CCAI is a company that has implemented SMK3. The application of the CCAI SMK3 supported by K3 program one of them is OHS Planned Inspection. This study aimed to analyze the implementation of Occupational Health & Safety (OHS) program Planned Inspection in CCAI. The subjects of this study amounted to five people as the main informants and 2 as an informant triangulation. The res...

  17. A randomised controlled study to evaluate the effectiveness of targeted occupational health and safety consultation or inspection in Ontario manufacturing workplaces.

    Science.gov (United States)

    Hogg-Johnson, Sheilah; Robson, Lynda; Cole, Donald C; Amick, Benjamin C; Tompa, Emile; Smith, Peter M; van Eerd, Dwayne; Mustard, Cameron

    2012-12-01

    From 2004 to 2008, the prevention system in Ontario, Canada ran the High Risk Firm Initiative, an injury-experience based targeted consultation or inspection programme. Our objective was to establish whether prevention system targeting of firms was effective in improving injury outcomes. Randomised controlled parallel groups. Population included all manufacturing firms registered with the Ontario Workplace Safety & Insurance Board in 2005. Firms ranked between the 2nd and 10th percentile on a composite measure of occupational health and safety performance were randomised to three study arms in 2006: targeted for Health & Safety Association (HSA) consultation, targeted for Ministry of Labour (MOL) inspection, or services as usual. Data included firm characteristics (sector, size, years in business, region, branches), work injury claims 2002-2008 and measures of consulting and inspecting activity. Negative binomial generalised estimating equations modelled claim and disability day rates by study arm and year, controlling for firm characteristics. Among 2153 firms, firm characteristics and 2002-2005 rates of work injury claims and disability days were similar across arms. Firm outcomes were significantly different from year to year, but study arm by year interactions were insignificant indicating similar trends for all three study arms. 83% of HSA targeted firms were contacted and 63% engaged while 75% of MOL targeted firms were inspected with orders written in 56%. Consultation and enforcement programmes as implemented were not sufficient to reduce work injury outcomes over 21 month follow-up. Lack of benefit could be due to non-specific firm selection methods, limited firm participation in interventions, low intervention intensity or insensitivity of available outcomes.

  18. Super Phenix 1: in Service inspection of main and safety tanks weldments

    International Nuclear Information System (INIS)

    Asty, Michel; Vertut, Jean; Argous, J.P.

    1980-05-01

    In service inspection of the main tank of the Super Phenix 1 reactor is a new demand as compared to Phenix: the authorities have asked that surface and internal defects could be detected and their evolution monitored in the future. The presence of thermal baffles inside the main tank precludes the access on that side: the distance between the main and safety tanks takes into account the room needed for an In Service Inspection module. An inspection vehicle is presently under development, which includes ultrasonic examination (focussed probes) and visual examination (TV cameras) capabilities. We briefly describe the techniques that have been selected for ultrasonic testing and also for the vehicle and its guidance between the tanks

  19. Super Phenix 1: In-service inspection of main and safety tanks weldments

    Energy Technology Data Exchange (ETDEWEB)

    Asty, M [DTech/STA, Centre d' Etudes Nucleaires de Saclay (France); Vertut, J [DPR/STEP, Centre d' Etudes Nucleaires de Saclay (France); Argous, J P [DRNR/STRS, Centre d' Etudes Nucleaires de Cadarache (France)

    1980-11-01

    In Service Inspection of the main tank of the Super Phenix 1 reactor is a new demand compared to Phenix: the authorities have asked that surface and internal defects be detected and their evolution monitored in the future. The presence of thermal baffles inside the main tank precludes the access on that side: the distance between the main and safety tanks takes into account the room needed for an In Service Inspection module. An inspection vehicle is presently under development, which includes ultrasonic examination (focussed probes) and visual examination (TV cameras) capabilities. We briefly describe the techniques that have been selected for ultrasonic testing and also for the vehicle and its guidance between the tanks. (author)

  20. Super Phenix 1: In-service inspection of main and safety tanks weldments

    International Nuclear Information System (INIS)

    Asty, M.; Vertut, J.; Argous, J.P.

    1980-01-01

    In Service Inspection of the main tank of the Super Phenix 1 reactor is a new demand compared to Phenix: the authorities have asked that surface and internal defects be detected and their evolution monitored in the future. The presence of thermal baffles inside the main tank precludes the access on that side: the distance between the main and safety tanks takes into account the room needed for an In Service Inspection module. An inspection vehicle is presently under development, which includes ultrasonic examination (focussed probes) and visual examination (TV cameras) capabilities. We briefly describe the techniques that have been selected for ultrasonic testing and also for the vehicle and its guidance between the tanks. (author)

  1. APPLICATION OF LEAN CONCEPT TO SHIP SAFETY INSPECTION: A CASE STUDY AT PORT OF SURABAYA

    Directory of Open Access Journals (Sweden)

    F. Cahyadi

    2012-06-01

    Full Text Available The Lean Concept is a mindset widely used in various industries seeking for efficiency and effectiveness through improvement of process flow and elimination of waste. This research applies lean thinking to ship safety inspection at Port of Surabaya to investigate the existing procedure and to identify the wastes and non-value-add (NVA activity. It used a combination of literature review, examination on the data of 520 inspections that have been carried out to 201 ships in the last two years (2009 - 2011, investigation on related regulations and guidelines, observation on the actual conduct of inspection, and interview with 59 marine inspectors and ship officers. Analysis is conducted using Value Stream Mapping (VSM. It is found that the existing procedure lacks significant impact in terms of imposing a reduction in the total number of detected deficiency between the earlier and subsequent inspections. Only 37% of the ships experience a reduction, indicating that the performance of inspection is currently at the level of 37 on a 100-point scale. It was mainly due to severe violation of the regulations, which is demonstrated by the issuance of ship certificate regardless of corrective action undertaken relating to the detected deficiency. Keywords: Lean concept, ship safety inspection, value stream mapping.

  2. Inspection of radiation sources and regulatory enforcement (supplement to IAEA Safety Standards Series No. GS-G-1.5)

    International Nuclear Information System (INIS)

    2010-08-01

    The achievement and maintenance of a high level of safety in the use of radiation sources depends on there being a sound legal and governmental infrastructure, including a national regulatory body with well-defined responsibilities and functions. These responsibilities and functions include establishing and implementing a system for carrying out regulatory inspections, and taking necessary enforcement actions. The Safety Requirements publication entitled Legal and Governmental Infrastructure for Nuclear, Radiation, Radioactive Waste and Transport Safety establishes the requirements for legal and governmental infrastructure. The term 'infrastructure' refers to the underlying structure of systems and organizations. This includes requirements concerning the establishment of a regulatory body for radiation sources and the responsibilities and functions assigned to it. The International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (the Basic Safety Standards or the BSS) establish basic requirements for protection against risks associated with exposure to ionizing radiation and for the safety of radiation sources. The application of the BSS is based on the presumption that national infrastructures are in place to enable governments to discharge their responsibilities to for radiation protection and safety. This TECDOC provides practical guidance on the processes for carrying out regulatory inspections and taking enforcement actions. It includes information on the development and use of procedures and standard review plans (i.e. checklists) for inspection. Specific procedures for inspection of radiation practices and sources are provided in the Appendices

  3. Inspection of radiation sources and regulatory enforcement (supplement to IAEA Safety Standards Series No. GS-G-1.5)

    International Nuclear Information System (INIS)

    2007-04-01

    The achievement and maintenance of a high level of safety in the use of radiation sources depends on there being a sound legal and governmental infrastructure, including a national regulatory body with well-defined responsibilities and functions. These responsibilities and functions include establishing and implementing a system for carrying out regulatory inspections, and taking necessary enforcement actions. The Safety Requirements publication entitled Legal and Governmental Infrastructure for Nuclear, Radiation, Radioactive Waste and Transport Safety establishes the requirements for legal and governmental infrastructure. The term 'infrastructure' refers to the underlying structure of systems and organizations. This includes requirements concerning the establishment of a regulatory body for radiation sources and the responsibilities and functions assigned to it. The International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (the Basic Safety Standards or the BSS) establish basic requirements for protection against risks associated with exposure to ionizing radiation and for the safety of radiation sources. The application of the BSS is based on the presumption that national infrastructures are in place to enable governments to discharge their responsibilities to for radiation protection and safety. This TECDOC provides practical guidance on the processes for carrying out regulatory inspections and taking enforcement actions. It includes information on the development and use of procedures and standard review plans (i.e. checklists) for inspection. Specific procedures for inspection of radiation practices and sources are provided in the Appendices

  4. Periodic vehicle inspection (MOT). [previously: Periodic Vehicle Inspection of cars (MOT).

    OpenAIRE

    2010-01-01

    In the 1980s the periodic vehicle inspection (MOT) of various categories of vehicles was introduced in the Netherlands. This fact sheet will discuss the legal framework of this measure and the research carried out into its effects on road safety, also in an international context. For instance, the technical conditions of cars at inspection as well as that of cars involved in crashes were studied. Tyre pressure will also be discussed in this fact sheet.

  5. How Agencies Inspect. A Comparative Study of Inspection Policies in Eight Swedish Government Agencies

    International Nuclear Information System (INIS)

    Lindblom, Lars; Clausen, Jonas; Edvardsson, Karin; Hayenhielm, Madeleine; Hermansson, Helene; Nihlen, Jessica; Palm, Elin; Ruden, Christina; Wikman, Per; Hansson, Sven Ove

    2003-04-01

    Eight Swedish authorities with inspection tasks in the areas of health, safety, and environmental protection have been compared, namely the authorities responsible for nuclear safety, radiation protection, railway, marine and aviation safety, environmental protection, chemicals control, and health and safety on workplaces. Significant differences in inspection policies and practices between the authorities were found, such as: diverging definitions of supervision and inspection that complicate comparisons, different priority-setting principles for inspections, variations in inspection frequencies (between 13 and 0.03 inspections per company and year), different practices with respect to notifying companies before inspection visits, and in particular, large differences in the extent to which non-compliance with regulations is reported to legal authorities. It was concluded that these agencies have much to gain from increasing their cooperation in methods development, evaluation studies, and education of inspectors

  6. Probabilistic safety analysis and risk-based inspection of nuclear research reactors: state-of-the-art and implementation proposal

    Energy Technology Data Exchange (ETDEWEB)

    Marques, Raíssa O.; Vasceoncelos, Vanderley de; Soares, Wellington A.; Silva Júnior, Silvério F.; Raso, Amanda L.; Mesquita, Amir Z., E-mail: raissaomarques@gmail.com, E-mail: vasconv@cdtn.br, E-mail: soaresw@cdtn.br, E-mail: silvasf@cdtn.br, E-mail: amandaraso@hotmail.com, E-mail: amir@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2017-07-01

    Industrial facilities systems deteriorate over time during operation, thus increasing the possibility of accidents. Risk-Based Inspection (RBI) classifies such systems by their risk information with the purpose of prioritizing inspection efforts. RBI can reduce inspection activities, resulting in lower risk levels, and maintaining reliability and safety in acceptable levels. Risk-Informed In-Service Inspection (RI-ISI) is a RBI approach used in nuclear industry. RI-ISI uses outcomes from Probabilistic Safety Analysis (PSA) of Nuclear Power Plants (NPP) to plan In-Service Inspections (ISI). Despite nuclear research reactors are simpler and have lower risks than power reactors, the application of PSA to them may be useful for safety improvements once they are more flexible, provide easier access to its core, and allow changes in fuel configurations in case of experimental tests. Ageing management of structures, systems and components important to safety of a nuclear research reactor throughout its lifetime is also required to assure continued adequacy of safety levels, reliable operation, and compliance with operational limits and conditions. This includes periodic review of ISI programs in which monitoring of material deterioration and aging effects are considered, and that can be supported by the RBI approach. A review of state-of-the-art of PSA and RBI applications to nuclear reactors is presented in this work. Advantages to apply these methodologies are also analyzed. PSA and RBI implementation proposal applied to nuclear research reactors is also presented, as well as its application to a TRIGA research nuclear reactor using computer codes developed by ReliaSoft® Corporation. (author)

  7. Probabilistic safety analysis and risk-based inspection of nuclear research reactors: state-of-the-art and implementation proposal

    International Nuclear Information System (INIS)

    Marques, Raíssa O.; Vasceoncelos, Vanderley de; Soares, Wellington A.; Silva Júnior, Silvério F.; Raso, Amanda L.; Mesquita, Amir Z.

    2017-01-01

    Industrial facilities systems deteriorate over time during operation, thus increasing the possibility of accidents. Risk-Based Inspection (RBI) classifies such systems by their risk information with the purpose of prioritizing inspection efforts. RBI can reduce inspection activities, resulting in lower risk levels, and maintaining reliability and safety in acceptable levels. Risk-Informed In-Service Inspection (RI-ISI) is a RBI approach used in nuclear industry. RI-ISI uses outcomes from Probabilistic Safety Analysis (PSA) of Nuclear Power Plants (NPP) to plan In-Service Inspections (ISI). Despite nuclear research reactors are simpler and have lower risks than power reactors, the application of PSA to them may be useful for safety improvements once they are more flexible, provide easier access to its core, and allow changes in fuel configurations in case of experimental tests. Ageing management of structures, systems and components important to safety of a nuclear research reactor throughout its lifetime is also required to assure continued adequacy of safety levels, reliable operation, and compliance with operational limits and conditions. This includes periodic review of ISI programs in which monitoring of material deterioration and aging effects are considered, and that can be supported by the RBI approach. A review of state-of-the-art of PSA and RBI applications to nuclear reactors is presented in this work. Advantages to apply these methodologies are also analyzed. PSA and RBI implementation proposal applied to nuclear research reactors is also presented, as well as its application to a TRIGA research nuclear reactor using computer codes developed by ReliaSoft® Corporation. (author)

  8. ALS insertion device block measurement and inspection

    International Nuclear Information System (INIS)

    Marks, S.; Carrieri, J.; Cook, C.; Hassenzahl, W.V.; Hoyer, E.; Plate, D.

    1991-05-01

    The performance specifications for ALS insertion devices require detailed knowledge and strict control of the Nd-Fe-B permanent magnet blocks incorporated in these devices. This paper describes the measurement and inspection apparatus and the procedures designed to qualify and characterize these blocks. A detailed description of a new, automated Helmholtz coil facility for measurement of the three components of magnetic moment is included. Physical block inspection and magnetic moment measurement procedures are described. Together they provide a basis for qualifying blocks and for specifying placement of blocks within an insertion devices' magnetic structures. 1 ref., 4 figs

  9. The 900 MWe water pressurized reactor safety re-examination at the occasion of their third decennial inspection

    International Nuclear Information System (INIS)

    2009-01-01

    This document reports the safety re-examination actions performed on the French 900 MWe water pressurized reactors. This process includes three stages. The first one is an inventory of safety, design and operation requirements which are defined or specified in different texts: regulations, rules, criteria and specifications. This leads to compliance studies with respect to these documents and by in situ inspections, and then to corrective recommendations. After presenting this process, the report deals with specific safety studies which are related to external or internal aggressions (fire, explosions, flooding, climate, seism), to accidental situations (primary circuit cold overpressure, severe accidents, containment, level 1 and 2 safety probabilistic studies, passive failure of safeguard circuits, vapour generator tube failure, and so on), to design and sizing of civil engineering works and systems (radioactivity measurement system, safety injection system, recirculation function liability, liability of the irradiated fuel deactivation pool cooling system)

  10. A risk-informed approach to optimising in-service inspection of piping

    International Nuclear Information System (INIS)

    Billington, A.; Monette, P.

    1999-01-01

    Traditional criteria for the selection of in-service inspection locations in piping, have come to be regarded as being out-of-touch with current knowledge of piping failures and with current measures of safety importance. An alternative , risk-informed, method has been developed and successfully licensed, that systematically establishes an inspection plan addressing all safety-related piping systems, in a way that is optimized with respect to the safety gain achieved through in-service inspection. The principles of the method are discussed and the results of several applications are summarized, all of which demonstrate that the risk-informed program would lead to significant improvements in the overall level of plant safety, while at the same time re-distributing the inspections in such a way that reduces both plant costs and radiation exposure to personnel.(author)

  11. Periodic vehicle inspection (MOT). [previously: Periodic Vehicle Inspection of cars (MOT).

    NARCIS (Netherlands)

    2010-01-01

    In the 1980s the periodic vehicle inspection (MOT) of various categories of vehicles was introduced in the Netherlands. This fact sheet will discuss the legal framework of this measure and the research carried out into its effects on road safety, also in an international context. For instance, the

  12. Chapter 4. Assessment and inspection of nuclear installations

    International Nuclear Information System (INIS)

    2001-01-01

    develop protocols in which the findings from these inspections are specified. This protocol also contains orders and measures imposed by UJD to correct the shortcomings found. Qualifications and examinations of nuclear safety inspectors are assured in accordance with an internal guideline of UJD. Inspectors take part not only in training courses and other technical meetings organised by the IAEA, but also in some special training courses organised in co-operation with nuclear safety regulators from European countries, USA, Canada and Japan. In next part of this chapter there are presented in details the assessment activity as well as the inspection activity of UJD on the NPP V-1 Bohunice, NPP V-2 Bohunice, NPP Mochovce, NPP A-1 Bohunice, Interim spent fuel storage Bohunice, Technology for treatment and conditioning of radioactive waste Bohunice, National Radioactive Waste Repository Mochovce, Nuclear facilities of VUJE Trnava, Statistical data on assessment and inspection activity of UJD

  13. 29 CFR 1960.25 - Qualifications of safety and health inspectors and agency inspections.

    Science.gov (United States)

    2010-07-01

    ... conditions affecting employee safety and health, coordination of inspection functions is encouraged. ... HEALTH ADMINISTRATION, DEPARTMENT OF LABOR (CONTINUED) BASIC PROGRAM ELEMENTS FOR FEDERAL EMPLOYEE... shall be conducted by inspectors qualified to recognize and evaluate hazards of the working environment...

  14. Strategic environmental safety inspection for the National disposal program. Description of the inspection volume. Documentation for the scoping team; Strategische Umweltpruefung zum Nationalen Entsorgungsprogramm. Beschreibung des Untersuchungsumfangs. Unterlage fuer den Scoping-Termin

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2015-01-06

    The Strategic environmental safety inspection for the National disposal program covers the following topics: Legal framework: determination of the requirement for an environmental inspection program, coordination of the scoping team into the overall context; environmental targets; approach for assessment and evaluation of environmental impact, description of the inspection targets for the strategic environmental inspection; consideration of alternatives.

  15. Influence of visual clutter on the effect of navigated safety inspection: a case study on elevator installation.

    Science.gov (United States)

    Liao, Pin-Chao; Sun, Xinlu; Liu, Mei; Shih, Yu-Nien

    2018-01-11

    Navigated safety inspection based on task-specific checklists can increase the hazard detection rate, theoretically with interference from scene complexity. Visual clutter, a proxy of scene complexity, can theoretically impair visual search performance, but its impact on the effect of safety inspection performance remains to be explored for the optimization of navigated inspection. This research aims to explore whether the relationship between working memory and hazard detection rate is moderated by visual clutter. Based on a perceptive model of hazard detection, we: (a) developed a mathematical influence model for construction hazard detection; (b) designed an experiment to observe the performance of hazard detection rate with adjusted working memory under different levels of visual clutter, while using an eye-tracking device to observe participants' visual search processes; (c) utilized logistic regression to analyze the developed model under various visual clutter. The effect of a strengthened working memory on the detection rate through increased search efficiency is more apparent in high visual clutter. This study confirms the role of visual clutter in construction-navigated inspections, thus serving as a foundation for the optimization of inspection planning.

  16. Regulatory inspection of BARC facilities

    International Nuclear Information System (INIS)

    Rajdeep; Jayarajan, K.

    2017-01-01

    Nuclear and radiation facilities are sited, constructed, commissioned, operated and decommissioned, in conformity with the current safety standards and codes. Regulatory bodies follow different means to ensure compliance of the standards for the safety of the personnel, the public and the environment. Regulatory Inspection (RI) is one of the important measures employed by regulatory bodies to obtain the safety status of a facility or project and to verify the fulfilment of the conditions stipulated in the consent

  17. Verification of implementation of the radiological safety standards through the regulatory inspections

    International Nuclear Information System (INIS)

    Perez Gonzalez, Francisco; Fornet Rodriguez, Ofelia M.

    2008-01-01

    Full text: As an element of the updating process of the legal framework on radiological safety in Cuba, a new rule was put into force; the Radiological Basic Safety Standards (RBSS) in January 2002. Five years after the application of these new safety requirements, it was considered appropriate to assess the effectiveness of its implementation. Therefore, in this work the authors analysed the outcomes of the regulatory inspections conducted in this period upon medical and industrial practices in a sample of facilities representative of those with the highest radiological risks in the territory under supervision of a Territorial Delegation of the Nuclear Regulatory Authority. For better understanding of this presentation, a summary explanation of the structure of the rule is given in its introduction. The work was to identify for each deficiency, or finding, or counter-measure; out of the relevant inspections; the corresponding requirement/Article of the RBSS that shows difficulties in implementation. For each installation an analysis is made with regard to the relevant articles difficult to implement. Finally, the appraisal is shown separately for the medical practice, and for the industrial practice, and also in general for the whole sample of installations under review. The study showed that the implementation of the Standards has been satisfactory and uniform in the practices under review. So far it seems that there have not been major difficulties with the implementation of the Titles; III On Intervention, IV Dose Limits, as well as with the Especial, Final, and Transitory Dispositions. On the other hand, it is shown there is a need for continued work only with regard to the implementation of the requirements in Section IV Verification of Safety and in Section V On the responsibilities with regard to occupational exposure in Chapter III Title I, and correspondingly in Chapter II Occupational Exposure in Title II. It is recommended to conduct this kind of

  18. Competition and safety in the law on technical inspection and control - is it a contradiction?

    International Nuclear Information System (INIS)

    Roth, H.A.

    1987-01-01

    For some time now, objections have been raised against the argument that technical inspection and control should indeed remain a task exlusively for the Technical Control Boards and their offices, organisations and employed inspectors, because competition in this very safety-related sector would not be a positive factor of selection but rather a mechanism reducing the inspection quality, resulting in a hazardous lowering of the safety level. The objections are primarily raised by the free-lance technical experts and their organisations who would like to enlarge their field of activity in this direction. The book at hand discusses the question how much free manoeuvering space there is for the legislative body to deal with such demands and reconcile the interests of safety and competition. The problem is discussed with a view to the Basic Law, which is said to create no legal basis for the demand for more competition in this field. The Basic Law leaves this decision to the discretion of the legislature. (orig./HP) [de

  19. 2015 annual report of the managing director of the CEA general and nuclear inspection for nuclear safety and radiation protection

    International Nuclear Information System (INIS)

    2016-08-01

    After an introduction by the managing director of the CEA general and nuclear inspection about activities and events of 2015, this report proposes some key figures and indicators to illustrate these activities and events. The next parts discuss, present and comment how a culture of safety is at the heart of the continuous progress approach by the CEA. The next chapters propose overviews and comments of lessons learned from nuclear inspections within the frame of audit programme or within the frame of centres' safety audits, and from reactive inspections. The last parts address the follow-up of recommendations, and progress orientations and perspectives

  20. Inspection program for U.S. research reactors

    International Nuclear Information System (INIS)

    Isaac, Patrick J.

    2010-01-01

    This paper presents an established program for inspection of nuclear research reactors to ensure that systems and techniques are in accordance with regulatory requirements and to provide protection for the health and safety of the public. The inspection program, implemented from the time a facility gets licensed, remains in effect through operations, shutdown, decommissioning, and until the license is terminated. The program establishes inspection methodology for operating, safeguards, and decommissioning activities. Using a performance- based approach, inspectors focus their attention on activities important to safety. Inspection procedures allow the inspectors to assess facility safety and compliance to applicable requirements. A well designed inspection program is an integral part of the mechanism to ensure that the level of performance in the strategic areas of reactor safety, radiation safety, and safeguards is acceptable and provides adequate protection of public health and safety. (author)

  1. APPLICATION OF LEAN CONCEPT TO SHIP SAFETY INSPECTION: A CASE STUDY AT PORT OF SURABAYA

    OpenAIRE

    Cahyadi, F.

    2012-01-01

    The Lean Concept is a mindset widely used in various industries seeking for efficiency and effectiveness through improvement of process flow and elimination of waste. This research applies lean thinking to ship safety inspection at Port of Surabaya to investigate the existing procedure and to identify the wastes and non-value-add (NVA) activity. It used a combination of literature review, examination on the data of 520 inspections that have been carried out to 201 ships in the last two years ...

  2. Preventing degradation and in-service inspection of NPP steam generator

    International Nuclear Information System (INIS)

    Ding Xunshen

    1999-01-01

    The author describes the degradation of steam generator tubes in initial operating stage of France NPP. The author emphatically presents the preventive measures to tackle degradation and In-service inspection of Daya Bay NPP 1 unit as a guarantee of safety operation, including secondary side water chemistry monitoring and controlling, leakage rate monitoring, eddy-current inspection, mechanical cleaning, cleanliness inspection, foreign objects removal and etc

  3. Technological progress, safety, and the guardian role of inspection (with Appendix: Antecedants of the Nuclear Installation Inspectorate)

    International Nuclear Information System (INIS)

    Critchley, O.H.

    1981-01-01

    Technological progress inevitably brings hazards which must be inspected to reduce the occurence of any attendant risks to a minimum. Although the responsibility for regulatory safety inspection in Britain is spread amongst a number of specialist inspectorates, it is arguably the most fully developed, efficient and satisfactorily operating regime of its kind, this being especially true for commercial nuclear installations. The latter aspect is a complex mix of engineering, legal and managerial practices which has been modelled on the developments in safety technology in atomic energy in the Manhattan Project and in the UKAEA, among others, and on to the present Nuclear Installations Inspectorate. (U.K.)

  4. Optimal inspection and replacement periods of the safety system in Wolsung Nuclear Power Plant Unit 1 with an optimized cost perspective

    International Nuclear Information System (INIS)

    Jinil Mok; Poong Hyun Seong

    1996-01-01

    In this work, a model for determining the optimal inspection and replacement periods of the safety system in Wolsung Nuclear Power Plant Unit 1 is developed, which is to minimize economic loss caused by inadvertent trip and the system failure. This model uses cost benefit analysis method and the part for optimal inspection period considers the human error. The model is based on three factors as follows: (i) The cumulative failure distribution function of the safety system, (ii) The probability that the safety system does not operate due to failure of the system or human error when the safety system is needed at an emergency condition and (iii) The average probability that the reactor is tripped due to the failure of system components or human error. The model then is applied to evaluate the safety system in Wolsung Nuclear Power Plant Unit 1. The optimal replacement periods which are calculated with proposed model differ from those used in Wolsung NPP Unit 1 by about a few days or months, whereas the optimal inspection periods are in about the same range. (author)

  5. 33 CFR 165.169 - Safety and Security Zones: New York Marine Inspection Zone and Captain of the Port Zone.

    Science.gov (United States)

    2010-07-01

    ... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false Safety and Security Zones: New... Navigable Waters COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) PORTS AND WATERWAYS SAFETY... Areas First Coast Guard District § 165.169 Safety and Security Zones: New York Marine Inspection Zone...

  6. Task of radiation hygiene inspection at NPPs

    International Nuclear Information System (INIS)

    Shevts, J.; Kunz, Eh.

    1983-01-01

    The task and functions of the radiation-hygiene inspection in Czechoslovakia are presented. The radiation safety related information amounts that are to be presented to the hygiene inspection institutions are determined. The hygiene inspection content and forms at the stages of NPP designing, construction and operation are discussed. The hygiene inspection place is determined within the general radiation safety system [ru

  7. Radiation safety for baggage x-ray inspection systems

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-05-01

    This book is an outgrowth of a course on radiation safety aimed at technicians responsible for conducting maintenance on baggage x-ray inspection systems used in federally operated facilities. The need for a single reference book became apparent to the instructor in 1984. In an effort to provide a cohesive development of the subject, a set of lecture notes was prepared and revised annually since 1984, from which this book has evolved. This book is intended to present concepts necessary for an elementary but comprehensive knowledge of radiation safety. While some material coverage may appear somewhat detailed, it is a deliberate attempt to strengthen areas of demonstrated weaknesses observed in course attenders and to provide guidance on the numerous questions about man-made radiation asked by course attenders over the years. Numerical examples are included in most chapters for clarity and ease of understanding. The problems given at the end of most chapters provide the reader with the opportunity of applying the material presented in the chapters to situations of practical interest. It is important that these problems be considered an integral part of the course and students attempt to solve them. 36 refs., 9 tabs., 17 figs.

  8. Radiation safety for baggage x-ray inspection systems

    International Nuclear Information System (INIS)

    1994-05-01

    This book is an outgrowth of a course on radiation safety aimed at technicians responsible for conducting maintenance on baggage x-ray inspection systems used in federally operated facilities. The need for a single reference book became apparent to the instructor in 1984. In an effort to provide a cohesive development of the subject, a set of lecture notes was prepared and revised annually since 1984, from which this book has evolved. This book is intended to present concepts necessary for an elementary but comprehensive knowledge of radiation safety. While some material coverage may appear somewhat detailed, it is a deliberate attempt to strengthen areas of demonstrated weaknesses observed in course attenders and to provide guidance on the numerous questions about man-made radiation asked by course attenders over the years. Numerical examples are included in most chapters for clarity and ease of understanding. The problems given at the end of most chapters provide the reader with the opportunity of applying the material presented in the chapters to situations of practical interest. It is important that these problems be considered an integral part of the course and students attempt to solve them. 36 refs., 9 tabs., 17 figs

  9. In-service inspection techniques

    International Nuclear Information System (INIS)

    Backfisch, W.; Zipser, R.R.

    1980-01-01

    The owner of a nuclear power plant (NPP) is obligated and interested to maintain - by regular maintenance and in-service inspections - the operational safety and availability of the plant for the subsequent operating period in a condition, as is specified as the basis of the erection and the last operational permits. In-service inspections are performed to verify the operational safety, and maintenance work is performed to guarantee the availability. Below, the typical in-service inspections of a light-water reactor NPP (operated on a pressurized-water reactor or on a boiling-water reactor) are described with details and examples of typical inspections, especially of recurrent performance tests of the systems. (orig./RW)

  10. Urgent Safety Measures in Japan after Great East Japan Earthquake

    International Nuclear Information System (INIS)

    Taniura, W.; Otani, H.

    2012-01-01

    Due to tsunami triggered by the Great East Japan Earthquake on March 11, 2011, the operating and refueling reactor facilities at Fukushima Dai-ichi and Dai-ni Nuclear Power Plants of Tokyo Electric Power Co. caused a nuclear hazard. Japanese electric power companies voluntarily began to compile various urgent measures against tsunami within the week the hazard was caused. As for the urgent safety measures of each licensee, it is clarified that effective measures have been appropriately implemented as a result of the inspection of the national government, the verification based on the guideline of the Japan Society of Maintenology and the stress test. (author)

  11. The role of the United States Food Safety and Inspection Service after the Chernobyl accident

    Energy Technology Data Exchange (ETDEWEB)

    Engel, Ronald E; Randecker, Victor; Johnson, Wesley [Food Safety and Inspection Service, United States Department of Agriculture (United States)

    1989-09-01

    The Food Safety and Inspection Service (FSIS) of the United States Department of Agriculture (USDA) inspects domestic and imported meat and poultry food products to assure the public that they are safe, wholesome, not economically adulterated and properly labeled. The Service also monitors the activities of meat and poultry plants and related activities in allied industries, and establishes standards and approves labels for meat and poultry products. As part of its responsibility, shortly after the Chernobyl accident occurred, FSIS developed a plan to assess this accident's impact on domestically produced and imported meat and poultry.

  12. The role of the United States Food Safety and Inspection Service after the Chernobyl accident

    International Nuclear Information System (INIS)

    Engel, Ronald E.; Randecker, Victor; Johnson, Wesley

    1989-01-01

    The Food Safety and Inspection Service (FSIS) of the United States Department of Agriculture (USDA) inspects domestic and imported meat and poultry food products to assure the public that they are safe, wholesome, not economically adulterated and properly labeled. The Service also monitors the activities of meat and poultry plants and related activities in allied industries, and establishes standards and approves labels for meat and poultry products. As part of its responsibility, shortly after the Chernobyl accident occurred, FSIS developed a plan to assess this accident's impact on domestically produced and imported meat and poultry

  13. Status on system inspection and preventive maintenance of HANARO

    International Nuclear Information System (INIS)

    Kim, Young-Ki; Cho, Yeong-Garp; Kwag, Byung-Ho

    1999-01-01

    The HANARO is a 30 MW open pool type multi-purpose research reactor with forced light water coolant/moderator flows and heavy water annular reflector. The relatively small reactor core uses a low enriched fuel and is designed to maximize the power density, thus providing the required neutron flux for various research activities. It is mainly used for radioisotope production, nuclear material testing and neutron physics experiments. The initial criticality was achieved February 1995. Considering the importance of their functionality from the safety point of view, some components and equipment are categorized into a nuclear safety grade. There are three different inspection activities for the various reactor systems and components - a Surveillance Inspection(SI) for the safety grades and a Periodic Inspection (PI) for the non-safety grades and In-Service Inspection (ISI) for the ASME Sec.III components. All of the SIs are specified and required by the safety analysis report. The SI also differs from the PI in such a point that all kinds of activities for the SIs should be accompanied by an appropriate quality assurance, while for the PIs it is not necessarily mandatory. In addition, the inspection results for the SIs should go through an examination from regulatory body every two years and specific functions of the critical components or systems are demonstrated under the witness by the governmental inspector. The ISI is required and carried out as per international codes and standards as well as Korean atomic energy regulations. There are 54 SIs, 25 PIs and 4 ISIs for the HANARO. This paper concentrates on the managing strategy and its practices for the SIs and ISIs of the safety-related components, currently being done at HANARO. Most parts of the inspections fall into a group for the periodic performance testing and/or equipment calibration. Some mechanical inspections like a torque measurement are grouped into a preventive maintenance. Lastly the ASME Sec

  14. Enhancement of the reliability of automated ultrasonic inspections using tools of quantitative NDT

    International Nuclear Information System (INIS)

    Kappes, W.; Baehr, W.; Kroening, M.; Schmitz, V.

    1994-01-01

    To achieve reliable test results from automated ultrasonic inspection of safety related components, optimization and integral consideration of the various inspection stages - inspection planning, inspection performance and evaluation of results - are indispensable. For this purpose, a large potential of methods is available: advanced measurement techniques, mathematical-numerical modelling processes, artificial intelligence tools, data bases and CAD systems. The potential inherent in these methods to enhance inspection reliability is outlined by way of different applications. (orig.) [de

  15. Multispectral fluorescence imaging techniques for nondestructive food safety inspection

    Science.gov (United States)

    Kim, Moon S.; Lefcourt, Alan M.; Chen, Yud-Ren

    2004-03-01

    The use of spectral sensing has gained acceptance as a rapid means for nondestructive inspection of postharvest food produce. Current technologies generally use color or a single wavelength camera technology. The applicability and sensitivity of these techniques can be expanded through the use of multiple wavelengths. Reflectance in the Vis/NIR is the prevalent spectral technique. Fluorescence, compared to reflectance, is regarded as a more sensitive technique due to its dynamic responses to subtle changes in biological entities. Our laboratory has been exploring fluorescence as a potential means for detection of quality and wholesomeness of food products. Applications of fluorescence sensing require an understanding of the spectral characteristics emanating from constituents and potential contaminants. A number of factors affecting fluorescence emission characteristics are discussed. Because of relatively low fluorescence quantum yield from biological samples, a system with a powerful pulse light source such as a laser coupled with a gated detection device is used to harvest fluorescence, in the presence of ambient light. Several fluorescence sensor platforms developed in our laboratory, including hyperspectral imaging, and laser-induced fluorescence (LIF) and steady-state fluorescence imaging systems with multispectral capabilities are presented. We demonstrate the potential uses of recently developed fluorescence imaging platforms in food safety inspection of apples contaminated with animal feces.

  16. NIKHEF-K safety report 1982

    International Nuclear Information System (INIS)

    1983-12-01

    In this safety report, general information is offered about the safety policy at the NIKHEF-K institute Amsterdam. Costs, prevention, training courses and inspection related to (radiation) safety are briefly discussed. Small accidents are reported. Some measurements have been carried out, but no measurable increase of radiation doses have been found. (Auth.)

  17. The Determinants of Federal and State Enforcement of Workplace Safety Regulations: OSHA Inspections 1990-2010*

    Science.gov (United States)

    Jung, Juergen

    2013-01-01

    We explore the determinants of inspection outcomes across 1.6 million Occupational Safety and Health Agency (OSHA) audits from 1990 through 2010. We find that discretion in enforcement differs in state and federally conducted inspections. State agencies are more sensitive to local economic conditions, finding fewer standard violations and fewer serious violations as unemployment increases. Larger companies receive greater lenience in multiple dimensions. Inspector issued fines and final fines, after negotiated reductions, are both smaller during Republican presidencies. Quantile regression analysis reveals that Presidential and Congressional party affiliations have their greatest impact on the largest negotiated reductions in fines. PMID:24659856

  18. Development approach on usage of radiation and inspection of QA according to the change of approval procedure of safety regulatory guides

    International Nuclear Information System (INIS)

    Oh, B. J.; Ahn, H. Z.; Kim, S. W.; Yoo, S. O.; Kang, S. C.; Yang, S. H.; Han, S. J.; Kim, H. S.; Kim, H. J.

    2002-01-01

    In accordance with 2001 amendment of the Atomic Energy Act(AEA), KINS also amended its internal 'Regulation on Implementation of Entrusted AEA-related Work'. Up to now the nuclear safety-specialized institute has used its internally developed guidelines in the safety regulation. From now on, however, the institute will enhance the objectivity and transparency by having the instruments approved by the Ministry of Science ad Technology. In this paper, we introduced the major points and directions to be considered to the development of the safety regulatory guides on Inspection for the quality assurance of the nuclear reactor facilities and the use of radioisotopes, and review and inspection for dosimeter reading

  19. Safety procedures in operation of inspection and maintenance of pressure reduction and metering stations

    International Nuclear Information System (INIS)

    Villas Boas, Ademar Jose; Biesemeyer, Marco Aurelio R.

    2000-01-01

    Each local Natural Gas Distribution Company in Brazil has its own working procedures for operations of inspection and maintenance on equipment and accessories connected to the gas network. Some of these Companies developed a better elaborated and documented way of working routines, while others only work based on their operators experience. The objective of this work is to create a standard procedure for operations of inspection and maintenance of Pressure Reducing Stations and Metering Stations, mainly the ones concerned to safety aspects. This work has no intention of exhausting all aspects related to this subject but to become the first step to standardize these types of operations among Natural Gas Distribution Companies. (author)

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

    International Nuclear Information System (INIS)

    Tsuchiya, T.

    2007-01-01

    As several decades have passed since the construction of nuclear power plants began, residents have become gradually less interested in nuclear safety. The Tokai criticality accident in 1909, however, had roused residents in Tokai-Mura to realize that they live with nuclear technology risks. To prepare a field of risk communication, the Tokai-Mura C 3 project began as a pilot research project supported by NISA. Alter the project ended, we are continuing risk. communication activities as a non-profit organisation. The most important activity of C 3 project is the citizen's inspection programme for nuclear related facilities. This programme was decided by participants who voluntarily applied to the project. The concept of the citizen's inspection programme is 'not the usual facility tours'. Participants are involved from the planning stage and continue to communicate with workers of the inspected nuclear facility. Since 2003, we have conducted six programmes for five nuclear related organisations. Participants evaluated that radiation protection measures were near good but there were some problems concerning the worker's safety and safety culture, and proposed a mixture of advice based on personal experience. Some advice was accepted and it did improve the facility's safety measures. Other suggestions were not agreed upon by nuclear organisations. The reason lies in the difference of concept between the nuclear expert's 'safety' and the citizen's 'safety'. Residents do not worry about radiation only, but also about the facility's safety as a whole including the worker's safety. They say, 'If the workers are not safe, you also are unable to protect us'. Although the disagreement remained, the participants and the nuclear industry learned much about each other. Participating citizens received a substantial amount of knowledge about the nuclear industry and its safety measures, and feel the credibility and openness of the nuclear industry. On the other hand, the nuclear

  1. 49 CFR 193.2623 - Inspecting LNG storage tanks.

    Science.gov (United States)

    2010-10-01

    ... MATERIALS SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) PIPELINE SAFETY LIQUEFIED NATURAL GAS FACILITIES: FEDERAL SAFETY STANDARDS Maintenance § 193.2623 Inspecting LNG storage tanks. Each LNG... 49 Transportation 3 2010-10-01 2010-10-01 false Inspecting LNG storage tanks. 193.2623 Section 193...

  2. Inspection of licensee - Maintenance programme and activities

    International Nuclear Information System (INIS)

    2013-01-01

    An effective maintenance programme is critical to sustained safe and reliable operation of nuclear power plants. The Working Group on Inspection Practices (WGIP) concluded that when a licensee has an effective maintenance programme, the overall operating safety of the plant is improved and the protection of public health and safety enhanced. All Regulatory Bodies (RB) consider maintenance to be an important area for oversight. Although a variety of inspection practices are being used; RB are actively monitoring licensee performance. Specifically the following conclusions were reached and commendable practices identified: - Maintenance oversight by regulators appears to be in a stable continuous improvement state. Most regulators are executing inspection oversight based on an existing regulatory framework. - The performance of a licensee's maintenance programme is recognized as important part of maintaining nuclear safety. The result of the maintenance program assessment is included in the overall performance assessment of a license. - Maintenance inspection activities are recognized as an important part of the regulatory oversight process. Inspection activities are based on the safety significance and nature of work being performed by the licensee. - The effectiveness of the maintenance inspection activities is recognized to rely on properly qualified inspectors; who are adequately supported by specialists. Training and qualification of inspectors should be based on how the RB reviews and inspects licensee maintenance programmes. - Reporting requirements are identified to provide information on the licensees maintenance programme, and to help guide inspection activities. - Performance Indicators are recognized as a useful tool for helping focus regulatory activities. Basic PI are identified and tracked by the RB, and use of PI by the licensee is monitored. - Inspections are designed to confirm that the licensee is planning and scheduling maintenance with due

  3. Catalogue of requirements for a plant-specific safety inspection of German nuclear power plants taking into account the Fukushima-I (Japan) events; Anforderungskatalog fuer anlagenbezogene Ueberpruefungen deutscher Kernkraftwerke unter Beruecksichtigung der Ereignisse in Fukushima-I (Japan)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-03-30

    The catalogue of requirements for a plant-specific safety inspection of German nuclear power plants taking into account the Fukushima-I (Japan) events worked out by the German RSK (reactor safety commission) includes the following inspection topics: natural events like earth quakes, floods, weather-based consequences and possible superposition; civilization-based events like airplane crash, gas release, reactor accident consequences for neighboring units, terroristic impacts, external attacks on computer-based control systems. Further event-independent assumptions have to be considered: station blackout, long-term emergency power supply requirement, failure of auxiliary cooling water supply, efficacy of preventive measures, aggravating boundary conditions for the performance of emergency measures.

  4. Development of CANDU fuel in-bay inspection and dimensional measurement system

    Energy Technology Data Exchange (ETDEWEB)

    Jo, Chang Keun; Cho, Moon Sung; Suk, Ho Chun; Koo, Dae Seo; Park, Kwang June; Jun, Ji Su; Jung, Jong Yeob

    2004-09-01

    In this report, we describe a spent fuel inspection and dimensional measuring system for CANDU fuel bundles in atmosphere or water. The submissible camera with radiation resistance was used to inspect a spent fuel in water. The design criteria of the dimensional measuring system was set up {+-}0.01mm(10{mu}m) for measuring accuracy. The LVDT (Linear Variable Differential Transformer) was used as measuring sensor in this dimensional measuring system. An LVDT calibration equipment was developed in order to satisfy the required accuracy of the system. Also, aluminum master and CANDU Master with same dimension of fuel bundle was made to calibrate the mechanical error of the dimensional measuring system. The accuracy of the fuel inspection system was examined. The results show that the accuracy in dimensional measurement of fuel rod profile and bearing pad profile, diameter of fuel bundle, fuel rod length, and end plate profile using standard test equipment satisfies the design criteria, i.e., maximum measurement error of {+-}0.01mm(10{mu}m)

  5. Recent activities on clearance in IAEA and clearance automatic laser inspection system (CLALIS)

    International Nuclear Information System (INIS)

    Hattori, Takatoshi; Sasaki, Michiya

    2005-01-01

    Exemption levels for bulk amounts of materials have been described in RS-G-1.7 published as a safety guide in IAEA on August 2004. In Japan, the Nuclear Safety Commission adopted the RS-G-1.7 values as Japanese clearance levels after the careful review of dose assessment results. After completing revises of regulatory laws in relation to clearance level, solid wastes from decommissioning and operating nuclear power plants will be targets of clearance inspection. In CRIEPI, Clearance Automatic Laser Inspection System (CLALIS) has been developed, which can give high reliability and objectivity to the measurement data. The CLALIS is a new monitoring system coupling with 3D laser shape measurement, Monte-Carlo calculation and gamma measurement techniques, which can keep a high accuracy in the measurement data using an automatic correction technique for self-shielding effects of metal waste itself and is expected to apply as a practical use in actual clearance inspections. (author)

  6. Wireless Roadside Inspection Proof of Concept Test Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Capps, Gary J [ORNL; Franzese, Oscar [ORNL; Knee, Helmut E [ORNL; Plate, Randall S [ORNL; Lascurain, Mary Beth [ORNL

    2009-03-01

    The U.S. Department of Transportation (DOT) FMCSA commissioned the Wireless Roadside Inspection (WRI) Program to validate technologies and methodologies that can improve safety through inspections using wireless technologies that convey real-time identification of commercial vehicles, drivers, and carriers, as well as information about the condition of the vehicles and their drivers. It is hypothesized that these inspections will: -- Increase safety -- Decrease the number of unsafe commercial vehicles on the road; -- Increase efficiency -- Speed up the inspection process, enabling more inspections to occur, at least on par with the number of weight inspections; -- Improve effectiveness -- Reduce the probability of drivers bypassing CMV inspection stations and increase the likelihood that fleets will attempt to meet the safety regulations; and -- Benefit industry -- Reduce fleet costs, provide good return-on-investment, minimize wait times, and level the playing field. The WRI Program is defined in three phases which are: Phase 1: Proof of Concept Test (POC) Testing of commercially available off-the-shelf (COTS) or near-COTS technology to validate the wireless inspection concept. Phase 2: Pilot Test Safety technology maturation and back office system integration Phase 3: Field Operational Test Multi-vehicle testing over a multi-state instrumented corridor This report focuses on Phase 1 efforts that were initiated in March, 2006. Technical efforts dealt with the ability of a Universal Wireless Inspection System (UWIS) to collect driver, vehicle, and carrier information; format a Safety Data Message Set from this information; and wirelessly transmit a Safety Data Message Set to a roadside receiver unit or mobile enforcement vehicle.

  7. Review of activities relevant to in-service inspection

    International Nuclear Information System (INIS)

    Imanaka, N.

    1980-01-01

    Nuclear power plants are requested to provide continuing safety that cannot compare with other industries, as plant safety is a matter of much concern. To provide continuous assurance for plant safety there is increasing tendency to demand much of inspection of components during the lifetime. This inservice inspection of LMFBRs should be investigated from a view point of different systems and characteristics from LWRs. In this paper a review for inservice inspection of LMFBRs is described. To provide a continuous assurance of safety to the LMFBR, it is essential to develop how to construct the components to maintain the integrity throughout the service lifetime. Especially how to design is urged for this object. In-service inspection should be located only to compensate some uncertainty remained at the design stage, as it is too much complex in practice. As for inspection techniques, leak monitoring is assumed to be a best way to assure the plant safety continuously with the minimum plant outage time and minimum radioactive hazard to the inspectors

  8. Safety and Inspection Planning of Older Installations

    DEFF Research Database (Denmark)

    Sørensen, John Dalsgaard; Ersdal, G.

    2007-01-01

    A basic assumption often made in risk/reliability based inspection planning is that a Bayesian approach can be used. This implies that probabilities of failure can be updated in a consistent way when new information (from inspections and repairs) becomes available. The Bayesian approach and a no-...

  9. Safety and Inspection Planning of Older Installations

    DEFF Research Database (Denmark)

    Sørensen, John Dalsgaard; Ersdal, G.

    2008-01-01

    A basic assumption often made in risk- and reliability-based inspection planning is that a Bayesian approach can be used. This implies that probabilities of failure can be updated in a consistent way when new information (from inspections and repairs) becomes available. The Bayesian approach and ...

  10. Evaluation of radiological safety in industrial gammagraphy services during the construction of Bolivia-Brazil gas transmission lines (GASBOL), by regulatory inspections from brazilian CNEN

    International Nuclear Information System (INIS)

    Aquino, Josilto O. de; Silva, Francisco Cesar A. da; Leocadio, Joao Carlos; Pinho, Adaugoberto S. de; Souza, Luiz Antonio C. de; Lourenco, Manoel J.; Nicola, Marcello S.; Melo, Ivan F.

    2001-01-01

    This paper presents a brief description of the Brazilian Regulatory Authority's (National Commission of Nuclear Energy - CNEN) action about safety control on industrial radioactive installations. It shows some specific radiation safety inspections that were done during the construction of the Bolivia-Brazil Gas Transmission Line (GASBOL). In this GASBOL work, it was used industrial radiography sources for weld quality control. During two years were done thirty regulatory safety inspections in these movable installations that use gamma radiography devices. As final result, it was noticed that the national system of inspection to control the safe use of radioactive sources in industrial activities is really efficient because none overexposure was detect and every CNEN's recommendations were applied by the operators. Some result about the gamma devices and violations are also showed. (author)

  11. 9 CFR 381.309 - Finished product inspection.

    Science.gov (United States)

    2010-01-01

    ... Section 381.309 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE AGENCY ORGANIZATION AND TERMINOLOGY; MANDATORY MEAT AND POULTRY PRODUCTS INSPECTION AND VOLUNTARY INSPECTION AND CERTIFICATION POULTRY PRODUCTS INSPECTION REGULATIONS Canning and Canned Products § 381.309...

  12. Developing inspection strategies to support local activities

    DEFF Research Database (Denmark)

    Jensen, Per Langå

    2003-01-01

    An analysis of the Danish development in regulatory praxsis within occupational health and safety with a detailed description of Adapted Inspection.......An analysis of the Danish development in regulatory praxsis within occupational health and safety with a detailed description of Adapted Inspection....

  13. Recurrent safety inspection of German nuclear power plant - performance, schedule and goals. As of 11 August 1995; Periodische Sicherheitsueberpruefung (PSUe) fuer deutsche Kernkraftwerke - Durchfuehrung der PSUe. Vom 11. August 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-08-23

    The recurrent safety inspection is intended as an inspection supplementing the continuous operation monitoring activities within the framework given by the supervisory activities of the supervisory authority. The first recurrent safety inspection is scheduled to be performed about ten years after start-up of the plant, with subsequent inspection intervals to cover ten-year periods, and recorded operating and monitoring results to be taken into account at each recurrent inspection. The purpose of the recurrent safety inspections is to ascertain that post-inspection operation of the plant meets the then required safety standards. Significant testing results of the latest inspection are to be analysed and compared with regard to the current state of the art and operating results accumulated since the previous inspection, for subsequent definition of enhancements if required. (orig./HP) [Deutsch] Die PSUesoll eine Ergaenzung der staendigen Ueberpruefung im Rahmen der atomrechtlichen Aufsicht ueber den Betrieb sein. Eine erstmalige PSUesoll etwa zehn Jahre nach Inbetriebnahme erfolgen. Die weiteren Ueberpruefungen sollen danach jeweils im Abstand von etwa zehn Jahren stattfinden. Die zwischenzeitlichen Erfahrungen aus Betrieb und Aufsicht sind einzubeziehen. Ziel der PSUemuss sein, festzustellen, ob die Anlage auch im Hinblick auf den kuenftigen Betrieb ein ausreichendes Sicherheitsniveau besitzt. Zu diesem Zweck muessen repraesentative Ereignisse dann detailliert untersucht werden, wenn neue Erkenntnisse aus Forschung und Entwicklung sowie aus der Betriebserfahrung seit der letzten Periodischen Sicherheitsueberpruefung dies erfordern. (orig./HP)

  14. 9 CFR 318.309 - Finished product inspection.

    Science.gov (United States)

    2010-01-01

    ... Section 318.309 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE AGENCY ORGANIZATION AND TERMINOLOGY; MANDATORY MEAT AND POULTRY PRODUCTS INSPECTION AND VOLUNTARY... Canning and Canned Products § 318.309 Finished product inspection. (a) Finished product inspections must...

  15. 9 CFR 355.7 - Inauguration of inspection.

    Science.gov (United States)

    2010-01-01

    ... INSPECTION AND CERTIFICATION CERTIFIED PRODUCTS FOR DOGS, CATS, AND OTHER CARNIVORA; INSPECTION... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Inauguration of inspection. 355.7 Section 355.7 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE...

  16. Measures to ensure safety of radioactive materials in India

    International Nuclear Information System (INIS)

    Ghosh, P.K.; Sonawane, A.U.; Rane, D.M.

    2001-01-01

    In India, the use of ionizing radiation sources in industry, medicine, agriculture and research registered a significant increase during recent years. The basis of legislative control of the use of radiation in India is the Atomic Energy Act from 1962, which empowers the central Government to provide control over radioactive substances. Exercising these powers, the central Government has promulgated several radiation safety rules, which specify the requirements of licensing, the duties and responsibilities of radiation safety officers, powers of inspection, etc. Later in 1983, by the Act, the Atomic Energy Regulatory Board (AERB) was constituted by the central Government to exercise regulatory and safety functions. The report describes the existing system of regulatory control of radiation sources in India and in particular, refers to the regulatory documents prepared by the AERB, the type approval of radiation equipment, the regulatory consent for every person handling radioactive sources, and the inspection activities and enforcement of regulatory actions. The report also explains how management of disused sources is carried out in India, including the handling of accidents and emergency activities. (author)

  17. 49 CFR 396.13 - Driver inspection.

    Science.gov (United States)

    2010-10-01

    ... ADMINISTRATION, DEPARTMENT OF TRANSPORTATION FEDERAL MOTOR CARRIER SAFETY REGULATIONS INSPECTION, REPAIR, AND MAINTENANCE § 396.13 Driver inspection. Before driving a motor vehicle, the driver shall: (a) Be satisfied that the motor vehicle is in safe operating condition; (b) Review the last driver vehicle inspection...

  18. Modeling of a remote inspection system for NSSS components

    International Nuclear Information System (INIS)

    Choi, Yoo Rark; Kim, Jae Hee; Lee, Jae Cheol

    2003-03-01

    Safety inspection for safety-critical unit of nuclear power plant has been processed using off-line technology. Thus we can not access safety inspection system and inspection data via network such as internet. We are making an on-line control and data access system based on WWW and JAVA technologies which can be used during plant operation to overcome these problems. Users can access inspection systems and inspection data only using web-browser. This report discusses about analysis of the existing remote system and essential techniques such as Web, JAVA, client/server model, and multi-tier model. This report also discusses about a system modeling that we have been developed using these techniques and provides solutions for developing an on-line control and data access system

  19. Safety-related subject fields, institutions, associations, inspection boards and authorities

    International Nuclear Information System (INIS)

    Cebulla, E.

    1986-01-01

    The chapter outlines the various branches of industry where safety plays an important role, adapting the scheme applied by the Federal German Labour Office. The various sections of this chapter deal with legal provisions and relevant institutions, with natural and man-made hazards, with industrial systems requiring inspection and surveillance, with agriculture and forestry including animal husbandry, with manufacturing branches, the building industry, traffic and transport, with the services sector, househoulds, leisure and sports, and with establishments and activities where the handling of radioactive substances is a major source of hazards (e.g. in the medical field, for which a particularly extensive literature index is given). Aspects of power supply industries and water pollution prevention are discussed where appropriate. (DG) [de

  20. Findings of the inspection grading system on industrial radiography

    International Nuclear Information System (INIS)

    Gloria Doloressa

    2011-01-01

    The use of industrial radiography techniques evolve rapidly and widely. Various jobs in industry require the examination of welding techniques / connecting pipes and metal construction. The use of industrial radiography is one type of utilization of nuclear energy must get control so that its use does not cause harmful impacts to worker safety, community, and environment. Regulations is done through inspections, in order to supervise the observance of the terms in the licensing and legislation in the field of nuclear safety. The main purpose of inspection is to ensure the utilization of radiation sources of radiation have been used with. Findings of the inspection is a decline in the performance of licensees in meeting safety requirements. The Grading System to the findings of the inspection needs to be done to improve the effectiveness and efficiency of inspection, and it is expected that the company can improve the management of radiation safety. (author)

  1. Opinions of the well-informed persons about the nuclear reactor facility periodical inspection

    International Nuclear Information System (INIS)

    Aeba, Yoichi; Ishikawa, Michio; Enomoto, Toshiaki; Oomori, Katsuyoshi

    2005-01-01

    Falsifications of self-inspection records in the shrouds and of leakage rates for containment vessels at TEPCO nuclear power plants destroyed public trust in nuclear safety. The Nuclear Reactor Regulation Law and Electric Utility Law were amended to enhance the nuclear safety regulation system. The major improvements are that operators are legally required to conduct inspection (periodical operator inspection) and recording and keeping inspection results. The operator performs 'periodical operator inspection' regularly, and Nuclear and Industrial Safety Agency (NISA) performs periodical inspection' about particularly important facilities/function in safety. Sixteen opinions of well-informed persons about the nuclear reactor facility periodical inspection were presented in this special number. Interval of periodical inspection less than thirteen months was disputed. Maintenance activities should be more rationalized based on risk information. (T. Tanaka)

  2. 29 CFR 1960.31 - Inspections by OSHA.

    Science.gov (United States)

    2010-07-01

    ... 29 Labor 9 2010-07-01 2010-07-01 false Inspections by OSHA. 1960.31 Section 1960.31 Labor... MATTERS Inspection and Abatement § 1960.31 Inspections by OSHA. (a) The Secretary or the Secretary's... scheduled inspections as an integral part of OSHA's evaluation of an agency's safety and health program in...

  3. Nondestructive web thickness measurement of micro-drills with an integrated laser inspection system

    Science.gov (United States)

    Chuang, Shui-Fa; Chen, Yen-Chung; Chang, Wen-Tung; Lin, Ching-Chih; Tarng, Yeong-Shin

    2010-09-01

    Nowadays, the electric and semiconductor industries use numerous micro-drills to machine micro-holes in printed circuit boards. The measurement of web thickness of micro-drills, a key parameter of micro-drill geometry influencing drill rigidity and chip-removal ability, is quite important to ensure quality control. Traditionally, inefficiently destructive measuring method is adopted by inspectors. To improve quality and efficiency of the web thickness measuring tasks, a nondestructive measuring method is required. In this paper, based on the laser micro-gauge (LMG) and laser confocal displacement meter (LCDM) techniques, a nondestructive measuring principle of web thickness of micro-drills is introduced. An integrated laser inspection system, mainly consisting of a LMG, a LCDM and a two-axis-driven micro-drill fixture device, was developed. Experiments meant to inspect web thickness of micro-drill samples with a nominal diameter of 0.25 mm were conducted to test the feasibility of the developed laser inspection system. The experimental results showed that the web thickness measurement could achieve an estimated repeatability of ± 1.6 μm and a worst repeatability of ± 7.5 μm. The developed laser inspection system, combined with the nondestructive measuring principle, was able to undertake the web thickness measuring tasks for certain micro-drills.

  4. Automated ultrasonic inspection of nuclear plant components

    International Nuclear Information System (INIS)

    Baron, J.A.; Dolbey, M.P.

    1982-01-01

    For reasons of safety and efficiency, automated systems are used in performing ultrasonic inspection of nuclear components. An automated system designed specifically for the inspection of headers in a nuclear plant is described. In-service inspection results obtained with this system are shown to correlate with pre-service inspection results obtained by manual methods

  5. Inspection and mitigating measures for life extension of nuclear power plant containment structures

    International Nuclear Information System (INIS)

    Meyers, B.L.; Daye, M.A.

    1989-01-01

    The subject of life extension of nuclear power plants has drawn considerable attention during the last few years. Interest in life extension initiated because of both safety and economic reasons. A number of evaluations have been performed. The main thrust of earlier work was directed toward evaluating the factors causing aging, and defining degradation sites, degradation mechanism and failure modes. At present, attention is directed toward establishing the appropriate inspection programs suitable for each of the defined aging sites. Some components and aging sites are already subjected to routine inspection programs such as the surveillance of post-tensioning system and the integrated leak rate test (ILRT) of prestressed concrete and reinforced concrete containments. The aging process affects mechanical, electrical and structural components in all types of containments. This paper addresses the structural components of PWR containments only and presents examples of inspection approaches and describes methods to prevent further degradation of select sites

  6. What kinds of injuries do OSHA inspections prevent?

    Science.gov (United States)

    Haviland, Amelia; Burns, Rachel; Gray, Wayne; Ruder, Teague; Mendeloff, John

    2010-08-01

    OSHA's enforcement program is one of the major public efforts to protect American workers. We examine both the scope of injury prevention that inspections can contribute and the types of standards that contribute the most. We linked Pennsylvania Department of Labor and Industry files for lost-time injuries and employment to calculate injury rates for 1998-2005 for all single-establishment manufacturing firms. We linked these to OSHA inspection records. Inspections with penalties did affect injury types unrelated to standards as well as those related. We also found again that citations for violations of the standard requiring personal protective equipment had the largest impact on preventing injuries. Programs requiring protective equipment use deserve added attention from consultants and inspectors. In addition, some inspections spur managers to undertake safety measures that go beyond compliance with standards. 2010 Elsevier Ltd. All rights reserved.

  7. Risk informed In-service Inspection

    International Nuclear Information System (INIS)

    Corak, Z.

    2003-01-01

    Safety of nuclear power plants is one of the most important conditions for their acceptance. Safety is being acheived by numerous methods and techniques in phase of design, manufacturing and maintenance of the nuclear power plants. In-service Inspection (ISI) has a significant role in avoidances of failure in components of nuclear power plants just the same as in assurance of their integrity. Non-destructive examinations are performed periodically in accordance with 10 CFR 50 50.55a and ASME Boiler and Pressure Vessel Code section XI which is referenced by 10 CFR 50.55a. Nondestructive examinations provide information about a current condition of equipment at nuclear power plants and about any damage, defect or degradation mechanism. A lot of effort is often spent in situations in which the probability of failure and their effects on safety have a very low impact. Practical experience shows that failures can often occur at locations where the inspection has never been performed. Costs and expenses of in-service inspections are very high. Therefore, the accent has to be on locations with significant risk to safety. Many years of nuclear power plants' operation and maintenance have resulted in a more broad knowledge of degradation mechanism and the most susceptible locations and huge databases of different nuclear power plants' components. U.S. Nuclear Regulatory Commission (NRC) and the nuclear industry have recognized that probabilistic risk assessment (PRA) has developed and changed to be more useful in improvement of traditional engineering approaches in nuclear power plants regulation. After the publication of its policy statement on the use of PRA in nuclear regulatory activities, the Commission ordered the NRC staff to develop a regulatory framework that incorporated risk insights. The American Society of Mechanical Engineers (ASME) initiated Code Case N-560, N-577, and N-578 that address the importance of categorization and inspection of piping using risk

  8. Barsebaeck power plant - safety and emergency measures

    International Nuclear Information System (INIS)

    Anon.

    1981-01-01

    A Swedish-Danish Committee on safety at the Swedish nuclear power plant Barsebaeck was established in 1979 in order to evaluate the nuclear safety at Barsebaeck with a view to the reactor accident at the Three-Mile-Island nuclear power plant March 28, 1979. According to the committees mandate the investigations of the Kemeny Commission, the Rogouin investigation, investigations of the American Nuclear Regulatory Commission, and the Swedish report ''Safe nuclear power'' have been taken into consideration by the Committee. Furthermore, it has formed the basis for the Committees work that the authority responsibility for the safety at Barsebaeck lies with the Swedish authorities, and that these authorities have evaluated the safety aspects before the permissions for operation of the Barsebaeck power plant were given and hereafter currently in connection with the inspection of the power plant. The report prepared by the Commission treats aspects as: a) Nuclear safety at the Barsebaeck power plant, b) reactor safety and emergency provisions, c) common elements in the emergency provision situation in Sweden and Denmark, d) ongoing investigations on course of events during accidents and release limiting safety systems. (BP)

  9. 9 CFR 355.21 - Products entering inspected plants.

    Science.gov (United States)

    2010-01-01

    ... INSPECTION AND CERTIFICATION CERTIFIED PRODUCTS FOR DOGS, CATS, AND OTHER CARNIVORA; INSPECTION... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Products entering inspected plants. 355.21 Section 355.21 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF...

  10. The use of risk indicators for establishing inspection and control priorities

    International Nuclear Information System (INIS)

    Alzbutas, R.; Klimasauskas, A.; Nedzinskas, L.

    2003-01-01

    Risk-informed approach used to support decision-making related to in-service inspections was considered in order to identify ways for establishing inspection and control priorities. The in-service inspection of piping in the Ignalina NPP has been selected as the object for research application, The inspection process studied was modelled using the integration of deterministic and probabilistic analysis methods, In order to optimize the inspection process, the focus was set on the highest risk measured as the conditional core damage frequency, It was produced by quantitatively estimated probabilities of different degradation states and conditional failure consequence probabilities, Comprehensive databases for calculation of such indicators (measures) were collected and analyzed, The failure statistical analysis as well as the evaluation of inspection efficiency expressed by the probability of defect detection was also used, The databases were further investigated with a closer attention to the data variation and comparison of risk measures using the developed software, The developed software was used to perform and administrate all the risk evaluations and ensure the possibilities to compare different options and perform sensitivity analysis, The risk measures helped to define an adequate inspection program and to focus inspections on the more important locations of the study systems, This approach allowed an optimisation of the inspection program while the probabilistic and fundamental deterministic safety requirements were maintained, The approaches to define an acceptable level of the inspection program were also considered. These approaches to define an acceptable risk were considered together with the means to reduce the number of inspection sites and the cumulative radiation exposure to the NPP inspection personnel with a reduction of overall risk, The investigated issues provided a good basis for drawing conclusions about the inspection priorities, to

  11. 33 CFR 3.40-15 - Sector New Orleans Marine Inspection Zone and Captain of the Port Zone; Marine Safety Unit Morgan...

    Science.gov (United States)

    2010-07-01

    ... 33 Navigation and Navigable Waters 1 2010-07-01 2010-07-01 false Sector New Orleans Marine....40-15 Sector New Orleans Marine Inspection Zone and Captain of the Port Zone; Marine Safety Unit Morgan City. Sector New Orleans' office is located in New Orleans, LA. A subordinate unit, Marine Safety...

  12. 30 CFR 56.4201 - Inspection.

    Science.gov (United States)

    2010-07-01

    ... Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR METAL AND NONMETAL MINE SAFETY AND HEALTH SAFETY AND HEALTH STANDARDS-SURFACE METAL AND NONMETAL MINES Fire Prevention and Control... following schedules: (1) Fire extinguishers shall be inspected visually at least once a month to determine...

  13. 30 CFR 57.4201 - Inspection.

    Science.gov (United States)

    2010-07-01

    ... Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR METAL AND NONMETAL MINE SAFETY AND HEALTH SAFETY AND HEALTH STANDARDS-UNDERGROUND METAL AND NONMETAL MINES Fire Prevention and Control... following schedules: (1) Fire extinguishers shall be inspected visually at least once a month to determine...

  14. Machine vision inspection of railroad track

    Science.gov (United States)

    2011-01-10

    North American Railways and the United States Department of Transportation : (US DOT) Federal Railroad Administration (FRA) require periodic inspection of railway : infrastructure to ensure the safety of railway operation. This inspection is a critic...

  15. 9 CFR 355.3 - Plants eligible for inspection.

    Science.gov (United States)

    2010-01-01

    ... INSPECTION AND CERTIFICATION CERTIFIED PRODUCTS FOR DOGS, CATS, AND OTHER CARNIVORA; INSPECTION... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Plants eligible for inspection. 355.3 Section 355.3 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE...

  16. Computed Radiography: An Innovative Inspection Technique

    International Nuclear Information System (INIS)

    Klein, William A.; Councill, Donald L.

    2002-01-01

    Florida Power and Light Company's (FPL) Nuclear Division combined two diverse technologies to create an innovative inspection technique, Computed Radiography, that improves personnel safety and unit reliability while reducing inspection costs. This technique was pioneered in the medical field and applied in the Nuclear Division initially to detect piping degradation due to flow-accelerated corrosion. Component degradation can be detected by this additional technique. This approach permits FPL to reduce inspection costs, perform on line examinations (no generation curtailment), and to maintain or improve both personnel safety and unit reliability. Computed Radiography is a very versatile tool capable of other uses: - improving the external corrosion program by permitting inspections underneath insulation, and - diagnosing system and component problems such as valve positions, without the need to shutdown or disassemble the component. (authors)

  17. Control of the Saclay CEA's base nuclear installations - Inspection n. INS-2010-CEASAC-0006 31 May 2010-4 June 2010 - Safety management

    International Nuclear Information System (INIS)

    2010-01-01

    This document reports an inspection dedicated to safety management, and performed by the ASN (the French Nuclear Safety Authority) on several nuclear installations present on the CEA's Saclay site. The inspected installations have been the INBs (base nuclear installations) number 35 (STEL), 40 (Osiris), 49 (LHA), 50 (LECI), 77 (Poseidon) and 101 (Orphee), and four departments (CCSIMN, USL2TI, SP2S and DANS) involved in safety or in charge of it. The report describes the requested corrective actions about the quality of the internal diagnosis, about the follow-up of actions and directives, about internal authorizations, about the follow-up of commitments, about second level control, about the management of the return on experience, about interesting events, about the control of subcontractors. Some additional information requests are also formulated

  18. Pre-service inspection and in-service inspection in Japan

    International Nuclear Information System (INIS)

    Uebayashi, T.; Miyake, Y.

    1985-01-01

    To ensure the safety of nuclear power plant, pre-service inspection/in-service inspection (PSI/ISI) has an important role, and informations obtained from various inspections during plant shut-down period are contributing to establish effective preventive maintenance activities for plant facilities. It might be said that the high level of availability of Japanese light-water nuclear power plants in these two or three years has been achieved by those efforts. In case of Japan, inspections to be carried out during scheduled plant shut-down period are not limited to code requirements but include many other inspections which are mostly reflected from troubles experienced in both domestic and overseas plants. Usually, those additional inspections are performed by Ministry of Trade and Industries' (MITI's) regulator and/or tentative requirement and considered as ISI in broad meaning. To achieve high availability of plant, it is essential to avoid unscheduled shut-down and to shorten inspection period. The developments of new technology to perform effective ISI for operating plants are continued, but on the other hand it is also very important to pay a great consideration to inspectability of the plants at the stage of plant engineering. With the leadership of MITI, improvement and standardization of light-water nuclear power plant has been proceeded and newly constructed plants have great advantage from the point of view on ISI

  19. Japanese regulatory practices on licensing, inspection, operational supervision and related standards

    International Nuclear Information System (INIS)

    Tatsuta, Yoshinori

    1991-01-01

    Japanese view on the safety of nuclear power plants is based on the concept that the primary responsibility for securing safety lies on electric power companies, installers of reactors. Under this concept, the Ministry of International Trade and Industry (MITI), in the course of designing and construction, has been performed an examination of the basic design and the detailed design of nuclear power plants, and in each stage of construction, a pre-operational inspection process. In addition, MITI, in operating stage, has been made throughgoing investigations on the cases of troubles and incidents as well as accidents that may affect operation, forcing utilities to take measures to prevent recurrence, and implementing safety regulation based on the 'preventive maintenance' including elaborate checkings and overhaulings at the periodical inspections conducted for a period of three to four months after every 12-month operation cycle under the laws and regulations. This paper discusses the current status of nuclear power development in Japan, safety regulatory systems, views on safety and future prospects of securing safety. (orig.)

  20. The computer vision in the service of safety and reliability in steam generators inspection services

    International Nuclear Information System (INIS)

    Pineiro Fernandez, P.; Garcia Bueno, A.; Cabrera Jordan, E.

    2012-01-01

    The actual computational vision has matured very quickly in the last ten years by facilitating new developments in various areas of nuclear application allowing to automate and simplify processes and tasks, instead or in collaboration with the people and equipment efficiently. The current computer vision (more appropriate than the artificial vision concept) provides great possibilities of also improving in terms of the reliability and safety of NPPS inspection systems.

  1. Thermographic inspection of pipes, tanks, and containment liners

    Energy Technology Data Exchange (ETDEWEB)

    Renshaw, Jeremy B., E-mail: jrenshaw@epri.com; Muthu, Nathan [Electric Power Research Institute, 1300 West WT Harris Blvd., Charlotte, NC 28262 (United States); Lhota, James R.; Shepard, Steven M., E-mail: sshepard@thermalwave.com [Thermal Wave Imaging, 845 Livernois St., Ferndale, MI 48220 (United States)

    2015-03-31

    Nuclear power plants are required to operate at a high level of safety. Recent industry and license renewal commitments aim to further increase safety by requiring the inspection of components that have not traditionally undergone detailed inspected in the past, such as tanks and liners. NEI 09-14 requires the inspection of buried pipes and tanks while containment liner inspections are required as a part of license renewal commitments. Containment liner inspections must inspect the carbon steel liner for defects - such as corrosion - that could threaten the pressure boundary and ideally, should be able to inspect the surrounding concrete for foreign material that could be in contact with the steel liner and potentially initiate corrosion. Such an inspection requires a simultaneous evaluation of two materials with very different material properties. Rapid, yet detailed, inspection results are required due to the massive size of the tanks and containment liners to be inspected. For this reason, thermal NDE methods were evaluated to inspect tank and containment liner mockups with simulated defects. Thermographic Signal Reconstruction (TSR) was utilized to enhance the images and provide detailed information on the sizes and shapes of the observed defects. The results show that thermographic inspection is highly sensitive to the defects of interest and is capable of rapidly inspecting large areas.

  2. Comparison of Survival and Safety Requirements in European Union for Recreational Craft Inspections. A Spanish Case Study

    Directory of Open Access Journals (Sweden)

    J. Torralbo

    2014-03-01

    Full Text Available Statistical data shows that a large number of maritime accidents are related to recreational craft. For instance, in Spain, more than fifty percent of the emergencies are related to pleasure boats at sea. Recreational craft marketed in the EU must comply with harmonized technical safety and environmental requirements defined by Directive 94/25/EC, as amended in 2003. On 28 December 2013, the new recreational craft directive 2013/53/EU was published in the Official Journal of the European Union. EU Member States have until 18 January 2016 to amend their national legislation and transpose the new directive. The current directive 94/25/EC as amended by directive 2003/44/EC will be repealed on 18 January 2016, after the full application of the new text. Although this directive, there is not a clear coordination and equivalence among the EU countries according to the survival and safety equipment compulsory for recreational crafts. The main purpose of this paper is to analyze and compare the types of survey / inspections to be carried in pleasure craft (non-commercial use, periodicity and required safety equipment in some member states of the European Union. A case study of Spain is presented. From the results obtained, we can make clear that in the European Union there is a lack of coordination in this area and indicate the need to unify a common pattern in inspections and survival and safety requirements of recreational boats in the EU.

  3. Inspection of licensee activities in emergency planning

    International Nuclear Information System (INIS)

    Van Binnebeek, J.J.; Gutierrez Ruiz, Luis Miguel; Bouvrie, E. des; Aro, Ilari; Gil, J.; Balloffet, Yves; Forsberg, Staffan; Klonk, H.; Lang, Hans-Guenter; Fichtinger, G.; Warren, T.; Manzella, P.; Gallo, R.; Koizumi, Hiroyoshi; Johnson, M.; Pittermann, P.

    1998-01-01

    The CNRA believes that safety inspections are a major element in the regulatory authority's efforts to ensure the safe operation of nuclear facilities. Considering the importance of these issues, the Committee has established a special Working Group on Inspection Practices (WGIP). The purpose of WGIP, is to facilitate the exchange of information and experience related to regulatory safety inspections between CNRA Member countries Following discussions at several meetings on the topic of what is expected by the regulatory body regarding inspection criteria, WGIP proposed putting together a compilation of Member countries practices on regulatory inspection practices with respect to licensee emergency planning. CNRA approved this task and this report. Information was collected from a questionnaire which was issued in 1996. The report presents information on regulatory inspection activities with respect to emergency planning in NEA Member countries. The focus of the report is on the third section. It reviews the similarities and differences in inspection practices to evaluate compliance with the requirements over which the regulatory body (RB) has jurisdiction

  4. UAV Low Altitude Photogrammetry for Power Line Inspection

    Directory of Open Access Journals (Sweden)

    Yong Zhang

    2017-01-01

    Full Text Available When the distance between an obstacle and a power line is less than the discharge distance, a discharge arc can be generated, resulting in the interruption of power supplies. Therefore, regular safety inspections are necessary to ensure the safe operation of power grids. Tall vegetation and buildings are the key factors threatening the safe operation of extra high voltage transmission lines within a power line corridor. Manual or laser intensity direction and ranging (LiDAR based inspections are time consuming and expensive. To make safety inspections more efficient and flexible, a low-altitude unmanned aerial vehicle (UAV remote-sensing platform, equipped with an optical digital camera, was used to inspect power line corridors. We propose a semi-patch matching algorithm based on epipolar constraints, using both the correlation coefficient (CC and the shape of its curve to extract three dimensional (3D point clouds for a power line corridor. We use a stereo image pair from inter-strip to improve power line measurement accuracy by transforming the power line direction to an approximately perpendicular to epipolar line. The distance between the power lines and the 3D point cloud is taken as a criterion for locating obstacles within the power line corridor automatically. Experimental results show that our proposed method is a reliable, cost effective, and applicable way for practical power line inspection and can locate obstacles within the power line corridor with accuracy better than ±0.5 m.

  5. The role of independent inspection in verification activities

    International Nuclear Information System (INIS)

    Fuerste, W.

    1982-01-01

    Independent inspection has its origin in the early Middle Ages, when kings prescribed to textile manufacturers a quality control by authorized inspectors. Independent inspection became more important with respect to the safety of workers in the industrial era beginning in the 18th century, when the high-pressure steam engines were introduced and many accidents and explosions of steam boilers occurred. Nowadays, independent inspection is of utmost importance, because the safety of the public is endangered by industrial plants located near highly populated areas. To better understand the role of independent inspection, the paper reviews its historical development in Europe from the Middle Ages to the 20th century. Most of the independent inspection associations in European countries were established after the second half of the 19th century and began with the surveillance of steam boilers. Nowadays, organizations like the TUEVs (Technical Inspection Agencies) in the Federal Republic of Germany perform expertise and inspection on behalf of the government in various fields of industrial safety. To show how independent inspection is involved in quality assurance, the methods practised in the United States of America and the Federal Republic of Germany are compared and future trends discussed. For developing countries starting with nuclear energy, it is important to consider the information and recommendations regarding independent inspection and its regulation as laid down in a number of publications in the IAEA NUSS Programme. (author)

  6. OHS Certification as Tool and Strategy in Labour Inspection

    DEFF Research Database (Denmark)

    Hendriksen, Kåre

    Certification of Occupational Health and Safety as Tool and Strategy in Labour Inspection Presentation of the project Certification of Occupational Health and Safety as Tool and Strategy in Labour Inspection financed by Nordic Council of Ministers. The project has analysed the new role...... 18001. Especially in Denmark this is the case, where certified companies a. o. are exempt from primary inspection, a development that can be seen as a slight successive privatization of regulation and inspection. The focused has been the validity of certification regarding to OHS performance...

  7. 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.)

  8. Advanced inspection technology for non intrusive inspection (NII) program

    International Nuclear Information System (INIS)

    Zamir Mohamed Daud

    2003-01-01

    In the current economic environment, plants and facilities are under pressure to introduced cost saving as well as profit maximising measures. Among the many changes in the way things are run is a move towards Risk Based Inspection (RBI), with an emphasis on longer operating periods between shutdowns as well as to utilise components to their maximum capability. Underpinning and RBI program requires good data from an effective online inspections program, which would not require the shutdown of critical components. One methodology of online inspection is known as Non Intrusive Inspection (NII), an inspection philosophy with the objective of replacing internal inspection of a vessel by doing Non Destructive Testing (NDT) and inspections externally. To this end, a variety of advanced NDT techniques are needed to provide accurate online measurements. (Author)

  9. Hanford site post-NPH building inspection plan

    International Nuclear Information System (INIS)

    Wagenblast, G.R. Westinghouse Hanford

    1996-01-01

    This plan establishes consistent post-NPH building inspection procedures and defines a procedure for prioritization of buildings for inspection to ensure the safety of facilities prior to reentry. Qualification of systems for restart of operation is not included. This plan takes advantage, where possible, of existing national procedures for post-NPH inspection of buildings, of existing structural design and evaluation documentation of Hanford facilities, and current and proposed seismic instrumentation located throughout the Hanford site. A list of buildings, prioritized according to current building safety function and building vulnerability (without regard for or information about a damaging natural forces event) is provided

  10. 47 CFR 80.59 - Compulsory ship inspections.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 5 2010-10-01 2010-10-01 false Compulsory ship inspections. 80.59 Section 80... STATIONS IN THE MARITIME SERVICES Applications and Licenses § 80.59 Compulsory ship inspections. (a) Inspection of ships subject to the Communications Act or the Safety Convention. (1) The FCC will not normally...

  11. Aspects of the Optimization on the In-Service Inspection

    International Nuclear Information System (INIS)

    Korosec, D.; Vojvodic Tuma, J.

    2002-01-01

    In the present paper, the aspects of optimizing In-Service Inspection (ISI) is discussed. Slovenian Nuclear Safety Administration (SNSA) and its authorized organization for the ISI activities, Institute of Metals and Technologies, are actually permanently involved in the ISI processes of the nuclear power plant (NPP) Krsko. Based on the previous experience on the ISI activities, evaluation of the results and review of the new ISI program, the decision was made to improve recent regulatory and professional practice. That means, the conclusion was made to optimize the evaluation process of the ISI as a process. Traditional criteria, standards and practice gives good fundament for the improvements implementation. Improvements can be done on the way that the more broad knowledge about safety important components of the systems shall bee added to the basic practice. It is necessary to identify conditions of the safety important components, such as realistic stress and fatigue conditions, material properties changes due aging processes, the temperature cycling effects, existing flaws characterization in the light of the previous detection and equipment technique used, assessment of the measurement accuracy on the results etc. In addition to the above mentioned, risk assessment and evaluation of the whole ISI shall be done. To do this it is necessary to made risk evaluation, based on previous structural element probability assessment. Probabilistic risk assessment is important and one of the most powerful tools in the ISI optimization. Some basic work on the filed of the risk informed methods related to the nuclear safety components has been already done. Based on reference documentation, the most important steps in risk informed ISI are discussed: scope definition, consequence evaluation, failure probability estimation, risk evaluation, non-destructive examination method selection and possibilities of implementation, monitoring and feedback. Recent experience on the ISI

  12. Using CID for internals visual inspection and measurement

    International Nuclear Information System (INIS)

    Anon.

    1991-01-01

    Solid state sensors for video camera applications, notably the CCD (charge coupled device), tend to be much more compact than conventional tubes and therefore offer advantages in remote viewing applications. A major drawback in the nuclear context, however, is their low tolerance to radiation. Recently, however, Electricite de France and the French company Image Technologie have been working on a solid state vision system using CID (Charge injection device) technology, which is radiation resistant up to 10 5 gamma absorbed dose. The particular application is inspection and measurement of clearances in PWR core guide tubes. The system promises to save outage time by combining metrology with visual inspection - effectively two tools in one. Clearance measurements are made via the screen on the operator's computerized control system using an electronic grid system. Images can then be stored on magnetic tape. The CID camera is located at the lower end of a system of linked rods. The rods connect to a special head at the upper end, which provides fine height adjustment of the tool assembly. (author)

  13. Radiation control in the nondestructive inspection

    International Nuclear Information System (INIS)

    Kariya, Yukihiro

    1982-01-01

    In the early days of radiation nondestructive inspection about ten years ago, the loss of radiation sources and careless radiation exposure gave the impression of radiography inspection being immediately slipshod management. In this problem, the peculiar nature of the business in this field is involved. In Nondestructive Inspection Co., Ltd., besides the safety management of radioisotopes, the radiation exposure control of personnel in the regular inspection of nuclear power plants has become increasingly important. The following matters are described: radiation utilization in nondestructive inspection (X- and #betta#-ray radiography, #betta#-ray leak test on shield), radiation control problems in nondestructive inspection business (the peculiar aspects of the business, the analysis of the incidents related with nondestructive inspection), and the practice of radiation control in nondestructive inspection in Nondestructive Inspection Co., Ltd. (Mori, K.)

  14. Improved plant availability by advanced condition based inspections

    International Nuclear Information System (INIS)

    Hulshof, Harry J.M.; Noteboom, Jan W.; Welberg, Paul G.M.; Bruijn, Leo E.

    2004-01-01

    An industrial plant has to operate safely, reliably and efficiently at the lowest possible cost. Plant availability plays an important role regarding economic life optimisation. Industrial installations that are under pressure and are operating at high temperatures have a limited life due to creep and fatigue. It is, therefore, of critical importance to know the location of any possible weak spots in the installation. To avoid safety risks, unplanned plant shutdown and, as a consequence, high costs for unavailability, cycling and repair, periodic inspections and strain measurements are recommended. A Speckle Image Correlation Analysis (SPICA) system enables on-stream measurement of deformation due to creep in critical areas like the heat-affected zone in welds. Plant management and operators use the strain measurements to take action when necessary and, consequently, prevent failures. In those plants that have been provided with SPICA-technology for some years plant availability has improved significantly as a result. Another important development for yielding improved availability concerns steam drums. During some 20 years, KEMA has been performing automated ultrasonic steam drum inspections from outside. The Dutch authorities accepted this methodology in this period as an alternative (rather than an addition) after several pilot projects. An advantage of this inspection methodology is the possibility to record of the inspection results and possibility of thus trending these data. The resulting reduction of through time appeared a major benefit for plant owners. Since the authorities adopted the RBI approach during the last 10 years, another advantage of the inspection methodology became apparent: complete scanning and recording of the inspection data of circumferential and longitudinal (butt and fillet) welds, inspection of nozzle welds and inner radius as well as corrosion mapping has been covering all higher risk areas in these drums. This enhanced inspection

  15. Improved plant availability by advanced condition based inspections

    Energy Technology Data Exchange (ETDEWEB)

    Hulshof, Harry J.M.; Noteboom, Jan W; Welberg, Paul G.M.; Bruijn, Leo E

    2004-06-01

    An industrial plant has to operate safely, reliably and efficiently at the lowest possible cost. Plant availability plays an important role regarding economic life optimisation. Industrial installations that are under pressure and are operating at high temperatures have a limited life due to creep and fatigue. It is, therefore, of critical importance to know the location of any possible weak spots in the installation. To avoid safety risks, unplanned plant shutdown and, as a consequence, high costs for unavailability, cycling and repair, periodic inspections and strain measurements are recommended. A Speckle Image Correlation Analysis (SPICA) system enables on-stream measurement of deformation due to creep in critical areas like the heat-affected zone in welds. Plant management and operators use the strain measurements to take action when necessary and, consequently, prevent failures. In those plants that have been provided with SPICA-technology for some years plant availability has improved significantly as a result. Another important development for yielding improved availability concerns steam drums. During some 20 years, KEMA has been performing automated ultrasonic steam drum inspections from outside. The Dutch authorities accepted this methodology in this period as an alternative (rather than an addition) after several pilot projects. An advantage of this inspection methodology is the possibility to record of the inspection results and possibility of thus trending these data. The resulting reduction of through time appeared a major benefit for plant owners. Since the authorities adopted the RBI approach during the last 10 years, another advantage of the inspection methodology became apparent: complete scanning and recording of the inspection data of circumferential and longitudinal (butt and fillet) welds, inspection of nozzle welds and inner radius as well as corrosion mapping has been covering all higher risk areas in these drums. This enhanced inspection

  16. Safety analysis of ventilation and inspection operations on barrels in which spent fuel elements are stored

    International Nuclear Information System (INIS)

    Pavlovic, R.; Todorovic, D.; Plecas, I.

    2000-01-01

    Safety analysis of possible accident during performing ventilation and inspection operations on barrels in which spent fuel elements are stored has been proposed. Investigation is confined to a case when primary contamination is localized to the disposal room and controlled release of gaseous effluents to the atmosphere. 85 Kr is the most important radionuclide considered risk estimation due to release of gaseous fission products (author) [sr

  17. In-service inspection and periodic testing

    International Nuclear Information System (INIS)

    Eisele, H.; Meyer, F.A.; Zipser, R.R.

    1981-01-01

    In-service inspections are performed to verify the operational safety, and maintenance work is performed to guarantee the availability. Below, the typical in-service inspections of a light-water reactor NPP (operated on a pressurized-water reactor/PWR/ or on a boiling-water reactor/BWR/) are described with details and examples of typical inspections, especially of recurrent performance tests of the systems. (orig./RW)

  18. In-service inspection and periodic testing

    International Nuclear Information System (INIS)

    Eisele, H.; Meyer, F.A.; Zipser, R.R.

    1980-01-01

    In-service inspections are performed to verify the operational safety, and maintenance work is performed to guarantee the availability. In the present paper, the typical in-service inspections of a light-water reactor NPP (operated on a pressurized-water reactor/PWR/ or on a boiling-water reactor/BWR/) are described with details and examples of typical inspections, especially of recurrent performance tests of the systems. (orig./RW)

  19. 47 CFR 80.903 - Inspection of radiotelephone installation.

    Science.gov (United States)

    2010-10-01

    ... ship passes the inspection, the technician will issue a Communications Act Safety Radiotelephony... 47 Telecommunication 5 2010-10-01 2010-10-01 false Inspection of radiotelephone installation. 80... Passenger Boats § 80.903 Inspection of radiotelephone installation. Every vessel subject to Part III of...

  20. Non-destructive inspection protocol for reinforced concrete barriers and bridge railings

    Energy Technology Data Exchange (ETDEWEB)

    Chintakunta, Satish R. [Engineering and Software Consultants, Inc., 14123 Robert Paris Ct., Chantilly, VA 20151 (United States); Boone, Shane D. [Federal Highway Administration, Turner Fairbank Highway Research Center, 6300 Georgetown Pike, McLean, VA 22101 (United States)

    2014-02-18

    Reinforced concrete highway barriers and bridge railings serve to prevent errant vehicles from departing the travel way at grade separations. Despite the important role that they play in maintaining safety and their ubiquitous nature, barrier inspection rarely moves beyond visual inspection. In August 2008, a tractor-trailer fatally departed William Preston Lane, Jr. Memorial Bridge after it dislodged a section of the bridge barrier. Investigations following the accident identified significant corrosion of the anchor bolts attaching the bridge railing to the bridge deck. As a result of the information gathered during its investigation of the accident, the National Transportation Safety Board (NTSB) made recommendations to the Federal Highway Administration concerning Non-Destructive Evaluation (NDE) of concrete bridge railings. The Center for nondestructive evaluation (NDE) at Turner Fairbank Highway Research Center in McLean, VA is currently evaluating feasibility of using four technologies - ground penetrating radar (GPR), ultrasonic pulse-echo, digital radiography and infrared thermal imaging methods to develop bridge inspection methods that augment visual inspections, offer reliable measurement techniques, and are practical, both in terms of time and cost, for field inspection work. Controlled samples containing predefined corrosion levels in reinforcing steel were embedded at barrier connection points for laboratory testing. All four NDE techniques were used in the initial phase I testing. An inspection protocol for detecting and measuring the corrosion of reinforced steel embedded in the anchorage system will be developed as part of phase II research. The identified technologies shall be further developed for field testing utilizing a structure with a barrier in good condition and a structure with a barrier in poor condition.

  1. Non-destructive inspection protocol for reinforced concrete barriers and bridge railings

    Science.gov (United States)

    Chintakunta, Satish R.; Boone, Shane D.

    2014-02-01

    Reinforced concrete highway barriers and bridge railings serve to prevent errant vehicles from departing the travel way at grade separations. Despite the important role that they play in maintaining safety and their ubiquitous nature, barrier inspection rarely moves beyond visual inspection. In August 2008, a tractor-trailer fatally departed William Preston Lane, Jr. Memorial Bridge after it dislodged a section of the bridge barrier. Investigations following the accident identified significant corrosion of the anchor bolts attaching the bridge railing to the bridge deck. As a result of the information gathered during its investigation of the accident, the National Transportation Safety Board (NTSB) made recommendations to the Federal Highway Administration concerning Non-Destructive Evaluation (NDE) of concrete bridge railings. The Center for nondestructive evaluation (NDE) at Turner Fairbank Highway Research Center in McLean, VA is currently evaluating feasibility of using four technologies - ground penetrating radar (GPR), ultrasonic pulse-echo, digital radiography and infrared thermal imaging methods to develop bridge inspection methods that augment visual inspections, offer reliable measurement techniques, and are practical, both in terms of time and cost, for field inspection work. Controlled samples containing predefined corrosion levels in reinforcing steel were embedded at barrier connection points for laboratory testing. All four NDE techniques were used in the initial phase I testing. An inspection protocol for detecting and measuring the corrosion of reinforced steel embedded in the anchorage system will be developed as part of phase II research. The identified technologies shall be further developed for field testing utilizing a structure with a barrier in good condition and a structure with a barrier in poor condition.

  2. CASTOR - Advanced System for VVER Steam Generator Inspection

    International Nuclear Information System (INIS)

    Mateljak, Petar

    2014-01-01

    From the safety point of view, steam generator is a very important component of a nuclear power plant. Only a thin tube wall prevents leakage of radioactive material from the primary side into the environment. Therefore, it is very important to perform inspections in order to detect pipe damage and apply appropriate corrective actions during outage. Application of the nondestructive examination (NDE) technique, that can locate degradation and measure its size and orientation, is an integral part of nuclear power plant maintenance. The steam generator inspection system is consisted of remotely controlled manipulator, testing instrument and software for data acquisition and analysis. Recently, the inspection systems have evolved to a much higher level of automation, efficiency and reliability resulting in a lower cost and shorter outage time. Electronic components have become smaller and deal with more complex algorithms. These systems are very fast, precise, reliable and easy to handle. The whole inspection, from the planning, examination, data analysis and final report, is now a highly automated process, which makes inspection much easier and more reliable. This paper presents the new generation of INETEC's VVER steam generator inspection system as ultimate solution for steam generator inspection and repair. (author)

  3. Application of risk based inspection as a part of life management of nuclear power plants

    International Nuclear Information System (INIS)

    Vinod, Gopika; Babar, A.K.; Saraf, R.K.; Kushwaha, H.S.; Venkat Raj, V.

    2002-01-01

    Full text: Risk Informed approach is a systematic effort to improve plant safety in a more efficient manner by distributing the available safety resources depending on the importance to plant safety. This approach has found immense application in various aspects associated with Nuclear Power Plants, including design, manufacturing, operation and regulation. Typical applications of Risk Informed approach are in Technical Specification, In-Service Inspection (ISI) requirements, Motor Operated Valve testing, Configuration Control etc. In order to cater to such variety of Probabilistic Safety Assessment (PSA) based Risk Informed requirements, a software package, 'Risk Monitor' has been developed by the authors. An important application of Risk informed approach that has been undertaken for Indian Pressurised Heavy Water Reactor (IPHWR) is towards Risk Informed In-Service Inspection (RI-ISI). Studies are being conducted to evolve an inspection plan that is optimised to provide effective inspections at the right location with a proper inspection frequency. Using risk informed approach, the identification of system / component for inspection resource allocation is based on the results from Level 1 PSA of a NPP. Even though this methodology can be employed on any of the nuclear components/systems such as mechanical systems, instrumentation, etc., as a starting point, piping has been considered for employing Risk Informed Inspection. Plant risk assessment is modelled through the analysis of Core Damage Frequency (CDF) using PSA models. Risk Informed Inspection program of piping involves the estimation of failure probability or frequency of a piping segment and estimation of consequences of piping failures. ISI program changes could affect the failure probability values of piping and can introduce a change in CDF. These effects can be brought out through the implementation of Risk Informed inspection strategy. Various importance measures like Fussel-Vesely, Birnbaum

  4. A longitudinal study to assess the role of sanitary inspections in improving the hygiene and food safety of eating establishments in a tertiary care hospital of North India

    Directory of Open Access Journals (Sweden)

    Puja Dudeja

    2017-01-01

    Full Text Available Introduction: Food safety inspections serve two purposes; determine compliance with the law and gather evidence for enforcement if there is noncompliance. The present study was conducted to assess the role of regular inspections on food safety in hospital premises. Methodology: This was an intervention based before and after study. A tool was prepared based on the Food Safety and Standards Regulations (FSSR (in India 2011. This included major, critical, and highly critical domains. Each item in the tool scored between 1 and 3 (poor, satisfactory, and good. Based on this, each eating establishment (EE was given a score on conformance to FSSR 2011. Monthly inspection was made over a year and corrective actions were suggested. Results: The minimum preintervention score was (41.28%, and maximum was (77.25%. There was no significant association between type of meal services and score EE (P > 0.05. Higher proportion of EEs within the hospital building had a satisfactory and good score as compared to EEs outside the hospital building but within hospital premises (P < 0.05. Postintervention, there was a significant change (increase in the scores of EEs. There was a significant increase in mean scores of EEs under major domains namely maintenance, layout of equipment, monitoring an detection, and elimination of food sources to the pests. Under critical and highly critical domains personal cleanliness, training, and self-inspection by food business operators improved significantly. Conclusion: Regular inspections can improve the food safety standards in EEs.

  5. An overview of the on-site inspection measurements from the non-proliferation experiment

    Energy Technology Data Exchange (ETDEWEB)

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

    1994-12-31

    An on-site inspection (OSI) is an in-person visit to site to collect data and examine evidence in order to determine the source of an ambiguous event detected via remote monitoring systems or other measures. Its purpose is to determine whether the treaty has been violated, to deter violations, and to build confidence. At the time of this writing, it is anticipated that the Comprehensive Test Ban Treaty (CTBT) being developed in the Conference on Disarmament will contain OSI provisions. In an era of testing moratoria, the Non-Proliferation Experiment (NPE) provided a unique opportunity to investigate candidate OSI techniques. On site inspections could occur in three different contexts: after-the-fact inspections based on information from remote monitoring systems; inspections prior to, during, and after large declared chemical explosions (e.g., a large mining explosion); continuous monitoring inspections with unattended sensors at certain agreed-upon sites (e.g., previous test sites). OSI monitoring techniques need to be designed to detect the phenomena and residual effects of nuclear explosions. In the underground case, the primary effects of interest for OSI are the electromagnetic pulse, shock waves, aftershocks, radioactive gas, rubble zone, and apical void. These effects are well known and the basic techniques for their detection well established. We designed our measurement program for the NPE to answer specific issues about these detection technologies. Our measurement program includes the following: zerotime electromagnetic measurements; seismic aftershock survey; before and after electrical soundings; gas tracers introduced into the explosive; before and after multispectral overhead imagery from low-flying aircraft; before and after geological surveys.

  6. MACS as a tool for international inspections

    Energy Technology Data Exchange (ETDEWEB)

    Curtiss, J.A.; Indusi, J.P.

    1995-08-01

    The MACS/ACRS (Managed Access by Controlled Sensing/Access by Controlled Remote Sensing) system is a collection of communication devices, video capability, and distance-measuring equipment which can effectively substitute for the physical presence of a challenge inspector within a facility. The MACS design allows growth of the prototype, developed in response to the Chemical Weapons Convention (CWC), into a versatile device for inspection of sensitive nuclear facilities under other international arrangements, for example the proposed Fissile Material Cutoff Convention. A MACS/ACRS-type system in a standard, international-recognized configuration could resolve sensitive information and safety concerns through providing a means of achieving the goals of an inspection while excluding the inspector. We believe the technology used to develop MACS for the Defense Nuclear Agency, followed by ACRS for the Department of Energy, is universally adaptable for minimally-intrusive managed-access international inspections of sensitive sites.

  7. MACS as a tool for international inspections

    International Nuclear Information System (INIS)

    Curtiss, J.A.; Indusi, J.P.

    1995-01-01

    The MACS/ACRS (Managed Access by Controlled Sensing/Access by Controlled Remote Sensing) system is a collection of communication devices, video capability, and distance-measuring equipment which can effectively substitute for the physical presence of a challenge inspector within a facility. The MACS design allows growth of the prototype, developed in response to the Chemical Weapons Convention (CWC), into a versatile device for inspection of sensitive nuclear facilities under other international arrangements, for example the proposed Fissile Material Cutoff Convention. A MACS/ACRS-type system in a standard, international-recognized configuration could resolve sensitive information and safety concerns through providing a means of achieving the goals of an inspection while excluding the inspector. We believe the technology used to develop MACS for the Defense Nuclear Agency, followed by ACRS for the Department of Energy, is universally adaptable for minimally-intrusive managed-access international inspections of sensitive sites

  8. An alternate approach to calibrating FAC-predictive models using inspection data (Log Book No. 398)

    International Nuclear Information System (INIS)

    Pulido, J.E.; Ksiazek, P.E.; Alecksick, R.M.

    2004-01-01

    Flow-Accelerated Corrosion (FAC) of piping and fittings in Nuclear Energy Plants can pose a threat to personnel safety, reduce plant availability, and result in undesirable challenges to plant safety systems. For these reasons, accurate predictions of FAC-induced wear rates are extremely valuable in that they allow action to be taken prior to component failure. The EPRI recommended method of predicting FAC wear rates for inspected as well as uninspected components allows for calibration of predictions through the use of wall thickness measurements obtained from UT inspections. This method uses a simple linear correction based on the median value of the ratio of measured to predicted thickness. An alternate approach is presented that takes local thermodynamic variations into account, thus resulting in an improved correlation with measured data. (author)

  9. Equipment inspection function; A funcao inspecao de equipamentos

    Energy Technology Data Exchange (ETDEWEB)

    Bressan, Edemir [PETROBRAS (Brazil). Refinaria Alberto Pasqualini

    1994-04-01

    Development of the safety engineering and equipment inspection policy in petroleum industry, with emphasis to the refineries equipment, are discussed. Presentation of the accidents percentages in petroleum plants under international researches, with details of involved equipment, kind of accident, plant and causes are reported. The start and actual stage of the safety inspection program in the PETROBRAS are also presented 5 refs., 3 figs.

  10. Licensee contractor and vendor inspection status report. Quarterly report, April 1982-June 1982

    International Nuclear Information System (INIS)

    1982-07-01

    Firms designing nuclear steam supply systems, architect engineering firms doing design work on nuclear power plants, and certain selected vendors are currently inspected on a regular basis by the NRC. NRC inspectors, during periodic inspections, ascertain through direct observation of selected activities (including review of processes and selected hardware, discussions with employees and selected record review) whether a licensee or contractor is satisfactorily implementing a quality assurance program. If nonconformances with QA commitments are found, the inspected organization is requested to take appropriate corrective action and to institute preventive measures to preclude recurrence. In addition to the QA program inspections, NRC also conducts reactive inspections of the licensee's contractors and vendors. These are special, limited scope inspections to verify that organizations supplying safety-related equipment or services to licensed facilities are exercising appropriate corrective/preventive measures when defects or conditions which could adversely affect the safe operation of such facilities are identified and that these organizations are complying with the NRC requirements which govern the evaluation and reporting of such conditions

  11. 9 CFR 381.197 - Imported products; foreign inspection certificates required.

    Science.gov (United States)

    2010-01-01

    ... AND VOLUNTARY INSPECTION AND CERTIFICATION POULTRY PRODUCTS INSPECTION REGULATIONS Imported Poultry... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Imported products; foreign inspection certificates required. 381.197 Section 381.197 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE...

  12. Bridging of inspection with corrosion management

    International Nuclear Information System (INIS)

    Zamaluddin Ali; Mohd Hawari Hassan; Rohana Jaafar

    2009-01-01

    Formerly, Inspection and Corrosion Engineers have less interaction and sharing of information to each other even they are working in the same plant or organization. Inspection finding either from visual inspection or NDT techniques rarely shared with corrosion engineers. Similarly corrosion engineers rarely discussed their corrosion prediction and potential damage mechanism with inspection engineers. A demanding request of more holistic plant safety and asset integrity promoted the introduction and implementation of Risk Based Inspection (RBI). RBI analysis demands the input mainly from both disciplines i.e. Inspection and Corrosion Engineers. Most of RBI methodologies are once-off analysis approach which also promoted once-off interaction between Inspection and Corrosion Engineers. PETRONAS has developed a methodology with supporting software, integrating both Inspection and Corrosion disciplines. PETRONAS Risk Based Inspection (PRBI) is intended to promote continuous integration of Inspection and Corrosion management of the plant through out the whole life cycle starting from the design stage to fabrication, operation and decommissions stage. (author)

  13. Phase I Inspection Report. National Dam Safety Program. Round Valley South Dam, Hunterdon County, New Jersey.

    Science.gov (United States)

    1978-05-01

    defined by the Recommended Guidelines for Safety Inspection of Dams. .M • wwM •^^^nmifgnmmmm’m •PH J.I.I MPU C. Hazard Classification - The...Conservation and Economic Development, August 1958. 3) Contract RV-1, State of New Jersey Department of Conservation and Economic Development...FIGURE 4 iymmmmr STATE OF NEW JERSEY DEPARTMENT OF CONSERVATION AND ECONOMIC DEVFl OtVNKM OF WATNt FOUCY «MO mm 1 ROUND VALLEY RESERVOIR

  14. Nuclear power safety

    International Nuclear Information System (INIS)

    1988-01-01

    The International Atomic Energy Agency, the organization concerned with worldwide nuclear safety has produced two international conventions to provide (1) prompt notification of nuclear accidents and (2) procedures to facilitate mutual assistance during an emergency. IAEA has also expanded operational safety review team missions, enhanced information exchange on operational safety events at nuclear power plants, and planned a review of its nuclear safety standards to ensure that they include the lessons learned from the Chernobyl nuclear plant accident. However, there appears to be a nearly unanimous belief among IAEA members that may attempt to impose international safety standards verified by an international inspection program would infringe on national sovereignty. Although several Western European countries have proposed establishing binding safety standards and inspections, no specific plant have been made; IAEA's member states are unlikely to adopt such standards and an inspection program

  15. Optimal replacement and inspection periods of safety and control boards in Wolsung nuclear power plant unit 1

    International Nuclear Information System (INIS)

    Mok, Jin Il

    1993-02-01

    upon to act when emergency conditions develop. To ensure their operability, the systems are periodically tested. In this paper, unavailability formulae for 2-out-of-3 logic configurations are developed, taking into account the probability of failure of channels tested due to human error in the simultaneous testing scheme. The probability of the channel being down due to human error is assumed to depend on the number of channel which have gone through the tests consecutively prior to the inspection of the channel under consideration. The system unavailability is the sum of unavailability due to hardware failure alone and the unavailability contribution due to human error. And we considered the probability that the reactor will be tripped during surveillance test. We determined the optimal inspection periods of safety system, taking into account both unavailability of safety system and the probability that the reactor will be tripped during surveillance test. We compared these periods with the inspection periods currently used at Wolsung NPP Unit 1. As a consequence, the inspection periods obtained using a minimum human error (8.24 x 10 -6 ) are shorter than those currently used in Wolsung NPP unit 1 while inspection periods obtained using a maximum human error is (4.44 x10 -4 ) longer than those used in Wolsung NPP unit 1

  16. International cooperation in production inspections

    International Nuclear Information System (INIS)

    Limousin, S.

    2009-01-01

    Nuclear pressure equipment, like the reactor pressure vessel or steam generators, are manufactured in many countries all around the world. As only few reactors were built in the 90's, most of the nuclear safety authorities have lost part of their know how in component manufacturing oversight. For these two reasons, vendor inspection is a key area for international cooperation. On the one hand, ASN has bilateral relationships with several countries (USA, Finland, China...) to fulfill specific purposes. On the other hand, ASN participates in international groups like the MDEP ( Multinational Design Evaluation Program). A MDEP working group dedicated to vendor inspection cooperation enables exchanges of informations (inspection program plan, inspection findings...) among the regulators. Join inspections are organized. International cooperation could lead in the long term to an harmonization of regulatory practices. (author)

  17. 75 FR 56015 - Vessel Inspection Alternatives

    Science.gov (United States)

    2010-09-15

    ... DEPARTMENT OF HOMELAND SECURITY Coast Guard 46 CFR Part 8 Vessel Inspection Alternatives CFR... Certificate; (ii) International Tonnage Certificate; (iii) Cargo Ship Safety Construction Certificate; (iv) Cargo Ship Safety Equipment Certificate; and (v) International Oil Pollution Prevention Certificate; and...

  18. Utilization of aging program results in plant inspections

    International Nuclear Information System (INIS)

    Gunther, W.; Fullwood, R.

    1989-01-01

    Research conducted under the auspices of the US Nuclear Regulatory Commission Nuclear Plant Aging Research (NPAR) Program has resulted in a large data base of component and system operating experience. This data base has been used to determine equipment aging susceptibility and the potential for equipment aging to impact plant safety and reliability. Methods of detecting and mitigating component and system aging have also been identified. This paper discusses how the NPAR results could be used to focus inspection activities on age-sensitive components and systems and on the specific modes and mechanisms of age degradation. These activities range from the regular inspections conducted by resident inspectors to extensive special inspections such as the Safety System Functional Inspection typically conducted by a team of inspectors. 5 refs., 3 figs., 1 tab

  19. Utilization of aging program results in plant inspections

    International Nuclear Information System (INIS)

    Gunther, W.; Fullwood, R.

    1988-01-01

    Research conducted under the auspices of the US Nuclear Regulatory Commission Nuclear Plant Aging Research (NPAR) Program has resulted in a large data base of component and system operating experience. This data base has been used to determine equipment aging susceptibility and the potential for equipment aging to impact plant safety and reliability. Methods of detecting and mitigating component and system aging have also been identified. This paper discusses how the NPAR results could be used to focus inspection activities on age-sensitive components and systems and on the specific modes and mechanisms of age degradation. These activities range from the regular inspections conducted by resident inspectors to extensive special inspections such as the Safety System Functional Inspection typically conducted by a team of inspectors. 5 refs., 3 figs., 1 tab

  20. Inspection systems for valves monitoring at EDF

    International Nuclear Information System (INIS)

    Germain, J.L.; Granal, L.; Provost, D.; Touillez, M.

    1997-01-01

    Electricite de France (EDF) makes increasing use of valve inspection systems to guarantee safety in its pressurized water reactor plants, improve plant availability and facilitate condition-based maintenance. A portable system known as SAMIR has been developed for inspection of motor-operated valves, and is now used on EDF's 900-MW sites. For its 1300-MW units, EDF has chosen a more complete system which enables measuring thrust on the valve stem during a maneuver, using a sensor mounted on the yoke. To detect internal vale leaks, an on-site assessment has demonstrated the economic benefits of acoustic emission techniques. EDF has equipped its sites with analog leak detection systems which may soon be replaced by a digital model now being developed. (authors)

  1. In service inspection of SUPERPHENIX 1 vessels: MIR

    International Nuclear Information System (INIS)

    Asty, M.; Viard, J.; Lerat, B.; Saglio, R.

    1985-01-01

    Although no in-service inspection constraints were imposed on the Phenix vessels, the Safety Authorities asked that the design of SUPERPHENIX 1 makes it possible to monitor throughout the lifetime of the reactor, surface and internal defects on the main vessel. A pool design and the presence of heat baffles inside the main vessel make access from the inside of the vessel impossible. Thus, an inspection can only be performed from the outside of the main vessel: the distance between the walls of the main and safety vessels is such that an inspection device can be introduced into the corresponding space. As the design of the reactor precludes radiographic inspection, the method which was selected for monitoring internal defects in the main vessel is ultrasonics. However, the anisotropic structure of austenitic stainless steel welds limits the performance of this technique. The authors present the in-service inspection device, MIR, which has been specially developed for the visual and ultrasonic examination of SUPERPHENIX 1 vessels

  2. Inspection of the Sizewll 'B' reactor coolant pump flywheels

    International Nuclear Information System (INIS)

    McNulty, A.L.; Cheshire, A.

    1992-01-01

    The Sizewell ''B'' safety case has categorised some primary circuit items as components for which failure is considered to be incredible. These Incredibility of Failure (IOF) components are particularly critical in their safety function, and specially stringent and all embracing provisions are made in their design, manufacture, inspection and operation. These provisions are such as to limit the probability of failure to levels which are so low that it does not have to be taken into account and no steps are necessary to control the consequences. The reactor coolant pump flywheel is considered to be an IOF component. Consequently there is a need for rigorous inspection during both manufacture and in service (ISI). The ISI requirement results in the need for an automated inspection. There is therefore a prerequisite to perform a Pre-Service Inspection (PSI) for baseline fingerprinting purposes. Furthermore there is a requirement that the inspection procedure, the inspection equipment and the operators are validated at the Inspection Validation Centre (IVC) of the AEA Technology laboratories at Risley. Development work is described. (author)

  3. In-service inspection of nuclear power plants

    International Nuclear Information System (INIS)

    1991-01-01

    This Manual is intended to provide more comprehensive considerations on the management, organization, preparation, improvement and implementation of in-service inspection activities and the related surveillance. It also gives illustrative examples of good practices and recommendations from operating and other organizations that are consistent with the requirements and recommendations of the Code and Safety Guides. The Manual is directed primarily towards plant management. This Manual should be used in conjunction with the Code and the Safety Guides, in particular with IAEA Safety Series Nos. 50-C-O, 50-SG-O2, 50-SG-05, 50-SG-07, 50-SG-08 and 50-SG-D1, which contain recommendations of a general character about maintenance activities and radiation protection in an operating power plant, and with the 'Manual on the Maintenance of Systems and Components Important to Safety'. This Manual is divided into four technical sections. The first introduces the purpose, structure and main requirements of the programme. The second section describes constituents of the programme, recommending its scope, scheduling, acceptance standards and documentation of results. The following section goes into details of the inspection programme's contents, such as the selection of components, inspection locations, defect types, applicable techniques and procedures, and the evaluation of results. The last section specifies recommended methods and techniques for inspection, such as visual, ultrasonic, eddy current, magnetic particle and others. This main part of the Manual is complemented by a number of annexes which reproduce actual national examples of established procedures, ISI programme parts, acceptance standards, personnel training programmes, testing techniques and other aspects of in-service inspection, illustrating practical implementation of the recommendations of the Manual

  4. Safety aspects and operating experience of LWR plants in Japan

    International Nuclear Information System (INIS)

    Aoki, S.; Hinoki, M.

    1977-01-01

    From the outset of nuclear power development in Japan, major emphasis has been placed on the safety of the nuclear power plants. There are now twelve nuclear power plants in operation with a total output of 6600 MWe. Their operating records were generally satisfactory, but in the 1974 to 1975 period, they experienced somewhat declined availability due to the repair work under the specific circumstances. After investigation of causes of troubles and the countermeasures thereof were made to ensure safety, they are now keeping good performance. In Japan, nuclear power plants are strictly subject to sufficient and careful inspection in compliance with the safety regulation, and are placed under stringent radiation control of employees. Under the various circumstances, however, the period of annual inspection tends to be prolonged more than originally planned, and this consequently is considered to be one of the causes of reduced availability. In order to develop nuclear power generation for the future, it is necessary to put further emphasis on the assurance of safety and to endeavor to devise measures to improve availability of the plants, based on the careful analysis of causes which reduce plant availability. This paper discusses the results of studies made for the following items from such viewpoints: (1) Safety and Operating Experience of LWR Nuclear Power Plants in Japan; a) Operating experience with light water reactors b) Improvements in design of light water reactors during the past ten years c) Analysis of the factors which affect plant availability; 2) Assurance of Safety and Measures to Increase Availability a) Measures for safety and environmental protection b) Measures to reduce radiation exposure of employees c) Appropriateness of maintenance and inspection work d) Measures to increase plant availability e) Measures to improve reliability of equipments and components; and 3) Future Technical Problems

  5. Knowledge-Based Inspection Capabilities

    National Research Council Canada - National Science Library

    Marrano, Lance R; Grussing, Michael N

    2006-01-01

    ... does not present a compelling safety hazard. Abandoning certain inspection programs to reduce costs is not a viable alternative, however, because that could degrade real property investments, soldier quality of life, and mission-readiness...

  6. 9 CFR 381.199 - Inspection of poultry products offered for entry.

    Science.gov (United States)

    2010-01-01

    ... AND VOLUNTARY INSPECTION AND CERTIFICATION POULTRY PRODUCTS INSPECTION REGULATIONS Imported Poultry... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Inspection of poultry products offered for entry. 381.199 Section 381.199 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE...

  7. Risk informed approach to the in-service inspection activities

    International Nuclear Information System (INIS)

    Korosec, D.; Vojvodic Tuma, J.

    2004-01-01

    In the present paper, the aspects of Risk Informed In-Service Inspection (RI-ISI) are discussed. Slovenian Nuclear Safety Administration (SNSA) and its authorized organization for the ISI activities, Institute of Metals and Technologies (IMT), are actually permanently involved in the ISI processes of the nuclear power plant (NPP) Krsko. Based on the previous experience on the ISI activities, evaluation of the results and review of the existing practice in nuclear world, the activities are started to asses the piping of systems in the light of probability of failure. This is so called Risk Informed approach. By the design established criteria, standards and practice gives good fundaments for the improvements implementation. Improvements can be done on the way that the more broad knowledge about safety important components of the systems shall bee added to the basic practice. It is necessary to identify conditions of the safety important components, such as realistic stress and fatigue conditions, material properties changes due aging processes, the temperature cycling effects, existing flaws characterization in the light of the previous detection and equipment technique used, assessment of the measurement accuracy on the results etc. In addition to this deterministic approach, the principles of risk evaluation methods should be used. NPP Krsko has, as practically majority of NPP's, probabilistic risk assessment (PRA) studies for all safety important systems and components. The methods and results from these studies can be efficiently used to upgrade classical deterministic results, based on which the in-service program as a whole is usually done. In addition to the above mentioned, risk assessment and evaluation of the piping shall be done, which is not covered by the existing PRA analysis. To do this it is necessary to made risk evaluation of the piping segments, based on previous structural element probability assessment. Probabilistic risk assessment is important

  8. 33 CFR 3.40-28 - Sector Houston-Galveston Marine Inspection Zone and Captain of the Port Zone; Marine Safety Unit...

    Science.gov (United States)

    2010-07-01

    ... 33 Navigation and Navigable Waters 1 2010-07-01 2010-07-01 false Sector Houston-Galveston Marine....40-28 Sector Houston-Galveston Marine Inspection Zone and Captain of the Port Zone; Marine Safety Unit Port Arthur. Sector Houston-Galveston's office is located in Galena Park, TX. A subordinate unit...

  9. The applications of risk-informed in-service-inspection

    International Nuclear Information System (INIS)

    Ting, K.; Ko, T.-H.; Li, Y.-C.; Wu, W.-F.; Lu, Y.-L.; Chien, F.-T.

    2005-01-01

    The US NRC and nuclear industry encouraged the applications of risk-informed In-Service Inspection (RI-ISI) which can be an alternative program to the ASME Section XI In-service Inspection requirements. The Implementation of RI-ISI can improve the substantial cost as well as does reductions. From the aspect of defense in depth for nuclear safety, the achievements of these procedures can identify the inspection rank to promote the integrity of the current inspection program. Thus, this study utilizes this techniques to implement risk assessment on safety class 1 recirculation piping welds where sensitized to IGSCC of Taibei BWR-6 nuclear power plant. In the evaluation process, WinPraise code is used to calculate the failure probabilities of all welds. The result of risk evaluations can be referred to the further regulatory and plant operation. (authors)

  10. 9 CFR 381.14 - Inspection concerning purportedly exempted operations.

    Science.gov (United States)

    2010-01-01

    ... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Inspection concerning purportedly exempted operations. 381.14 Section 381.14 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE... make inspections in accordance with law to ascertain whether any of the provisions of the Act or the...

  11. In service inspection for Superphenix vessels development of ultrasonic techniques available at high temperature

    International Nuclear Information System (INIS)

    Gondard, C.

    1983-12-01

    The main and safety vessels of SUPERPHENIX 1 were designed to allow in-service inspections. The remote controlled inspection device MIR was developped for this purpose. The ultrasonic examination has required the development of all new transducers fitted with severe operating conditions prevailing in intervessels interval. A list of problems to be resolved and technological solutions which were found is given. Measurements of acoustical properties on actual probes are compared with theoretical values. It appears that concordance is good and that an in-service inspection using high temperature transducers is possible with a good spatial resolution and signal to noise ratio

  12. Which follow-up by the CLIs for the 3. decennial inspections?

    International Nuclear Information System (INIS)

    Rollinger, Francois; Delalonde, Jean-Claude; Rousseau, Jean-Marie; Paulmaz, Xavier; Junker, R.; Sene, M.; Hubert, F.; Paulmaz, X.; Tindillere, M.; Lheureux, Y.

    2010-11-01

    This document contains contributions presented by representatives of the IRSN, EDF and CLIs. The first session addressed issues related to decennial inspections. The contributions proposed a presentation of the safety re-examination of EDF 900 MWe reactors at the occasion of the 3. decennial inspections, a presentation of IRSN works on skill management in electric power production nuclear plants (CNPEs), a presentation (by EDF) of these 3. decennial inspections, a presentation (by the Fessenheim CLI) of the implementation of the 3. decennial inspection in Fessenheim, and a discussion by the Blayais CLI of follow-up perspectives after a decennial inspection. The second session addressed issues not related to decennial inspections. It contains two presentations respectively made by the Gravelines CLI (an analysis of significant safety events) and Dampierre CLI (problematic of skill management in CNPEs)

  13. Measurement system analysis for binary inspection: Continuous versus dichotomous measurands

    NARCIS (Netherlands)

    de Mast, J.; Erdmann, T.P.; van Wieringen, W.N.

    2011-01-01

    We review methods for assessing the reliability of binary measurements, such as accept/reject inspection in industry. Our framework introduces two factors that are highly relevant in deciding which method to use: (1) whether a reference value (gold standard) can be obtained and (2) whether the

  14. Nuclear power plant pressure vessels. Inservice inspections

    International Nuclear Information System (INIS)

    1995-01-01

    The requirements for the planning and reporting of inservice inspections of nuclear power plant pressure vessels are presented. The guide specifically applies to inservice inspections of Safety class 1 and 2 nuclear power plant pressure vessels, piping, pumps and valves plus their supports and reactor pressure vessel internals by non- destructive examination methods (NDE). Inservice inspections according to the Pressure Vessel Degree (549/73) are discussed separately in the guide YVL 3.0. (4 refs.)

  15. Regulatory supervision of safety indicators; experience with radiation safety indicators in Dukovany nuclear power plant performance

    International Nuclear Information System (INIS)

    Urbancik, L.; Kulich, V.

    2004-01-01

    The State Office for Nuclear Safety uses three sets of indicators describing the following aspects of a favourable nuclear power plant operation: smooth operation in normal circumstances, low risk to the population, and operation with a positive safety attitude. These are three safety-related areas for assessment. Each area has its own set of indicators. Overall operational safety performance indicators were identified for each attribute. From this point, a level of strategic indicators was developed, and finally, a set of specific indicators was set up. While neither the overall indicators nor the strategic indicators are directly measurable, the specific indicators are directly measurable and are targeted during inspection. (author)

  16. INSPECT: a package of computer programs for planning safeguards inspections

    International Nuclear Information System (INIS)

    Wincek, M.A.; Mullen, M.F.

    1979-04-01

    As part of the U.S. program to provide technical assistance to the International Atomic Energy Agency, a package of computer programs was developed for use in planning safeguards inspections of various types of nuclear facilities. The INSPECT software package is a set of five interactive FORTRAN programs which can be used to calculate the variance components of the MUF (Material Unaccounted For) statistic, the variance components of the D (difference) statistic, attribute and variables sampling plans, a measure of the effectiveness of the inspection, and a measurement of the cost of implementing the inspection plan. This report describes the programs and explains how to use them

  17. The need to optimize inservice testing and inspection to enhance safety

    International Nuclear Information System (INIS)

    Perry, J.A.

    1996-01-01

    Welcome to the Fourth U.S. Nuclear Regulatory Commission and American Society of Mechanical Engineers (USNRC/ASME) Symposium on Valve and Pump Testing in Nuclear Power Plants. This symposium provides a forum to exchange information on technical and regulatory issues associated with the testing of valves and pumps used in nuclear power plants. Progress made since the last symposium will be discussed along with various methods for in service testing of valves and pumps. Active participation by industry representatives, regulators and consultants will entail discussion of a broad array of ideas and points of view regarding how to improve the in service testing of valves and pumps at nuclear power plants. One of the challenges faced is the need to optimize the in service testing and inspection to enhance safety, operability and reliability. The author addresses this challenge from an ASME Nuclear Codes and Standards point of view

  18. The need to optimize inservice testing and inspection to enhance safety

    Energy Technology Data Exchange (ETDEWEB)

    Perry, J.A.

    1996-12-01

    Welcome to the Fourth U.S. Nuclear Regulatory Commission and American Society of Mechanical Engineers (USNRC/ASME) Symposium on Valve and Pump Testing in Nuclear Power Plants. This symposium provides a forum to exchange information on technical and regulatory issues associated with the testing of valves and pumps used in nuclear power plants. Progress made since the last symposium will be discussed along with various methods for in service testing of valves and pumps. Active participation by industry representatives, regulators and consultants will entail discussion of a broad array of ideas and points of view regarding how to improve the in service testing of valves and pumps at nuclear power plants. One of the challenges faced is the need to optimize the in service testing and inspection to enhance safety, operability and reliability. The author addresses this challenge from an ASME Nuclear Codes and Standards point of view.

  19. Revised inspection program for nuclear power plants

    International Nuclear Information System (INIS)

    1978-01-01

    The United States Nuclear Regulatory Commission (NRC) regulates nuclear power plants to assure adequate protection of the public and the environment from the dangers associated with nuclear materials. NRC fulfills this responsibility through comprehensive safety reviews of nuclear facilities, licensing of organizations that use nuclear materials, and continuing inspection. The NRC inspection program is currently conducted from the five regional offices in or near Philadelphia, Atlanta, Chicago, Dallas and San Francisco. Inspectors travel from the regional offices to nuclear power plants in various phases of construction, test and operation in order to conduct inspections. However, in June 1977 the Commission approved a revision to the inspection program that will include stationing inspectors at selected plants under construction and at all plants in operation. In addition, the revised program provides for appraising the performance of licensees on a national basis and involves more direct measurement and observation by NRC inspectors of work and tests in progress. The program also includes enhanced career management consisting of improved training and career development for inspectors and other professionals. The report was requested in the Conference Report on the NRC Authorization for Appropriations for Fiscal Year 1978. The report provides a discussion of the basis for both the current and revised inspection programs, describes these programs, and shows how the NRC inspection force will be trained and utilized. In addition, the report includes a discussion of the actions that will be taken to assure the objectivity of inspectors

  20. Inspection of licensed nuclear power plants in the United States

    International Nuclear Information System (INIS)

    Thornburg, H. D.

    1977-01-01

    Inspection of licensed nuclear power plants in the United States is performed by the Office of Inspection and Enforcement (IE), United States Nuclear Regulatory Commission. IE has several key functions : a) Inspection of licensees and investigation of incidents, occurrences and allegations. b) Detection and correction of safety and security problems. c) Enforcement of rules, regulations, and Commission orders. d) Feedback to the industry and others regarding safety experience. e) Informing the public and others. Major enforcement actions and events involving operating power reactors for the past several years will be summarized. (author)

  1. A whole process quality control system for energy measuring instruments inspection based on IOT technology

    Science.gov (United States)

    Yin, Bo; Liu, Li; Wang, Jiahan; Li, Xiran; Liu, Zhenbo; Li, Dewei; Wang, Jun; Liu, Lu; Wu, Jun; Xu, Tingting; Cui, He

    2017-10-01

    Electric energy measurement as a basic work, an accurate measurements play a vital role for the economic interests of both parties of power supply, the standardized management of the measurement laboratory at all levels is a direct factor that directly affects the fairness of measurement. Currently, the management of metering laboratories generally uses one-dimensional bar code as the recognition object, advances the testing process by manual management, most of the test data requires human input to generate reports. There are many problems and potential risks in this process: Data cannot be saved completely, cannot trace the status of inspection, the inspection process isn't completely controllable and so on. For the provincial metrology center's actual requirements of the whole process management for the performance test of the power measuring appliances, using of large-capacity RF tags as a process management information media, we developed a set of general measurement experiment management system, formulated a standardized full performance test process, improved the raw data recording mode of experimental process, developed a storehouse automatic inventory device, established a strict test sample transfer and storage system, ensured that all the raw data of the inspection can be traced back, achieved full life-cycle control of the sample, significantly improved the quality control level and the effectiveness of inspection work.

  2. Development of video probe system for inspection of feeder pipe support in calandria reactor

    International Nuclear Information System (INIS)

    Cho, Jai Wan; Lee, Nam Ho; Choi, Young Soo

    2000-07-01

    There are 760 feederpipes, which they are connected to inlet/outlet of the 380 pressure tube channels on the front of the calandria, in CANDU-type Reactor of Wolsung Nuclear Power Plant. As an ISI(In-Service Inspection) and PSI (Post- Service Inspection) requirements, maintenance activities of measuring the thickness of curvilinear part of feederpipe and inspecting the feederpipe support area within calandria are needed to ensure continued reliable operation of nuclear power plant. And untrasonic probe is used to measure the thickness of curvilinear part of feederpipe, however workers are exposed to radioactivity irradiation during the measurement period. But, it is impossible to inspect feederpipe support area thoroughlv because of narrow and confined accessibility, that is, an inspection space between the pressure tube channels is less than 100mm and pipes in feederpipe support area are congested. And also, workers involved in inspecting feederpipe support area are under the jeopardy of high-level radiation exposure. Concerns about sliding home, which make the move of feederpipe connected to pressure tube channel smooth as pressure tube expands and contracts in its axial direction, stuck to feederpipe support and some of the structural components have made necessary the development of video inspection probe system with narrow and confined accessibility to observe and inspect feederpipe support area more close. Using video inspection probe system, it is possible to inspect and repair abnormality of feederpipe support connected to pressure tube channels of the calandria more accurate and quantative than naked eye. Therefore, that will do much for ensuring safety of CANDU-type nuclear power plant

  3. Quantitative approach for optimizing e-beam condition of photoresist inspection and measurement

    Science.gov (United States)

    Lin, Chia-Jen; Teng, Chia-Hao; Cheng, Po-Chung; Sato, Yoshishige; Huang, Shang-Chieh; Chen, Chu-En; Maruyama, Kotaro; Yamazaki, Yuichiro

    2018-03-01

    Severe process margin in advanced technology node of semiconductor device is controlled by e-beam metrology system and e-beam inspection system with scanning electron microscopy (SEM) image. By using SEM, larger area image with higher image quality is required to collect massive amount of data for metrology and to detect defect in a large area for inspection. Although photoresist is the one of the critical process in semiconductor device manufacturing, observing photoresist pattern by SEM image is crucial and troublesome especially in the case of large image. The charging effect by e-beam irradiation on photoresist pattern causes deterioration of image quality, and it affect CD variation on metrology system and causes difficulties to continue defect inspection in a long time for a large area. In this study, we established a quantitative approach for optimizing e-beam condition with "Die to Database" algorithm of NGR3500 on photoresist pattern to minimize charging effect. And we enhanced the performance of measurement and inspection on photoresist pattern by using optimized e-beam condition. NGR3500 is the geometry verification system based on "Die to Database" algorithm which compares SEM image with design data [1]. By comparing SEM image and design data, key performance indicator (KPI) of SEM image such as "Sharpness", "S/N", "Gray level variation in FOV", "Image shift" can be retrieved. These KPIs were analyzed with different e-beam conditions which consist of "Landing Energy", "Probe Current", "Scanning Speed" and "Scanning Method", and the best e-beam condition could be achieved with maximum image quality, maximum scanning speed and minimum image shift. On this quantitative approach of optimizing e-beam condition, we could observe dependency of SEM condition on photoresist charging. By using optimized e-beam condition, measurement could be continued on photoresist pattern over 24 hours stably. KPIs of SEM image proved image quality during measurement and

  4. 75 FR 56502 - National Advisory Committee on Meat and Poultry Inspection

    Science.gov (United States)

    2010-09-16

    ... Advisory Committee on Meat and Poultry Inspection AGENCY: Food Safety and Inspection Service, USDA. ACTION... and Poultry Inspection (NACMPI) will hold a public meeting on September 29-30, 2010, to review and... disks or CD-ROMs: Send to National Advisory Committee on Meat and Poultry Inspection, USDA, FSIS, 14th...

  5. FMCSA safety program effectiveness measurement : roadside intervention effectiveness model FY 2013 : analysis brief.

    Science.gov (United States)

    2017-08-01

    The Roadside Inspection and Traffic Enforcement programs are two of FMCSAs most powerful safety tools. By continually examining the results of these programs, FMCSA can ensure that they are being executed effectively and are producing the desired ...

  6. 9 CFR 355.41 - Antemortem and postmortem inspection for mules.

    Science.gov (United States)

    2010-01-01

    ... AND VOLUNTARY INSPECTION AND CERTIFICATION CERTIFIED PRODUCTS FOR DOGS, CATS, AND OTHER CARNIVORA... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Antemortem and postmortem inspection for mules. 355.41 Section 355.41 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE...

  7. Optical inspection of hidden MEMS structures

    Science.gov (United States)

    Krauter, Johann; Gronle, Marc; Osten, Wolfgang

    2017-06-01

    Micro-electro-mechanical system's (MEMS) applications have greatly expanded over the recent years, and the MEMS industry has grown almost exponentially. One of the strongest drivers are the automotive and consumer markets. A 100% test is necessary especially in the production of automotive MEMS sensors since they are subject to safety relevant functions. This inspection should be carried out before dicing and packaging since more than 90% of the production costs are incurred during these steps. An electrical test is currently being carried out with each MEMS component. In the case of a malfunction, the defect can not be located on the wafer because the MEMS are no longer optically accessible due to the encapsulation. This paper presents a low coherence interferometer for the topography measurement of MEMS structures located within the wafer stack. Here, a high axial and lateral resolution is necessary to identify defects such as stuck or bent MEMS fingers. First, the boundary conditions for an optical inspection system will be discussed. The setup is then shown with some exemplary measurements.

  8. A review of digital radiography technology for valve inspection

    International Nuclear Information System (INIS)

    Stoev, K.; Guerout, F.M.; Horn, D.

    2008-01-01

    There are thousands of valves in a nuclear power plant (NPP) used for control, safety and checks in various plant systems, so there is a well-identified need for fast and reliable inspection and diagnostics of valves. Digital radiography can provide considerable improvements to the inspection and testing procedures for valves in comparison to classical film radiography. These improvements can lead to significant financial advantages by providing real-time inspection results, significantly reduced inspection and decision-making time, and reduced operational cost. Digital image processing, including digital image enhancement, digital archiving, and digital communication of the images and the results, is also a considerable advantage over classical film radiography technology. Another advantage of digital radiography technology is the improved safety and the reduced environmental impact due to reduced exposure/test times, use of smaller exclusion zones, elimination of chemical processing, and absence of disposable materials. This paper reviews the existing technology and evaluates the potential of digital radiography for inspection and diagnostics of valves. Station needs and requirements are assessed, and the safety, environmental and economical constraints of digital radiography techniques estimated. The advantages and disadvantages of different digital radiography equipment are compared, and their limitations and characteristics studied. (author)

  9. Advanced In-Service Inspection Approaches Applied to the Phenix Fast Breeder Reactor

    International Nuclear Information System (INIS)

    Guidez, J.; Martin, L.; Dupraz, R.

    2006-01-01

    The safety upgrading of the Phenix plant undertaken between 1994 and 1997 involved a vast inspection programme of the reactor, the external storage drum and the secondary sodium circuits in order to meet the requirements of the defence-in-depth safety approach. The three lines of defence were analysed for every safety related component: demonstration of the quality of design and construction, appropriate in-service inspection and controlling the consequences of an accident. The in-service reactor block inspection programme consisted in controlling the core support structures and the high-temperature elements. Despite the fact that limited consideration had been given to inspection constraints during the design stage of the reactor in the 1960's, as compared to more recent reactor projects such as the European Fast Reactor (EFR), all the core support line elements were able to be inspected. The three following main operations are described: Ultrasonic inspection of the upper hangers of the main vessel, using small transducers able to withstand temperatures of 130 deg. C, Inspection of the conical shell supporting the core dia-grid. A specific ultrasonic method and a special implementation technique were used to control the under sodium structure welds, located up to several meters away from the scan surface. Remote inspection of the hot pool structures, particularly the core cover plug after partial sodium drainage of the reactor vessel. Other inspections are also summarized: control of secondary sodium circuit piping, intermediate heat exchangers, primary sodium pumps, steam generator units and external storage drum. The pool type reactor concept, developed in France since the 1960's, presents several favourable safety and operational features. The feedback from the Phenix plant also shows real potential for in-service inspection. The design of future generation IV sodium fast reactors will benefit from the experience acquired from the Phenix plant. (authors)

  10. Risk-based inspection in the context of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Soares, Wellington A.; Vasconcelos, Vanderley de; Rabello, Emerson G., E-mail: soaresw@cdtn.br, E-mail: vasconv@cdtn.br, E-mail: egr@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2015-07-01

    Nuclear power plant owners have to consider several aspects like safety, availability, costs and radiation exposure during operation of nuclear power plants. They also need to demonstrate to regulatory bodies that risk assessment and inspection planning processes are being implemented in effective and appropriate manner. Risk-Based Inspection (RBI) is a methodology that, unlike time-based inspection, involves a quantitative assessment of both failure probability and consequence associated with each safety-related item. A correctly implemented RBI program classifies individual equipment by its risks and prioritizes inspection efforts based on this classification. While in traditional deterministic approach, the inspection frequencies are constant, in the RBI approach the inspection interval for each item depends on the risk level. Regularly, inspection intervals from RBI result in risk levels lower or equal than deterministic inspection intervals. According to the literature, RBI solutions improve integrity and reduce costs through a more effective inspection. Risk-Informed In-service Inspection (RI-ISI) is the equivalent term used in the nuclear area. Its use in nuclear power plants around world is briefly reviewed in this paper. Identification of practice methodologies for performing risk-based analyses presented in this paper can help both Brazilian nuclear power plant operator and regulatory body in evaluating the RI-ISI technique feasibility as a tool for optimizing inspections within nuclear plants. (author)

  11. Risk-based inspection in the context of nuclear power plants

    International Nuclear Information System (INIS)

    Soares, Wellington A.; Vasconcelos, Vanderley de; Rabello, Emerson G.

    2015-01-01

    Nuclear power plant owners have to consider several aspects like safety, availability, costs and radiation exposure during operation of nuclear power plants. They also need to demonstrate to regulatory bodies that risk assessment and inspection planning processes are being implemented in effective and appropriate manner. Risk-Based Inspection (RBI) is a methodology that, unlike time-based inspection, involves a quantitative assessment of both failure probability and consequence associated with each safety-related item. A correctly implemented RBI program classifies individual equipment by its risks and prioritizes inspection efforts based on this classification. While in traditional deterministic approach, the inspection frequencies are constant, in the RBI approach the inspection interval for each item depends on the risk level. Regularly, inspection intervals from RBI result in risk levels lower or equal than deterministic inspection intervals. According to the literature, RBI solutions improve integrity and reduce costs through a more effective inspection. Risk-Informed In-service Inspection (RI-ISI) is the equivalent term used in the nuclear area. Its use in nuclear power plants around world is briefly reviewed in this paper. Identification of practice methodologies for performing risk-based analyses presented in this paper can help both Brazilian nuclear power plant operator and regulatory body in evaluating the RI-ISI technique feasibility as a tool for optimizing inspections within nuclear plants. (author)

  12. NRC program of inspection and enforcement

    International Nuclear Information System (INIS)

    LeDoux, J.C.; Rehfuss, C.

    1978-01-01

    The Nuclear Regulatory Commission (NRC) regulates civilian uses of nuclear materials to ensure the protection of the public health and safety and the environment. The Office of Inspection and Enforcement (IE) develops and implements the inspection, investigation, and enforcement programs for the NRC. The IE conducts inspection programs for reactors under construction and in operation, nuclear industry vendors, fuel facilities and users of nuclear materials, and all aspects of the safeguarding of facilities and materials. Recently the IE began implementing a program that will place inspectors on site at nuclear power reactors and will provide for national appraisal of licensee performance and for an evaluation of the effectiveness of the inspection programs

  13. Multiobjective optimization of the inspection intervals of a nuclear safety system: A clustering-based framework for reducing the Pareto Front

    International Nuclear Information System (INIS)

    Zio, E.; Bazzo, R.

    2010-01-01

    In this paper, a framework is developed for identifying a limited number of representative solutions of a multiobjective optimization problem concerning the inspection intervals of the components of a safety system of a nuclear power plant. Pareto Front solutions are first clustered into 'families', which are then synthetically represented by a 'head of the family' solution. Three clustering methods are analyzed. Level Diagrams are then used to represent, analyse and interpret the Pareto Fronts reduced to their head-of-the-family solutions. Two decision situations are considered: without or with decision maker preferences, the latter implying the introduction of a scoring system to rank the solutions with respect to the different objectives: a fuzzy preference assignment is then employed to this purpose. The results of the application of the framework of analysis to the problem of optimizing the inspection intervals of a nuclear power plant safety system show that the clustering-based reduction maintains the Pareto Front shape and relevant characteristics, while making it easier for the decision maker to select the final solution.

  14. Inspection and test planning

    International Nuclear Information System (INIS)

    Miller, T.

    1980-01-01

    Purpose of Quality Plan - arrangement of all necessary tests or inspections as far as possible filted to certain components or systems. Subject of Quality Plan - precise determination of tests or inspections and - according to the actual safety significance - the certificates to be done. Disposition of Quality Plan - accommodation of tests to the actual state of fabrication. Application of Quality Plan - to any component or system that is regarded. Supervision of Employment - by authorized personnel of manufacturer, customer or authority providing exact employment of quality plan. Overservance of Instructions - certificates given by authorized personnel. (orig./RW)

  15. Ultrasonic inspection

    International Nuclear Information System (INIS)

    Satittada, Gannaga

    1984-01-01

    Ultrasonic inspection is one of the most widely used methods for nondestructive inspection. The beam of high-frequency sound wave, ultrasonic wave, is introduced into the material. It travels through the material with some attendant loss of energy and can be reflected at interfaces. The reflected beam is detected and analyzed. Ultrasonic inspection is used to detect flaws in metal parts as well as in welded, brazed and bonded joints during research work and developing production and service. It is also used to detect and locate porosity, pipe, and flakes. In addition, it can be used for the measurement of metal thickness. Ultrasonic inspection is therefore used for quality control and material inspection in all major industries

  16. Inspection of freeform surfaces considering uncertainties in measurement, localization and surface reconstruction

    International Nuclear Information System (INIS)

    Mehrad, Vahid; Xue, Deyi; Gu, Peihua

    2013-01-01

    Inspection of a manufactured freeform surface can be conducted by building its surface model and comparing this manufactured surface model with the ideal design surface model and its tolerance requirement. The manufactured freeform surface model is usually achieved by obtaining measurement points on the manufactured surface, transforming these measurement points from the measurement coordinate system to the design coordinate system through localization, and reconstructing the surface model using the localized measurement points. In this research, a method was developed to estimate the locations and their variances of any selected points on the reconstructed freeform surface considering different sources of uncertainties in measurement, localization and surface reconstruction processes. In this method, first locations and variances of the localized measurement points are calculated considering uncertainties of the measurement points and uncertainties introduced in the localization processes. Then locations and variances of points on the reconstructed freeform surface are obtained considering uncertainties of the localized measurement points and uncertainties introduced in the freeform surface reconstruction process. Two case studies were developed to demonstrate how these three different uncertainty sources influence the quality of the reconstructed freeform curve and freeform surface in inspection. (paper)

  17. Development of the Risk-Based Inspection Techniques and Pilot Plant Activities

    International Nuclear Information System (INIS)

    Phillips, J.H.

    1997-01-01

    Risk-based techniques have been developed for commercial nuclear power plants. System boundaries and success criteria is defined using the probabilistic risk analysis or probabilistic safety analysis developed to meet the individual plant evaluation. Final ranking of components is by a plant expert panel similar to the one developed for maintenance rule. Components are identified as being high risk-significant or low-risk significant. Maintenance and resources are focused on those components that have the highest risk-significance. The techniques have been developed and applied at a number of pilot plants. Results from the first risk-based inspection pilot plant indicates that safety due to pipe failure can be doubled while the inspection reduced to about 80% when compared with current inspection programs. The reduction in inspection reduces the person-rem exposure resulting in further increases in safety. These techniques have been documented in publication by the ASME CRTD

  18. 77 FR 75118 - National Advisory Committee on Meat and Poultry Inspection

    Science.gov (United States)

    2012-12-19

    ... Advisory Committee on Meat and Poultry Inspection AGENCY: Food Safety and Inspection Service, USDA. ACTION... Inspection Service (FSIS) is announcing a meeting of the National Advisory Committee on Meat and Poultry... strengthening Agency verification activities and guidance concerning sanitary dressing and antimicrobial...

  19. AUTOMATED INSPECTION OF POWER LINE CORRIDORS TO MEASURE VEGETATION UNDERCUT USING UAV-BASED IMAGES

    Directory of Open Access Journals (Sweden)

    M. Maurer

    2017-08-01

    Full Text Available Power line corridor inspection is a time consuming task that is performed mostly manually. As the development of UAVs made huge progress in recent years, and photogrammetric computer vision systems became well established, it is time to further automate inspection tasks. In this paper we present an automated processing pipeline to inspect vegetation undercuts of power line corridors. For this, the area of inspection is reconstructed, geo-referenced, semantically segmented and inter class distance measurements are calculated. The presented pipeline performs an automated selection of the proper 3D reconstruction method for on the one hand wiry (power line, and on the other hand solid objects (surrounding. The automated selection is realized by performing pixel-wise semantic segmentation of the input images using a Fully Convolutional Neural Network. Due to the geo-referenced semantic 3D reconstructions a documentation of areas where maintenance work has to be performed is inherently included in the distance measurements and can be extracted easily. We evaluate the influence of the semantic segmentation according to the 3D reconstruction and show that the automated semantic separation in wiry and dense objects of the 3D reconstruction routine improves the quality of the vegetation undercut inspection. We show the generalization of the semantic segmentation to datasets acquired using different acquisition routines and to varied seasons in time.

  20. Automated Inspection of Power Line Corridors to Measure Vegetation Undercut Using Uav-Based Images

    Science.gov (United States)

    Maurer, M.; Hofer, M.; Fraundorfer, F.; Bischof, H.

    2017-08-01

    Power line corridor inspection is a time consuming task that is performed mostly manually. As the development of UAVs made huge progress in recent years, and photogrammetric computer vision systems became well established, it is time to further automate inspection tasks. In this paper we present an automated processing pipeline to inspect vegetation undercuts of power line corridors. For this, the area of inspection is reconstructed, geo-referenced, semantically segmented and inter class distance measurements are calculated. The presented pipeline performs an automated selection of the proper 3D reconstruction method for on the one hand wiry (power line), and on the other hand solid objects (surrounding). The automated selection is realized by performing pixel-wise semantic segmentation of the input images using a Fully Convolutional Neural Network. Due to the geo-referenced semantic 3D reconstructions a documentation of areas where maintenance work has to be performed is inherently included in the distance measurements and can be extracted easily. We evaluate the influence of the semantic segmentation according to the 3D reconstruction and show that the automated semantic separation in wiry and dense objects of the 3D reconstruction routine improves the quality of the vegetation undercut inspection. We show the generalization of the semantic segmentation to datasets acquired using different acquisition routines and to varied seasons in time.

  1. Implementation of in-service inspection program for HANARO

    International Nuclear Information System (INIS)

    Wu, J.S.; Park, Y.C.; Cho, Y.G.; Jun, B.J.

    2001-01-01

    HANARO, a 30 MW multi-purpose research reactor in Korea has been successfully in operation for 6 years since its initial criticality in February 1995. It is mainly used for the research areas including nuclear fuel and material irradiation tests, radioisotope production, neutron beam application, neutron activation analysis and neutron transmutation doping. HANARO was designed to perform for at least 20 years under full power operating condition. It is expected that the actual reactor lifetime will be much more than the design lifetime, due to a safety reassessment based on realistic data, preventive maintenance and appropriate in-service inspections (ISI). Since ageing may affect the overall safety of the reactor facility, it is needed to detect and evaluate the effects on aged components and systems related to safety. During the lifetime of the reactor, structures, systems and components are subjected to environmental conditions of stress, temperature and irradiation that may lead to changes in the material properties and could result in unexpected failures. Evidence of ageing problems appears progressively. A rigorous inspection and visual examination based on a periodic ISI program should be established. It is desirable that the ageing surveillance activities is scheduled as early as possible and continued throughout the operating life of the reactor. An inspection plan for safety related structures, systems and components subjected to the ageing conditions is requested by the regulatory body to assess the safety status of reactor facility. A long-term ISI program for HANARO has been established for safety-related systems and components in the context of the overall reactor ageing management. The objective of this paper is to describe the ISI program and the result of the visual inspection as the first ISI. (orig.)

  2. A microscopy approach for in situ inspection of micro-coordinate measurement machine styli for contamination

    Science.gov (United States)

    Feng, Xiaobing; Pascal, Jonathan; Lawes, Simon

    2017-09-01

    During the process of measurement using a micro-coordinate measurement machine (µCMM) contamination gradually builds up on the surface of the stylus tip and affects the dimensional accuracy of the measurement. Regular inspection of the stylus for contamination is essential to determine the appropriate cleaning interval and prevent the dimensional error from becoming significant. However, in situ inspection of a µCMM stylus is challenging due to the size, spherical shape, material and surface properties of a typical stylus. To address this challenge, this study evaluates several non-contact measurement technologies for in situ stylus inspection and, based on those findings, proposes a cost-effective microscopy approach. The operational principle is then demonstrated by an automated prototype, coordinated directly by the CMM software MCOSMOS, with an effective threshold of detection as low as 400 nm and a large field of view and depth of field. The level of contamination on the stylus has been found to increase steadily with the number of measurement contacts made. Once excessive contamination is detected on the stylus, measurement should be stopped and a stylus cleaning procedure should be performed to avoid affecting measurement accuracy.

  3. A microscopy approach for in situ inspection of micro-coordinate measurement machine styli for contamination

    International Nuclear Information System (INIS)

    Feng, Xiaobing; Lawes, Simon; Pascal, Jonathan

    2017-01-01

    During the process of measurement using a micro-coordinate measurement machine (µCMM) contamination gradually builds up on the surface of the stylus tip and affects the dimensional accuracy of the measurement. Regular inspection of the stylus for contamination is essential to determine the appropriate cleaning interval and prevent the dimensional error from becoming significant. However, in situ inspection of a µCMM stylus is challenging due to the size, spherical shape, material and surface properties of a typical stylus. To address this challenge, this study evaluates several non-contact measurement technologies for in situ stylus inspection and, based on those findings, proposes a cost-effective microscopy approach. The operational principle is then demonstrated by an automated prototype, coordinated directly by the CMM software MCOSMOS, with an effective threshold of detection as low as 400 nm and a large field of view and depth of field. The level of contamination on the stylus has been found to increase steadily with the number of measurement contacts made. Once excessive contamination is detected on the stylus, measurement should be stopped and a stylus cleaning procedure should be performed to avoid affecting measurement accuracy. (paper)

  4. Accumulation and preparation of nondestructive inspection data for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    In recent years, flaws due to stress corrosion cracking (SCC) in stainless steel piping and nickel based alloy welds were detected at nuclear power plants in Japan. Weld Overlay (WOL) has been developed as a repairing method for piping items without removing flaws. Since the inspection techniques for WOL pipes and nickel based alloy welds are not verified enough in Japan, Japan Nuclear Energy Safety Organization (JNES) has been carrying out a six year research project entitled 'Accumulation and Preparation of Nondestructive Inspection Data for Nuclear Power Plants' regarding nondestructive inspection since FY2007. In this research project, detection and sizing capability of SCC by Ultrasonic Testing (UT) are evaluated using mockup tests. In addition, the results of this project and past nondestructive inspection data performed by JNES projects are gathered, and inputted into the database of NDT information. In FY2012, followings were conducted. 1) Analysis for UT measurement results of nickel based alloy weld simulating safe end of reactor vessel outlet nozzle. 2) Analysis for UT measurement results of cast stainless steel piping. 3) Development of interface of UT simulation. 4) Development of nondestructive testing guideline. (author)

  5. Safety-barrier diagrams as a tool for modelling safety of hydrogen applications

    DEFF Research Database (Denmark)

    Duijm, Nijs Jan; Markert, Frank

    2009-01-01

    Safety-barrier diagrams have proven to be a useful tool in documenting the safety measures taken to prevent incidents and accidents in process industry. Especially during the introduction of new hydrogen technologies or applications, as e.g. hydrogen refuelling stations, safety-barrier diagrams...... are considered a valuable supplement to other traditional risk analysis tools to support the communication with authorities and other stakeholders during the permitting process. Another advantage of safety-barrier diagrams is that they highlight the importance of functional and reliable safety barriers in any...... system and here is a direct focus on those barriers that need to be subject to safety management in terms of design and installation, operational use, inspection and monitoring, and maintenance. Safety-barrier diagrams support both quantitative and qualitative approaches. The paper will describe...

  6. Remotely Operated Train for Inspection and Measurement in CERN's LHC Tunnel

    CERN Document Server

    Kershaw, K; Bestmann, P; Feniet, T; Forkel-Wirth, D; Grenard, J L; Rousset, N

    2010-01-01

    Personnel access to the LHC tunnel will be restricted to varying extents during the life of the machine due to radiation and cryogenic hazards. For this reason a remotely operated modular inspection train, (TIM) running on the LHC tunnel’s overhead monorail has been developed. In order to be compatible with the LHC personnel access system, a small section train that can pass through small openings at the top of sector doors has now been produced. The basic train can be used for remote visual inspection; additional modules give the capability of carrying out remote measurement of radiation levels, environmental conditions around the tunnel, and even remote measurement of the precise position of machine elements such as collimators. The paper outlines the design, development and operation of the equipment including preparation of the infrastructure. Key features of the trains are described along with future developments and intervention scenarios.

  7. The Preliminary Review for the Cross-Cutting Issues in the US Nuclear Regulatory Inspection Framework

    International Nuclear Information System (INIS)

    Lee, Yong Suk; Jung, Dae Wook; Cho, Nam Chul

    2008-01-01

    The research for the development of risk-informed and performance-based regulatory inspection is ongoing in KINS. In the USNRC, the cross-cutting issue is one of the main components the risk-informed and performance-based regulatory inspection process as shown in figure 1, which is named as ROP (Reactor Oversight Process). The following three cross-cutting areas implicitly affect all of the safety cornerstones in ROP. In this study, the preliminary review for the inspection practices of cross-cutting issues in the US and Korean safety regulatory system were performed. The elements of the cross-cutting issues were recently modified to emphasize the importance of safety culture, and the graded approach was applied for the inspection of cross-cutting issues in USNRC. The graded approach for the inspection of cross-cutting issues will be also needed to Korean safety regulatory system in the future

  8. The Preliminary Review for the Cross-Cutting Issues in the US Nuclear Regulatory Inspection Framework

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Yong Suk; Jung, Dae Wook [Future and Challenges Inc., Seoul (Korea, Republic of); Cho, Nam Chul [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2008-10-15

    The research for the development of risk-informed and performance-based regulatory inspection is ongoing in KINS. In the USNRC, the cross-cutting issue is one of the main components the risk-informed and performance-based regulatory inspection process as shown in figure 1, which is named as ROP (Reactor Oversight Process). The following three cross-cutting areas implicitly affect all of the safety cornerstones in ROP. In this study, the preliminary review for the inspection practices of cross-cutting issues in the US and Korean safety regulatory system were performed. The elements of the cross-cutting issues were recently modified to emphasize the importance of safety culture, and the graded approach was applied for the inspection of cross-cutting issues in USNRC. The graded approach for the inspection of cross-cutting issues will be also needed to Korean safety regulatory system in the future.

  9. Developing Measures for Assessing the Causality of Safety Culture in a Petrochemical Industry

    Energy Technology Data Exchange (ETDEWEB)

    Wu, T.-C., E-mail: tcwu@sunrise.hk.edu.t [HungKuang University, Department of Safety, Health and Environmental Engineering (China); Lin, C.-H.; Shiau, S.-Y. [HungKuang University, Institute of Occupational Safety and Hazard Prevention (China)

    2009-12-15

    This paper discusses safety culture in the petrochemical sector and the causes and consequences of safety culture. A sample of 520 responses selected by simple random sampling completed questionnaires for this survey, the return rate was 86.75%. The research instrument comprises four sections: basic information, the safety leadership scale (SLS), the safety climate scale (SCS), and the safety performance scale (SPS). SPSS 12.0, a statistical software package, was used for item analysis, validity analysis, and reliability analysis. Exploratory factor analysis indicated that (1) SLS abstracted three factors such as safety caring, safety controlling, and safety coaching; (2) SCS comprised three factors such as emergency response, safety commitment, and risk perception; and (3) SPS was composed of accident investigation, safety training, safety inspections, and safety motivation. We conclude that the SLS, SCS, and SPS developed in this paper have good construct validity and internal consistency and can serve as the basis for future research.

  10. Developing Measures for Assessing the Causality of Safety Culture in a Petrochemical Industry

    International Nuclear Information System (INIS)

    Wu, T.-C.; Lin, C.-H.; Shiau, S.-Y.

    2009-01-01

    This paper discusses safety culture in the petrochemical sector and the causes and consequences of safety culture. A sample of 520 responses selected by simple random sampling completed questionnaires for this survey, the return rate was 86.75%. The research instrument comprises four sections: basic information, the safety leadership scale (SLS), the safety climate scale (SCS), and the safety performance scale (SPS). SPSS 12.0, a statistical software package, was used for item analysis, validity analysis, and reliability analysis. Exploratory factor analysis indicated that (1) SLS abstracted three factors such as safety caring, safety controlling, and safety coaching; (2) SCS comprised three factors such as emergency response, safety commitment, and risk perception; and (3) SPS was composed of accident investigation, safety training, safety inspections, and safety motivation. We conclude that the SLS, SCS, and SPS developed in this paper have good construct validity and internal consistency and can serve as the basis for future research.

  11. In-service inspections of V-230 reactor

    International Nuclear Information System (INIS)

    Prepechal, J.

    1984-01-01

    It is stated that despite certain constraints the configuration of the WWER-440 is such that it allows to make in-service inspections on a fully satisfactory scale. Three factors are discussed whose existence is necessary for the implementation of in-service inspections. The program defining the scale of inspections is satisfactory with regard to the safety and reliability of reactor operation. Its further development must result in reducing time consumption and radiation burden of personnel. Regulations for the implementation and evaluation of inspections represent the weakest link in the system of in-service inspections. At present, various organizations are dealing with the said problem within international cooperation. Equipment for in-service inspections of WWER-440 reactors is relatively good. The most important knowledge is summed up gained from the ten pre-service and in-service inspections of reactors of this type made so far. (Z.M.)

  12. Safety, feasibility, and acceptability of visual inspection with acetic acid and immediate treatment with cryotherapy in rural Laos.

    Science.gov (United States)

    Phongsavan, Keokedthong; Phengsavanh, Alongkone; Wahlström, Rolf; Marions, Lena

    2011-09-01

    To assess the safety, acceptability, and feasibility of visual inspection with acetic acid (VIA) followed by immediate treatment with cryotherapy as a single-visit approach for the prevention of cervical cancer among women in rural Laos. In 2009, women from 2 provinces in Laos were recruited for cervical cancer screening using VIA. If the inspection of the cervix showed a well-defined acetowhite lesion close to the os, immediate cryotherapy was offered. Of the 1926 women who were included, 134 (7.0%) tested positive on VIA. Of these, 113 (84.3%) underwent immediate cryotherapy and none declined treatment. One year after immediate cryotherapy, 77 (68.1%) women returned for a follow-up assessment and 68 (88.3%) were now VIA-negative. There was no report of a major complication during or after treatment. The acceptance of both VIA and cryotherapy was high. Visual inspection with acetic acid is a simple test that requires minimal infrastructure and expenditure. Integration of VIA with cryotherapy at the primary care level may constitute a feasible program for the prevention of cervical cancer in Laos. Copyright © 2011 International Federation of Gynecology and Obstetrics. Published by Elsevier Ireland Ltd. All rights reserved.

  13. Regulatory inspections in nuclear plants in the field of radiation protection

    International Nuclear Information System (INIS)

    Hort, M.; Fuchsova, D.

    2014-01-01

    State Office for Nuclear Safety executes state administration and performs inspections at peaceful use of nuclear energy and ionizing radiation in the field of radiation protection and nuclear safety. Inspections on radiation protection at nuclear power plants are secured by inspectors of the Department of Radiation Protection in Fuel Cycle, who work at the Regional centre Brno and Ceske Budejovice. (authors)

  14. 77 FR 13512 - National Advisory Committee on Meat and Poultry Inspection

    Science.gov (United States)

    2012-03-07

    ... Poultry Inspection AGENCY: Food Safety and Inspection Service, USDA. ACTION: Notice of committee meeting... Committee Act, that the National Advisory Committee on Meat and Poultry Inspection (NACMPI) will hold a public meeting on Wednesday, March 21, 2012, to discuss the proposed rule on the Modernization of Poultry...

  15. 9 CFR 381.209 - Returned United States inspected and marked poultry products; exemption.

    Science.gov (United States)

    2010-01-01

    ... PRODUCTS INSPECTION AND VOLUNTARY INSPECTION AND CERTIFICATION POULTRY PRODUCTS INSPECTION REGULATIONS... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Returned United States inspected and marked poultry products; exemption. 381.209 Section 381.209 Animals and Animal Products FOOD SAFETY AND...

  16. Estimated Incident Cost Savings in Shipping Due to Inspections

    NARCIS (Netherlands)

    S. Knapp (Sabine); G.E. Bijwaard (Govert); C. Heij (Christiaan)

    2010-01-01

    textabstractThe effectiveness of safety inspections has been analysed from various angles, but until now, relatively little attention has been given to translate risk reduction into incident cost savings. This paper quantifies estimated cost savings based on port state control inspections and

  17. Machine vision system for remote inspection in hazardous environments

    International Nuclear Information System (INIS)

    Mukherjee, J.K.; Krishna, K.Y.V.; Wadnerkar, A.

    2011-01-01

    Visual Inspection of radioactive components need remote inspection systems for human safety and equipment (CCD imagers) protection from radiation. Elaborate view transport optics is required to deliver images at safe areas while maintaining fidelity of image data. Automation of the system requires robots to operate such equipment. A robotized periscope has been developed to meet the challenge of remote safe viewing and vision based inspection. (author)

  18. Regulatory inspection of nuclear power plants in NEA member countries

    International Nuclear Information System (INIS)

    Gronow, W.S.; Ilani, O.

    1977-01-01

    The increasing use of nuclear power and public interest in the safety controls led to the proposal by the sub-Committe on Licensing of the NEA Committee on the Safety of Nuclear Installations for a specialist meeting on regulatory inspection practices. This report which was prepared at the request of the sub-Committee to assist in the exchange of views and experience at the meeting reviews the response to a questionnaire on the systems employed, the scope and objectives and the effort involved in regulatory inspection throughout all stages of the life of a nuclear power plant. Other aspects of regulatory inspection activities are discussed including documentation, procedures for changes in technical specification and modifications to plant, powers and duties of regulatory inspection personnel and actions to be taken in the event of an accident or emergency. The report concludes with some comments on those aspects of regulatory inspection practices where further information and an exchange of experience might prove to be beneficial to Member countries. (author)

  19. Inspection system of radioactive contamination in foods and its results in Yokohama City

    International Nuclear Information System (INIS)

    Morita, Masahiro

    1993-01-01

    Accompanying the Chernobyl nuclear power plant accident occurred on April 26, 1986, the radioactive contamination of the foods imported from Europe became problems. Consequently, the Ministry of Health and Welfare stipulated the temporary limit of radioactive concentration in imported foods in terms of the total of Cs-134 and Cs-137 at less than 370 becquerel per 1 kg of foods in November, 1986, and the inspection system was tightened. In Yokohama, in view of securing the safety of foods and eliminating the anxiety of citizen, the measuring instruments for radioactivity were installed in the Hygiene Laboratory in 1986 and in the Food Hygiene Inspection Stations in Central Wholesale Market in 1987, and the inspection was begun. So far 720 subjects were inspected, but there was none that exceeds the temporary limit. The period and the method of executing the inspection and the results of nuclide analysis, screening inspection and so on are reported. It was judged that at the present point of time, there is not much influence to the life of citizen. (K.I.)

  20. Risk-Informed Decisions Optimization in Inspection and Maintenance

    International Nuclear Information System (INIS)

    Robertas Alzbutas

    2002-01-01

    The Risk-Informed Approach (RIA) used to support decisions related to inspection and maintenance program is considered. The use of risk-informed methods can help focus the adequate in-service inspections and control on the more important locations of complex dynamic systems. The focus is set on the highest risk measured as conditional core damage frequency, which is produced by the frequencies of degradation and final failure at different locations combined with the conditional failure consequence probability. The probabilities of different degradation states per year and consequences are estimated quantitatively. The investigation of inspection and maintenance process is presented as the combination of deterministic and probabilistic analysis based on general risk-informed model, which includes the inspection and maintenance program features. Such RIA allows an optimization of inspection program while maintaining probabilistic and fundamental deterministic safety requirements. The failure statistics analysis is used as well as the evaluation of reliability of inspections. The assumptions regarding the effectiveness of the inspection methods are based on a classification of the accessibility of the welds during the inspection and on the different techniques used for inspection. The probability of defect detection is assumed to depend on the parameters either through logarithmic or logit transformation. As example the modeling of the pipe systems inspection process is analyzed. The means to reduce a number of inspection sites and the cumulative radiation exposure to the NPP inspection personnel with a reduction of overall risk is presented together with used and developed software. The developed software can perform and administrate all the risk evaluations and ensure the possibilities to compare different options and perform sensitivity analysis. The approaches to define an acceptable level of risk are discussed. These approaches with appropriate software in

  1. 78 FR 77643 - National Advisory Committee of Meat and Poultry Inspection

    Science.gov (United States)

    2013-12-24

    ... Advisory Committee of Meat and Poultry Inspection AGENCY: Food Safety and Inspection Service, USDA. ACTION... of the National Advisory Committee on Meat and Poultry Inspection (NACMPI). The Committee is being... label on meat and poultry packages. With this input, the Agency will consider whether or not the current...

  2. Inspection and repair of nuclear components

    International Nuclear Information System (INIS)

    Lahner, K.; Poetz, F.

    1993-01-01

    Despite careful design, manufacturing and operation, some of the important safety-relevant components show deterioration with time. Because of activation and contamination of these components, their inspection and repair has to be performed with manipulators. Some sophisticated manipulators are described, built by ABB Reaktor and used for inspection, maintenance and repair of PWR steam generators, fuel alignment pins, core baffle former bolts and reactor pressure vessel head penetrations. (Z.S.) 7 figs

  3. Inspection practice and a role of TSO

    International Nuclear Information System (INIS)

    Janzekovic, H.

    2010-01-01

    Technical and Scientific Support Organisations (TSOs) are not only expert organisations helping operators to fulfil the legal obligations but they can perform at least five tasks related to regulatory authority activities. Namely, TSOs can be an expert support when preparing legislation or guidelines. They can provide specific technical service e.g. providing independent monitoring of radioactivity in the environment or monitoring of foodstuff. They can also provide valuable data to regulatory authorities because they follow the achievements of science and technologies i.e. they are familiar with best available techniques and technologies. In many cases TSOs can be a pool of future employees of regulatory authorities and TSOs are expert or technical support at on-site inspections. Involvement of TSOs in on-site inspections either foreseen inspections or interventions requires very well defined roles of all organisations involved. Regarding the experiences of the Slovenian Nuclear Safety Administration the involvement of TSOs in on-site inspections is very beneficial to all stakeholders and leads not only to less financial and other burdens posed on the owner of sources but also basic safety requirements are implemented efficiently. (author)

  4. Radiographic inspection on offshore platforms

    International Nuclear Information System (INIS)

    Soares, Sergio Damasceno; Sperandio, Augusto Gasparoni

    1994-01-01

    One of the great challenges for non-destructive inspection is on offshore platforms, where safety is a critical issue. Inspection by gammagraphy is practically forbidden on the platform deck due to problems to personnel safety and radiological protection. Ir-192 sources are used and the risk of an accident with loss of radioisotope must be considered. It is unfeasible to use gammagraphy, because in case of an accident the rapid evacuation from the platform would be impossible. This problem does not occur when X-ray equipment is used as the radiation source. The limited practicality and portability of the X-ray equipment have prevented its use as a replacement for the gammagraphy. This paper presents the preliminary tests to see the viable use of radiographic tests with constant potential on offshore platforms. (author). 2 refs., 1 fig., 2 tabs, 3 photos

  5. Organized labor and the origins of the Occupational Safety and Health Act.

    Science.gov (United States)

    Asher, Robert

    2014-11-01

    New Solutions is republishing this 1991 article by Robert Asher, which reviews the history of organized labor's efforts in the United States to secure health and safety protections for workers. The 1877 passage of the Massachusetts factory inspection law and the implementation of primitive industrial safety inspection systems in many states paralleled labor action for improved measures to protect workers' health and safety. In the early 1900s labor was focusing on workers' compensation laws. The New Deal expanded the federal government's role in worker protection, supported at least by the Congress of Industrial Organizations (CIO), but challenged by industry and many members of the U.S. Congress. The American Federation of Labor (AFL) and the CIO backed opposing legal and inspection strategies in the late 1940s and through the 1950s. Still, by the late 1960s, several unions were able to help craft the Occupational Safety and Health Act of 1970 and secure new federal protections for U.S. workers.

  6. A 3D printed smartphone optosensing platform for point-of-need food safety inspection.

    Science.gov (United States)

    Liu, Zhonggang; Zhang, Yali; Xu, Shujia; Zhang, Heng; Tan, Yixun; Ma, Chenming; Song, Rong; Jiang, Lelun; Yi, Changqing

    2017-05-08

    The deficiency in rapid and in-field detection methods and portable devices that are reliable, easy-to-use, and low cost, results in the difficulties to uphold the high safety standards in China. In this study, we introduce a rapid and cost-effective smartphone-based method for point-of-need food safety inspection, which employs aptamer-conjugated AuNPs as the colorimetric indicator, and a battery-powered optosensing accessory attached to the camera of a smartphone for transmission images capture. A user-friendly and easy-to-use Android application is developed for automatic digital image processing and result reporting. Streptomycin (STR) is selected as the proof-of-concept target, and its specific quantitation can be realized with a LOD of 12.3 nM (8.97 μg kg -1 ) using the reported smartphone-based method. The quantitation of STR in honey, milk and tap water confirm the reliability and applicability of the reported method. The extremely high acceptance of smartphone in remote and metropolitan areas of China and ease-of-use of the reported method facilitate active food contaminant and toxicant screening, thus making the implementation of the whole food supply chain monitoring and surveillance possible and hence significantly improving the current Chinese food safety control system. Copyright © 2017 Elsevier B.V. All rights reserved.

  7. Statement of the IRSN on the safety re-examination assessment made by EDF within the frame of the third decennial inspection of the 900 MW reactors

    International Nuclear Information System (INIS)

    2008-01-01

    The IRSN (the French Institute of Radioprotection and Nuclear Safety) here presents an assessment of the studies performed by EDF within the frame of the safety re-examination associated to the third decennial inspections of the 900 MW reactors, and of the modifications resulting from these studies with respect to the originally defined objectives of this re-examination. The aim of this report is to allow the ASN (Autorite de Surete Nucleaire, the Nuclear Safety Authority) stating the 900 MW reactor ability to carry on their operation until the fourth decennial inspections. Different themes and studies are assessed: internal and external aggressions (flooding, explosions, fire, seismic control, and climatic aggressions), accident assessments and their radiological consequences (failure of various components, the performing of probabilistic studies, confining procedures, structures and devices, etc.), operation and design of various systems and of civil engineering works. Several documents or extracts of official reports are given in appendix, expressing notably various recommendations on the here-above topics

  8. Improvement of foundation for inspection

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    Japan Nuclear Energy Safety Organization has been carrying out improvement of inspection system for nuclear plants in Japan since 2003FY. The new inspection system was introduced into nuclear power plants in{sub -}2008FY. In this project, improvement of comprehensive plant performance assessment and management tool for the new inspection system are developed. In 2012FY, a trend analysis method of the plant performance was developed with reference to the IAEA literature. And the trend analysis was tried based on the results of the comprehensive plant performance assessment of all domestic plants except Fukushima-Daiichi Nuclear Power Station. In addition, the teaching materials for QMS training guideline were made. And improvement of a quality management system evaluation support tool was performed. (author)

  9. Improvement of foundation for inspection

    International Nuclear Information System (INIS)

    2013-01-01

    Japan Nuclear Energy Safety Organization has been carrying out improvement of inspection system for nuclear plants in Japan since 2003FY. The new inspection system was introduced into nuclear power plants in - 2008FY. In this project, improvement of comprehensive plant performance assessment and management tool for the new inspection system are developed. In 2012FY, a trend analysis method of the plant performance was developed with reference to the IAEA literature. And the trend analysis was tried based on the results of the comprehensive plant performance assessment of all domestic plants except Fukushima-Daiichi Nuclear Power Station. In addition, the teaching materials for QMS training guideline were made. And improvement of a quality management system evaluation support tool was performed. (author)

  10. TIS General Safety Group Annual Report 2000

    CERN Document Server

    Weingarten, W

    2001-01-01

    This report summarises the main activities of the General Safety (GS) Group of the Technical Inspection and Safety Division (TIS) during the year 2000, and the results obtained. The different topics in which the Group is active are covered: general safety inspections and ergonomy, electrical, chemistry and gas safety, chemical pollution containment and control, industrial hygiene, the safety of civil engineering works and outside contractors, fire prevention and the safety aspects of the LHC experiments.

  11. Incision of the heart during meat inspection of fattening pigs - A risk-profile approach.

    Science.gov (United States)

    Leps, J; Fries, R

    2009-01-01

    Meat inspection in the EU is based on Regulation (EC) 854/2004. Accordingly a risk based meat inspection should be implemented. In this paper, the incision of the heart in pig meat inspection is discussed with respect to efficacy. The incision especially can reveal the presence of endocarditis. Here, Erysipelothrixrhusiopathiae (E. rhusiopathiae) and/or Streptococcussuis (S. suis) are of particular concern. Both agents are regarded to be zoonotic agents. There is some evidence for infection of humans via an alimentary pathway. Hence, the occurrence of E. rhusiopathiae and S. suis is a concern of public health (PH) as well as veterinary public health (VPH). However, other measures, including on-farm disease prevention and diagnosis, seem to be more important for food safety. It is concluded that the incision and inspection of the heart is not justifiable with respect to PH aspects.

  12. Vision based tunnel inspection using non-rigid registration

    Science.gov (United States)

    Badshah, Amir; Ullah, Shan; Shahzad, Danish

    2015-04-01

    Growing numbers of long tunnels across the globe has increased the need for safety measurements and inspections of tunnels in these days. To avoid serious damages, tunnel inspection is highly recommended at regular intervals of time to find any deformations or cracks at the right time. While following the stringent safety and tunnel accessibility standards, conventional geodetic surveying using techniques of civil engineering and other manual and mechanical methods are time consuming and results in troublesome of routine life. An automatic tunnel inspection by image processing techniques using non rigid registration has been proposed. There are many other image processing methods used for image registration purposes. Most of the processes are operation of images in its spatial domain like finding edges and corners by Harris edge detection method. These methods are quite time consuming and fail for some or other reasons like for blurred or images with noise. Due to use of image features directly by these methods in the process, are known by the group, correlation by image features. The other method is featureless correlation, in which the images are converted into its frequency domain and then correlated with each other. The shift in spatial domain is the same as in frequency domain, but the processing is order faster than in spatial domain. In the proposed method modified normalized phase correlation has been used to find any shift between two images. As pre pre-processing the tunnel images i.e. reference and template are divided into small patches. All these relative patches are registered by the proposed modified normalized phase correlation. By the application of the proposed algorithm we get the pixel movement of the images. And then these pixels shifts are converted to measuring units like mm, cm etc. After the complete process if there is any shift in the tunnel at described points are located.

  13. Inspection of Emergency Arrangements

    International Nuclear Information System (INIS)

    2013-01-01

    The Working Group on Inspection Practices (WGIP) was tasked by the NEA CNRA to examine and evaluate the extent to which emergency arrangements are inspected and to identify areas of importance for the development of good inspection practices. WGIP members shared their approaches to the inspection of emergency arrangements by the use of questionnaires, which were developed from the requirements set out in IAEA Safety Standards. Detailed responses to the questionnaires from WGIP member countries have been compiled and are presented in the appendix to this report. The following commendable practices have been drawn from the completed questionnaires and views provided by WGIP members: - RBs and their Inspectors have sufficient knowledge and information regarding operator's arrangements for the preparedness and response to nuclear emergencies, to enable authoritative advice to be given to the national coordinating authority, where necessary. - Inspectors check that the operator's response to a nuclear emergency is adequately integrated with relevant response organisations. - Inspectors pay attention to consider the integration of the operator's response to safety and security threats. - The efficiency of international relations is checked in depth during some exercises (e.g. early warning, assistance and technical information), especially for near-border facilities that could lead to an emergency response abroad. - RB inspection programmes consider the adequacy of arrangements for emergency preparedness and response to multi-unit accidents. - RBs assess the adequacy of arrangements to respond to accidents in other countries. - The RB's role is adequately documented and communicated to all agencies taking part in the response to a nuclear or radiological emergency. - Inspectors check that threat assessments for NPPs have been undertaken in accordance with national requirements and that up-to-date assessments have been used as the basis for developing emergency plans for

  14. Validated automated ultrasonic inspections of the Sizewell 'B' reactor pressure vessel

    International Nuclear Information System (INIS)

    Dikstra, B.J.; Farley, J.M.

    1992-01-01

    Automated ultrasonic inspection was applied extensively during manufacture of the RPV for Sizewell 'B'. This was an important element of the safety case presented at the Sizewell 'B' public enquiry. This requirement reflected concern in the United Kingdom as to the effectiveness and reliability of ultrasonic inspections. By applying automated inspections in addition to the manual ultrasonic inspection carried out by the vessel manufacturer, the overall reliability of the inspection of the vessel would be considerably enhanced. The automated inspections carried out in the manufacturer's workshops were termed 'automated shop inspections' (ASIs). The ASIs were carried out in two contracts: the first to inspect the component forgings of the RPV, the second to inspect the pressure retaining welds. (author)

  15. Assessment of safety culture: Changing regulatory approach in Hungary

    International Nuclear Information System (INIS)

    Ronaky, Jozsef; Toth, Andras

    2002-01-01

    Hungarian Atomic Energy Authority (HAEA) is changing its inspection practice and assessment methods of safety performance and safety culture in operating nuclear facilities. The new approach emphasises integrated team inspection of safety cornerstones and systematic assessment of safety performance of operators. (author)

  16. The Agency's Safety Standards and Measures

    International Nuclear Information System (INIS)

    1976-04-01

    The Agency's Health and Safety Measures were first, approved by the Board of Governors on 31 March 1960 in implementation of Articles III.A.6 and XII of the Statute of the Agency. On the basis of the experience gained from applying those measures to projects carried out by Members under agreements concluded with the Agency, the Agency's Health and Safety Measures were revised in 1975 and approved by the Board of Governors on 25 February 1976. The Agency's Safety Standards and Measures as revised are reproduced in this document for the information of all Members

  17. Probabilistic safety analysis about the radiation risk for the driver in a fast-scan container/vehicle inspection system

    International Nuclear Information System (INIS)

    Li Junli; Zhu Guoping; Ming Shenjin; Cao Yanfeng

    2008-01-01

    A new Container/Vehicle Inspection System called fast-scan inspection system has been developed and used in some countries, which has a special advantage in scanning efficiency of 200 - 400 containers per hour. However, for its unique scanning mode, the fast-scan inspection system causes some worries about the radiation risk for the truck drivers, who will drive the container truck to pass through the scanning tunnel and might be exposed by the radiation beam in accidents. A PSA analysis, which has been widely used to evaluate the safety of nuclear power plant in the past, is presented here to estimate the probability of accidental exposure to the driver and evaluate the health risk. The fault tree and event tree analysis show that the probability of accidental exposure to the driver is pretty low and the main failure contributions are human errors and scanning control devices failures, which provides some recommendations for the further improvement about this product. Furthermore, on the basic of ICRP No.60 and 76 reports, the health risk to the truck driver is only about 4.0x10 -14 /a. Compared with the exempt level of 5x10 -7 /a, it can be concluded that the fast-scan system is safe enough for the truck driver. (author)

  18. An effective technique for the software requirements analysis of NPP safety-critical systems, based on software inspection, requirements traceability, and formal specification

    International Nuclear Information System (INIS)

    Koo, Seo Ryong; Seong, Poong Hyun; Yoo, Junbeom; Cha, Sung Deok; Yoo, Yeong Jae

    2005-01-01

    A thorough requirements analysis is indispensable for developing and implementing safety-critical software systems such as nuclear power plant (NPP) software systems because a single error in the requirements can generate serious software faults. However, it is very difficult to completely analyze system requirements. In this paper, an effective technique for the software requirements analysis is suggested. For requirements verification and validation (V and V) tasks, our technique uses software inspection, requirement traceability, and formal specification with structural decomposition. Software inspection and requirements traceability analysis are widely considered the most effective software V and V methods. Although formal methods are also considered an effective V and V activity, they are difficult to use properly in the nuclear fields as well as in other fields because of their mathematical nature. In this work, we propose an integrated environment (IE) approach for requirements, which is an integrated approach that enables easy inspection by combining requirement traceability and effective use of a formal method. The paper also introduces computer-aided tools for supporting IE approach for requirements. Called the nuclear software inspection support and requirements traceability (NuSISRT), the tool incorporates software inspection, requirement traceability, and formal specification capabilities. We designed the NuSISRT to partially automate software inspection and analysis of requirement traceability. In addition, for the formal specification and analysis, we used the formal requirements specification and analysis tool for nuclear engineering (NuSRS)

  19. Innovative phased array ultrasonic inspection solution for large rotor shafts

    Energy Technology Data Exchange (ETDEWEB)

    Maes, G.; Devos, D.; Tremblay, P., E-mail: gmaes@zetec.com [Zetec, Ville de Quebec, Quebec (Canada)

    2016-05-15

    The increasing needs of energy production led to new rotor shaft designs with larger dimensions. A new generation of nuclear power plants is already being deployed worldwide with such heavy components. Their implementation requires new inspection tools in order to guarantee the public safety and to ensure the quality of these critical parts. Due to the long sound path, conventional ultrasonic (UT) techniques cannot provide adequate detectability of the reference reflectors required by the existing codes. Also, some standards require multiple angle beams to be applied in addition to the straight beam inspection, and this leads to long inspection times. This paper will address the implementation and validation of phased array (PA) UT techniques, using a semi-flexible 2D array probe, for the inspection of large mono-block rotor shaft forgings. It will show how the beam focusing and steering capabilities of phased array UT probes can be used to overcome the issues occurring with conventional UT probes. Results of acoustic beam simulation, as well as detectability measurements and data acquisitions on representative test specimens will be presented and compared with conventional UT performance. Various aspects of the hardware and software specification will be addressed, as well as the potential reduction of the total inspection time. (author)

  20. 9 CFR 590.920 - Importer to make application for inspection of imported eggs and egg products.

    Science.gov (United States)

    2010-01-01

    ... inspection of imported eggs and egg products. 590.920 Section 590.920 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE EGG PRODUCTS INSPECTION INSPECTION OF EGGS AND EGG PRODUCTS (EGG PRODUCTS INSPECTION ACT) Imports § 590.920 Importer to make application for inspection of...

  1. Industrial hazard and safety handbook

    CERN Document Server

    King, Ralph W

    1979-01-01

    Industrial Hazard and Safety Handbook (Revised Impression) describes and exposes the main hazards found in industry, with emphasis on how these hazards arise, are ignored, are identified, are eliminated, or are controlled. These hazard conditions can be due to human stresses (for example, insomnia), unsatisfactory working environments, as well as secret industrial processes. The book reviews the cost of accidents, human factors, inspections, insurance, legal aspects, planning for major emergencies, organization, and safety measures. The text discusses regulations, codes of practice, site layou

  2. 49 CFR 192.241 - Inspection and test of welds.

    Science.gov (United States)

    2010-10-01

    ... NATURAL AND OTHER GAS BY PIPELINE: MINIMUM FEDERAL SAFETY STANDARDS Welding of Steel in Pipelines § 192.241 Inspection and test of welds. (a) Visual inspection of welding must be conducted by an individual qualified by appropriate training and experience to ensure that: (1) The welding is performed in accordance...

  3. Kartini reactor tank inspection using NDT method for safety improvement of the reactor operation

    International Nuclear Information System (INIS)

    Syarip; Sutondo, Tegas; Saleh, Chaerul; Nitiswati; Puradwi; Andryansah; Mudiharjo

    2002-01-01

    The inspection of Kartini reactor tank liner (TRK) by using Non Destructive Testing (NDT) methods to improve the reactor operation safety, have been done. The type of NDT used were: visual examination using an underwater camera and magnifier, replication survey using dental putty, hardness test using an Equotip D indentor, thickness test using ultrasonic probe, and dye penetrant test. The visual examination showed that the surface of TRK was in good condition. The hardness readings were considered to be consistent with the original condition of the tank and the slight hardness increase at the reactor core area consistent with the neutron fluence experienced -10 1 4 n/cm 2 . Results of ultrasonic thickness survey showed that in average the TRK thickness is between 5,0 mm - 6,5 mm, a low 2,1 mm thickness exists at the top of the TRK in the belt area (double layer aluminum plat, therefore do not influencing the safety ). The replica and dye penetrant test at the low thickness area and several suspected areas showed that it could be some defect from original manufacture. Therefore, it can be concluded that the TRK is still feasible for continued operation safely

  4. Inspection surveys of x-ray inspection systems: results of five years and implications on future management of radiation risks

    International Nuclear Information System (INIS)

    Maharaj, H.P.

    1999-01-01

    Until the mid-1980s, federal inspectors performed radiation surveys annually on individual x-ray inspection systems which were operated for security screening purposes in federal facilities nationwide, and problems identified were corrected. The surveys were undertaken because of perceived high radiation risks and a need to ensure worker and public external exposures were minimized. The x-ray inspection systems are federally regulated under the Radiation Emitting Devices (RED) Act and, initially they were assessed by model type against the design, construction and performance criteria specified in the applicable RED regulations (Schedule II, Part IV) and were found compliant. A subsequent study not only demonstrated a much lower radiation risk attributed to a combination of technological advances in x-ray system design with narrow primary beams, high efficiency detectors and image processing capability, but also stressed the need for proper equipment maintenance and continued education of operators and maintenance personnel. Survey frequency was thus reduced to once every 2-3 years in accordance with a 1993 federal operational standard (Safety Code 29). The radiation protection principles in Safety Code 29 are similar to those of the 1996 International Atomic Energy Agency (IAEA) Basic Safety Standards for the protection against ionizing radiation and the safety of radiation sources. The purpose of this study was to assess inspection-survey data from 1993 through 1997 to elicit guidance toward the future management of radiation risks associated with the operation of such x-ray systems. (author)

  5. Increasing for effectiveness of inspection of the use of radioactive substances well logging

    International Nuclear Information System (INIS)

    Hesty Rimadianny

    2015-01-01

    One of the utilization of nuclear power is the use of radioactive substances for well logging. To ensure the achievement of radiation safety and security in the use of radioactive substances for well logging activities BAPETEN carries out inspections in accordance with the mandate as sepulated in the Government Regulation No. 29 of 2008 on the Licensing Resource Utilization Ionizing Radiation and Nuclear Materials. Besides referring to the implementation of Government Regulation inspection also refers to BAPETEN Chairman Regulation No. 5 of 2009 on Radiation Safety in the Use of Radioactive material for well logging. In 2014, of 18 facilities inspected the most significant findings include the availability of equipment safety and security of radioactive substances, as well as the availability and suitability of documents and records of safety and security of radioactive substances for well logging activities. Based on these findings BAPETEN needs to make efforts to increase the effectiveness of inspections on the use of radioactive substances for well logging. Increasing the effectiveness of these inspections include a commitment for the frequency of well logging inspection, the number of qualified of inspectors in accordance with the established procedures and optimizing the law enforcement process which includes the application of administrative sanctions in the form of a written warning, license suspension, revocation until reporting to law enforcement. Besides, BAPETEN need to improve the effectiveness of outreach programs and legal guidance as a precaution in the long run. (author)

  6. 9 CFR 381.191 - Distribution of inspected products to small lot buyers.

    Science.gov (United States)

    2010-01-01

    ... small lot buyers. 381.191 Section 381.191 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE...; Exportation; or Sale of Poultry or Poultry Products § 381.191 Distribution of inspected products to small lot... small lot buyers (such as small restaurants), distributors or jobbers may remove inspected and passed...

  7. 14 CFR 125.507 - Fuel tank system inspection program.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 3 2010-01-01 2010-01-01 false Fuel tank system inspection program. 125... Airworthiness and Safety Improvements § 125.507 Fuel tank system inspection program. (a) Except as provided in... fuel tank is installed under a field approval, before June 16, 2008, the certificate holder must submit...

  8. 14 CFR 91.1507 - Fuel tank system inspection program.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 2 2010-01-01 2010-01-01 false Fuel tank system inspection program. 91... Airworthiness and Safety Improvements § 91.1507 Fuel tank system inspection program. (a) Except as provided in... fuel tank is installed under a field approval, before June 16, 2008, the operator must submit to the...

  9. General inspection strategy for fault diagnosis-minimizing the inspection costs

    International Nuclear Information System (INIS)

    Reinertsen, Rune; Wang Xiaozhong

    1995-01-01

    In this paper, a general inspection strategy for system fault diagnosis is presented. The procedure presented in this paper, is an improvement of methods described in papers by , and . This general strategy provides the optimal inspection procedure when the inspections require unequal effort and the minimum cut set probabilities are unequal. This feature makes the procedure described in this paper more useful for practical applications than the most recent procedure presented in the paper by Najmus-Saqib and Ishaque, which requires the minimum cut set probabilities to be equal. The inspection strategy described in this paper is based on first inspecting the basic event that will provide the maximum information gain per unit cost invested. The information gain is measured by the decrease of Shannon entropy. A detailed tutorial example is presented

  10. Generic Reliability-Based Inspection Planning for Fatigue Sensitive Details

    DEFF Research Database (Denmark)

    Sørensen, John Dalsgaard; Straub, Daniel; Faber, Michael Havbro

    2005-01-01

    of fatigue sensitive details in fixed offshore steel jacket platforms and FPSO ship structures. Inspection and maintenance activities are planned such that code based requirements to the safety of personnel and environment for the considered structure are fulfilled and at the same time such that the overall......The generic approach for planning of in-service NDT inspections is extended to cover the case where the fatigue load is modified during the design lifetime of the structure. Generic reliability-based inspection planning has been developed as a practical approach to perform inspection planning...... expected costs for design, inspections, repairs and failures are minimized. The method is based on the assumption of “no-finds” of cracks during inspections. Each fatigue sensitive detail is categorized according to their type of details (SN curves), FDF values, RSR values, inspection, repair and failure...

  11. Hospital safety climate surveys: measurement issues.

    Science.gov (United States)

    Jackson, Jeanette; Sarac, Cakil; Flin, Rhona

    2010-12-01

    Organizational safety culture relates to behavioural norms in the workplace and is usually assessed by safety climate surveys. These can be a diagnostic indicator on the state of safety in a hospital. This review examines recent studies using staff surveys of hospital safety climate, focussing on measurement issues. Four questionnaires (hospital survey on patient safety culture, safety attitudes questionnaire, patient safety climate in healthcare organizations, hospital safety climate scale), with acceptable psychometric properties, are now applied across countries and clinical settings. Comparisons for benchmarking must be made with caution in case of questionnaire modifications. Increasing attention is being paid to the unit and hospital level wherein distinct cultures may be located, as well as to associated measurement and study design issues. Predictive validity of safety climate is tested against safety behaviours/outcomes, with some relationships reported, although effects may be specific to professional groups/units. Few studies test the role of intervening variables that could influence the effect of climate on outcomes. Hospital climate studies are becoming a key component of healthcare safety management systems. Large datasets have established more reliable instruments that allow a more focussed investigation of the role of culture in the improvement and maintenance of staff's safety perceptions within units, as well as within hospitals.

  12. Performance-based inspection and maintenance strategies

    International Nuclear Information System (INIS)

    Vesely, W.E.

    1995-01-01

    Performance-based inspection and maintenance strategies utilize measures of equipment performance to help guide inspection and maintenance activities. A relevant measure of performance for safety system components is component unavailability. The component unavailability can also be input into a plant risk model such as a Probabilistic Risk Assessment (PRA) to determine the associated plant risk performance. Based on the present and projected unavailability performance, or the present and projected risk performance, the effectiveness of current maintenance activities can be evaluated and this information can be used to plan future maintenance activities. A significant amount of information other than downtimes or failure times is collected or can be collected when an inspection or maintenance is conducted which can be used to estimate the component unavailability. This information generally involves observations on the condition or state of the component or component piecepart. The information can be detailed such as the amount of corrosion buildup or can be general such as the general state of the component described as ' high degradation', ' moderate degradation', or ' low degradation'. Much of the information collected in maintenance logs is qualitative and fuzzy. As part of an NRC Research program on performance-based engineering modeling, approaches have been developed to apply Fuzzy Set Theory to information collected on the state of the component to determine the implied component or component piecepart unavailability. Demonstrations of the applications of Fuzzy Set Theory are presented utilizing information from plant maintenance logs. The demonstrations show the power of Fuzzy Set Theory in translating engineering information to reliability and risk implications

  13. MIR: an in-service inspection device for Superphenix 1 vessels

    International Nuclear Information System (INIS)

    Asty, M.; Ceccato, S.; Lerat, B.; Viard, J.

    1986-06-01

    The main and safety vessels of SUPERPHENIX 1 were designed to allow in-service inspections. The remote controlled inspection device MIR was developed for this purpose. It allows both visual and ultrasonic examinations to be performed. Basically, MIR consists of a tetrahedral structure provided with four steering and traction wheels, two for each vessel. A computer assisted control system enables it to be driven to any position on either the main or safety vessels. Operating conditions are briefly reviewed and the main features of MIR presented

  14. Strategy of Risk-Informed Inspection for Secondary Systems in NPPs

    International Nuclear Information System (INIS)

    Kim, So Young; Heo, Gyun Young

    2012-01-01

    Recently, unexpected accidents such as large-scale blackout have been occurred due to increasing demand of electricity. The unplanned trips have great influence over the economics although they rarely affect the safety of system. Because the cost for inspection and maintenance is limited, it is beneficial not only economically to take follow-up action in a timely manner to prevent plant trip but also in safety by protecting against the risk which is occurred from trip. In nuclear power plants (NPPs), the importance about risk-informed service such as inspection, maintenance and replacement is becoming on the rise. Risk-informed techniques such as in-service test, in-service inspection, design guide change and etc. are already used in nuclear field but these techniques are applied focusing on primary system for safety-related regulatory issues. It is needed to consider the optimization of inspection informed risk for entire plant including secondary system which is not applied enough. The study about risk-based inspection for boilers in thermal power field is in progress actively, but not for turbine cycle, which is similar with nuclear industry. Today, the most of inspections or tests for turbine cycle are time-based maintenance, being performed on time. It is required to perform condition-based maintenance by evaluating risk analyzing both of probability and consequence simultaneously about damage mechanisms that can be predicted by equipment or devices configuring the secondary system. Probability of failure (POF) is analyzed in terms of materials' ageing mechanisms, but consequence of failure (COF) should be evaluated in terms of thermohydraulic condition then it is needed to check power loss and period of maintenance. This paper is going to propose the idea to quantify the consequence of failure using the fault tree and simulation for secondary system, and propose quantitative risk-informed inspection by these approaches

  15. Optimal Inspection and Maintenance Strategies for Structural Systems

    DEFF Research Database (Denmark)

    Sommer, A. M.

    The aim of this thesis is to give an overview of conventional and optimal reliability-based inspection and maintenance strategies and to examine for specific structures how the cost can be reduced and/or the safety can be improved by using optimal reliability-based inspection strategies....... For structures with several almost similar components it is suggested that individual inspection strategies should be determined for each component or a group of components based on the reliability of the actual component. The benefit of this procedure is assessed in connection with the structures considered....... Furthermore, in relation to the calculations performed the intention is to modify an existing program for determination of optimal inspection strategies. The main purpose of inspection and maintenance of structural systems is to prevent or delay damage or deterioration to protect people, environment...

  16. The General Safety Group Annual Report 2001/2002

    CERN Document Server

    Weingarten, W

    2003-01-01

    This report summarizes the main activities of the General Safety (GS) Group of the Technical Inspection and Safety Division during 2001 and 2002, and the results obtained. The different topics in which the group is active are covered: general safety inspections and ergonomics, electrical, chemical and gas safety, chemical pollution containment and control, industrial hygiene, the safety of civil engineering works and outside contractors, fire prevention and the safety aspects of the LHC experiments.

  17. Shielding repair and comprehensive safety inspection of the nuclear-powered ship Mutsu

    International Nuclear Information System (INIS)

    Takada, Etsuo

    1982-01-01

    Eight years after the radiation leakage accident, the nuclear-powered ship Mutsu returned again to its home port Ominato. During the period, for four years, the n.s. Mutsu was subjected to shielding repair and comprehensive inspection at Sasebo port. In the future, the ship will start on experimental navigation after its functional and power-up tests. The works of shielding repair and the comprehensive inspection with subsequent repair are described in technical aspects. The basic policy of the repair was two points, i.e. the usage of shielding materials excellent in shielding capacity, less in radioactivation and enduring operating temperature, and structural strength resisting ship-hull acceleration, shock and vibration, enabling easy maintenance and inspection. Comprehensive inspection was made on not only machinery integrity but also the design itself. (Mori, K.)

  18. The operator's requirement for in service inspection at Hinkley Point 'B' power station

    International Nuclear Information System (INIS)

    Outram, J.F.

    The subject is discussed under the following heads: the need for reactor internal inspection (safety; commercial interest); the methods available (man access inspection; remote viewing inspection); experience with man access; experience with remote viewing; reactor outage time -comparison of the two methods; contamination control; conclusions. (U.K.)

  19. In-service inspection of nuclear power-plant pressure components

    International Nuclear Information System (INIS)

    Lautzenheiser, C.E.

    1976-01-01

    The early light-water-reactor systems for production of commercial power were designed and fabricated in accordance with the codes then being used for fossil-fired power-generating stations with some design changes for increased inspectability during fabrication. Over the past few years, major strides have been made in in-service inspection technology. Work has been under way to determine the reliability of nondestructive testing methods and to develop formal inspection programs throughout the world. The major problems associated with in-service inspection are the scarcity of qualified personnel, the variability in procedures and data recording between inspection agencies, and exposure of inspection personnel to radiation. Further work will be required to more completely mechanize piping inspections to reduce radiation exposure and to standardize inspection procedures, equipment, and certification of personnel. Worldwide attention to the requirements of the American Society of Mechanical Engineers' Boiler and Pressure Vessel Code, the size and integrity of inspection agencies, and efforts such as the development of personnel qualification and certification guides emphasize the importance of in-service inspection to nuclear safety

  20. A Simple Semantics and Static Analysis for Stack Inspection

    Directory of Open Access Journals (Sweden)

    Anindya Banerjee

    2013-09-01

    Full Text Available The Java virtual machine and the .NET common language runtime feature an access control mechanism specified operationally in terms of run-time stack inspection. We give a denotational semantics in "eager" form, and show that it is equivalent to the "lazy" semantics using stack inspection. We give a static analysis of safety, i.e., the absence of security errors, that is simpler than previous proposals. We identify several program transformations that can be used to remove run-time checks. We give complete, detailed proofs for safety of the analysis and for the transformations, exploiting compositionality of the eager semantics.

  1. Modelling the effects of road traffic safety measures.

    Science.gov (United States)

    Lu, Meng

    2006-05-01

    A model is presented for assessing the effects of traffic safety measures, based on a breakdown of the process in underlying components of traffic safety (risk and consequence), and five (speed and conflict related) variables that influence these components, and are influenced by traffic safety measures. The relationships between measures, variables and components are modelled as coefficients. The focus is on probabilities rather than historical statistics, although in practice statistics may be needed to find values for the coefficients. The model may in general contribute to improve insight in the mechanisms between traffic safety measures and their safety effects. More specifically it allows comparative analysis of different types of measures by defining an effectiveness index, based on the coefficients. This index can be used to estimate absolute effects of advanced driver assistance systems (ADAS) related measures from absolute effects of substitutional (in terms of safety effects) infrastructure measures.

  2. Rail inspection of RCF defects

    Directory of Open Access Journals (Sweden)

    Z. Popović

    2013-10-01

    Full Text Available Rail defects due to rolling contact fatigue (RCF threaten the traffic safety around the world. That hazard is more distinct on railways without adequate maintenance strategy. Realization of interoperability of European railway network demands from every infrastructure manager to have a maintenance plan for the infrastructure subsystem. Besides that, this plan includes rail inspection and strategy against RCF defects. This paper emphasizes the importance of rail inspection and early detection of RCF because the most of RCF crack should be removed in rail grinding campaigns (preventive, cyclical and corrective activities during the whole rail service life.

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

    Science.gov (United States)

    Singh, Hardeep; Sittig, Dean F

    2016-04-01

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

  4. Factors influencing safety in a sample of marked pedestrian crossings selected for safety inspections in the city of Oslo.

    Science.gov (United States)

    Elvik, Rune; Sørensen, Michael W J; Nævestad, Tor-Olav

    2013-10-01

    This paper reports an analysis of factors influencing safety in a sample of marked pedestrian crossings in the city of Oslo, Norway. The sample consists of 159 marked pedestrian crossings where a total of 316 accidents were recorded during a period of five years. The crossings were selected for inspection because of they were, for various reasons, regarded as sub-standard. The sample of crossings is therefore not representative of all pedestrian crossings in Oslo. Factors influencing the number of accidents were studied by means of negative binomial regression. Factors that were studied included the volume of pedestrians and vehicles, the number of traffic lanes at the crossing, the location of the crossing (midblock or junction), the type of traffic control, the share of pedestrians using the crossing and the speed of approaching vehicles. The analysis confirmed the presence of a "safety-in-numbers" effect, meaning that an increase in the number of pedestrians is associated with a lower risk of accident for each pedestrian. Crossings located in four-leg junctions or roundabouts had more accidents than crossings located in three-leg junctions or on sections between junctions. A high share of pedestrians crossing the road outside the marked crossing was associated with a high number of accidents. Increased speed was associated with an increased number of accidents. Copyright © 2013 Elsevier Ltd. All rights reserved.

  5. Handbook of laboratory health and safety measures

    International Nuclear Information System (INIS)

    Pal, S.B.

    1985-01-01

    The application of radioactive isotopes and various scientific instruments based on different ionizing and non-ionizing radiation have brought new safety problems to laboratory workers today. Therefore, there is a need to revise present knowledge of safety measures to deal with new hazards, thus broadening the outlook towards health and safety measures for contemporary laboratory staff. This handbook presents a series of articles on current knowledge regarding laboratory safety

  6. Safety aspects and operating experience of LWR plants in Japan

    International Nuclear Information System (INIS)

    Aoki, S.; Yoshioka, T.; Toyota, M.; Hinoki, M.

    1977-01-01

    To develop nuclear power generation for the future, it is necessary to put further emphasis on safety assurance and to endeavour to devise measures to improve plant availability, based on the careful analysis of causes that reduce plant availability. The paper discusses the results of studies on the following items from such viewpoints: (1) Safety and operating experience of LWR nuclear power plants in Japan: operating experience with LWRs; improvements in LWR design during the past ten years; analysis of the factors affecting plant availability; (2) Assurance of safety and measures to increase availability: measures for safety and environmental protection; measures to reduce radiation exposure of employees; appropriateness of maintenance and inspection work; measures to increase plant availability; measures to improve reliability of equipment and components; (3) Future technical problems. (author)

  7. In-service inspections of the reactor cooling system of pressurized water reactors

    International Nuclear Information System (INIS)

    Fuerste, W.; Hohnerlein, G.; Werden, B.

    1982-01-01

    In order to guarantee constant safety of the components of the reactor cooling system, regular in-service inspections are carried out after commissioning of the nuclear power plant. This contribution is concerned with the components of the reactor cooling system, referring to the legal requirements, safety-related purposes and scope of the in-service inspections during the entire period of operation of a nuclear power plant. Reports are made with respect to type, examination intervals, examination technique, results and future development. The functional tests which are carried out within the scope of the in-service inspections are not part of this contribution. (orig.) [de

  8. 40 CFR 265.403 - Inspections.

    Science.gov (United States)

    2010-07-01

    ... must inspect, where present: (1) Discharge control and safety equipment (e.g., waste feed cut-off systems, by-pass systems, drainage systems, and pressure relief systems) at least once each operating day... equipment is being operated according to its design; (3) The construction materials of the treatment process...

  9. 9 CFR 352.6 - Denial or withdrawal of inspection service.

    Science.gov (United States)

    2010-01-01

    ... improper means; (4) has knowingly represented that any exotic animal carcass, or exotic animal product, has... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Denial or withdrawal of inspection service. 352.6 Section 352.6 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF...

  10. Optical Measuring Technologies for Industrial and Scientific Applications

    International Nuclear Information System (INIS)

    Chugui, Yu V; Plotnikov, S V; Potashnikov, A K; Verkhogliad, A G

    2006-01-01

    The novel results of the R and D activity of TDI SIE SB RAS in the field of the optical measuring technologies, as well as laser technologies for solving safety problems are presented. For permanent noncontact bearing position inspection of oil-drilling platforms on Sakhalin coast (Russia) we have developed optical-electronic method and system SAKHALIN with cumulative traveled distance (3 km) measurement error less than 0.03%. To measure the rocks stress and to prevent the mountain impact, as well as for basic investigations, a set of optical-electronic deformers and systems was developed and produced. Multifunctional laser technological system LSP-2000 equipped by two Nd-YAG lasers was developed for cutting, welding and surface micro profiling with ablation process (working range of 3 x 2 x 0.6 m 3 , positioning error less than 10 mkm). Safety of Russian nuclear reactors takes 100% noncontact 3D dimensional inspection of all parts of fuel assemblies, including grid spacers. Results of development and testing the specialized high productive laser measuring machine, based on structured illumination, for 3D inspection of grid spacers with micron resolution are presented. Ensuring the safety of running trains is the actual task for railways. Using high-speed laser noncontact method on the base of triangulation position sensors, TDI SIE has developed and produced automatic laser diagnostic system COMPLEX for inspection of geometric parameters of wheel pairs (train speed up to 60 km/hr.), which is used successfully on Russian railways. Experimental results on measuring and laser technological systems testing are presented

  11. Fundamentals of overlay measurement and inspection using scanning electron-microscope

    Science.gov (United States)

    Kato, T.; Okagawa, Y.; Inoue, O.; Arai, K.; Yamaguchi, S.

    2013-04-01

    Scanning electron-microscope (SEM) has been successfully applied to CD measurement as promising tools for qualifying and controlling quality of semiconductor devices in in-line manufacturing process since 1985. Furthermore SEM is proposed to be applied to in-die overlay monitor in the local area which is too small to be measured by optical overlay measurement tools any more, when the overlay control limit is going to be stringent and have un-ignorable dependence on device pattern layout, in-die location, and singular locations in wafer edge, etc. In this paper, we proposed new overlay measurement and inspection system to make an effective use of in-line SEM image, in consideration of trade-off between measurement uncertainty and measurement pattern density in each SEM conditions. In parallel, we make it clear that the best hybrid overlay metrology is in considering each tool's technology portfolio.

  12. Examination on the safety of handling the fuel elements in the nuclear ship 'Mutsu'

    International Nuclear Information System (INIS)

    1977-01-01

    This is the report of the Examination Committee on Total Inspection and Repair Technologies for Mutsu to the Director of Science and Technology Agency and the Minister of Transport dated July 29, 1977. The committee concluded before that the total inspection on safety and the repair of shielding can be carried out as the fuel elements are loaded, and the safety can be secured sufficiently. It was decided at the meeting of ministers concerned with Mutsu on May 17 that the safety concerning handling the fuel elements of Mutsu should be examined by the committee. Under the premise that the fuel elements are loaded again and used after the total inspection on safety and the repair of shielding, the committee examined the methods and the basic concept of safety about the taking-out, transport and preservation of the fuel elements, and the conclusions obtained are reported. The contents of the examination are the outline of the fuel elements, the present condition of the fuel elements, the safety concerning taking-out, transport and preservation of the fuel elements, and the other measures required for securing safety. The committee thinks that the safety can be secured sufficiently if the works are carried out carefully. (Kako, I.)

  13. Regulatory Oversight of Safety Culture — Korea’s Experience

    International Nuclear Information System (INIS)

    Jung, S.J.; Choi, Y.S.; Kim, J.T.

    2016-01-01

    In Korea, a regulatory oversight program of safety culture was launched in 2012 to establish regulatory measures against several events caused by weak safety culture in the nuclear industry. This paper is intended to introduce the preliminary regulatory oversight framework, development and validation of safety culture components, pilot safety culture inspection results and lessons learned. The safety culture model should be based on a sound understanding of the national culture and industry characteristics where the model will be applied. The nuclear safety culture oversight model is being developed and built on the Korean regulatory system to independently assess the nuclear power operating organizations’ safety culture.

  14. Safety advice sheets

    CERN Multimedia

    HSE Unit

    2013-01-01

    You never know when you might be faced with questions such as: when/how should I dispose of a gas canister? Where can I find an inspection report? How should I handle/store/dispose of a chemical substance…?   The SI section of the DGS/SEE Group is primarily responsible for safety inspections, evaluating the safety conditions of equipment items, premises and facilities. On top of this core task, it also regularly issues “Safety Advice Sheets” on various topics, designed to be of assistance to users but also to recall and reinforce safety rules and procedures. These clear and concise sheets, complete with illustrations, are easy to display in the appropriate areas. The following safety advice sheets have been issued so far: Other sheets will be published shortly. Suggestions are welcome and should be sent to the SI section of the DGS/SEE Group. Please send enquiries to general-safety-visits.service@cern.ch.

  15. Safety improvement of Paks nuclear power plant

    International Nuclear Information System (INIS)

    Vamos, G.

    1999-01-01

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

  16. Development on inspection and recognition procedure of clearance level of radioactivity in metal wastes, to secure social safety for reused metals

    International Nuclear Information System (INIS)

    Hattori, Takatoshi

    2002-01-01

    The Central Research Institute of Electric Power Industry developed a new procedure automatically measurable on radioactivity level in metal wastes in high precision by using the newest three-dimensional (3D) shape measuring technology and 3D Monte-Carlo computing technology (a code to probabilistically compute formation and movement of gamma-ray from metal wastes to detectors) to contribute to inspection and recognition of clearance level of radioactivity. This procedure can prove no super micro amount of radioactivity of 250 Bq in metal wastes of testing objects. As this proof is an evaluation of conservative safety side showing no pollution at any 100 sq cm of surface of the metal wastes on considering for taking-out reference on matters, for its price, the procedure cancelled all of labors to test all of metal wastes surfaces by survey meter, and so on, and feasibility of overlook of pollution at places difficult to measure by using survey meters can perfectly excluded. Its practical tester is planned to produce at 2002 fiscal year, and testing performance against actual metal wastes is planned to confirm by its proof-test on 2003 to 2004 fiscal years. (G.K.)

  17. Application of risk-informed methods to in-service piping inspection in Framatome type nuclear power plants

    International Nuclear Information System (INIS)

    Kim, Jin Hoi; Lee, Jeong Seok; Yun, Eun Sub

    2014-01-01

    The Pressurized water reactor owners group (PWROG) developed and applied a risk-informed in-service inspection (RI-ISI) program, as an alternative to the existing ASME Section XI sampling inspection method. The RI-ISI programs enhance overall safety by focusing inspections of piping at high safety significance (HSS) locations where failure mechanisms are likely to be present. Additionally, the RI-ISI program can reduce nondestructive evaluation (NDE) exams, man-rem exposure for inspectors, and inspection time, among other benefits. The RI-ISI method of in-service piping inspection was applied to 3 units (KSNPs: Korea standard nuclear power plants) and is being deployed to the other units. In this paper, the results of RI-ISI for a Framatome type (France CPI) nuclear power plant are presented. It was concluded that application of RI-ISI to the plant could enhance and maintain plant safety, as well as provide the benefits of greater reliability.

  18. A major safety overhaul

    CERN Multimedia

    2003-01-01

    A redefined policy, a revamped safety course, an environmental project... the TIS (Technical Inspection and Safety) Division has begun a major safety overhaul. Its new head, Wolfgang Weingarten, explains to the Bulletin why and how this is happening.

  19. Visual inspection technology of the narrow and small confined area for monitoring feederpipe support of pressure tube in calandria reactor

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Jae Wan; Lee, Nam Ho; Choi, Young Soo [Korea Atomic Energy Research Institute, Taejon (Korea)

    1999-12-01

    There are 760 feederpipes, which they are connected to inlet/outlet of the 380 pressure tube channels on the front of the calandria, in CANDU-type Reactor of Wolsung Nuclear Power Plant. As an ISI(In-Service Inspection) and PSI (Post-Service Inspection) requirements, maintenance activities of measuring the thickness of curvilinear part of feederpipe and inspecting the feederpipe support area within calandria are needed to ensure continued reliable operation of nuclear power plant. And ultrasonic probe is used to measure the thickness of curvilinear part of feederpipe, however workers are exposed to radioactivity irradiation during the measurement period. But, it is exposed to radioactivity irradiation during the measurement period. But, it is impossible to inspect feederpipe support area thoroughly because of narrow and confined accessibility, that is , an inspection space between the pressure tube channels is less than 100 mm and pipes in feederpipe support area are congested. And also, workers involved in inspecting feederpipe support area are under the jeopardy of high-level radiation exposure. Concerns about sliding home, which make the move of feederpipe connected to pressure tube channel smooth as pressure tube expands and contracts in its axial direction, stuck to feedeerpipe support and some of the structural components have made necessary the development of video inspection probe system with narrow and confined accessibility to observe and inspect feederpipe support area more close. Using video inspection probe system, it is possible to inspect and repair abnormality of feederpipe support connected to pressure tube channels of the calandria more accurate and quantative than naked eye. Therefore, that will do much for ensuring safety of CANDU-type nuclear power plant. 45 figs.,31 tabs. (Author)

  20. Surface crack detection by magnetic particle inspection

    International Nuclear Information System (INIS)

    Goebbels, K.

    1988-01-01

    For ferromagnetic materials magnetic particle inspection is without doubt the most sensitive method to detect surface cracks and the least sensitive method referring to disturbing boundary conditions. Up to now the technique is based on experiments, experience, on empirical facts and on a subjective evaluation. This contribution for the first time presents a concept which allows the objective, reproducible as well as reliable magnetic particle inspection: Modelling of testing based on Maxwell's equations by finite element calculation; objective setting of test-parameters and their surveillance, handling systems, illumination and sensors, image processing and fully automated evaluation. Economy and safety of magnetic particle inspection are strongly improved by this procedure. (orig./HP) [de

  1. Risk-informed optimisation of railway tracks inspection and maintenance procedures

    International Nuclear Information System (INIS)

    Podofillini, Luca; Zio, Enrico; Vatn, Jorn

    2006-01-01

    Nowadays, efforts are being made by the railway industry for the application of reliability-based and risk-informed approaches to maintenance optimisation of railway infrastructures, with the aim of reducing the operation and maintenance expenditures while still assuring high safety standards. In particular, in this paper, we address the use of ultrasonic inspection cars and develop a methodology for the determination of an optimal strategy for their use. A model is developed to calculate the risks and costs associated with an inspection strategy, giving credit to the realistic issues of the rail failure process and including the actual inspection and maintenance procedures followed by the railway company. A multi-objective optimisation viewpoint is adopted in an effort to optimise inspection and maintenance procedures with respect to both economical and safety-related aspects. More precisely, the objective functions here considered are such to drive the search towards solutions characterized by low expenditures and low derailment probability. The optimisation is performed by means of a genetic algorithm. The work has been carried out within a study of the Norwegian National Rail Administration (Jernbaneverket)

  2. Safety climate and attitude as evaluation measures of organizational safety.

    Science.gov (United States)

    Isla Díaz, R; Díaz Cabrera, D

    1997-09-01

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

  3. Inspection and enforcement by the regulatory body for nuclear power plants

    International Nuclear Information System (INIS)

    1980-01-01

    This Safety Guide was prepared as part of the Agency's programme, referred to as the NUSS programme, for establishing Codes of Practice and Safety Guides relating to nuclear power plants. It supplements the Code of Practice on Governmental Organization for the Regulation of Nuclear Power Plants, IAEA Safety Series No.50-C-G and should be used in conjunction with that document. The purpose of this Guide is to provide information, guidance and recommendations to assist Member States in (1) establishing and conducting a regulatory inspection programme for nuclear power plants, (2) establishing requirements for the applicant/licensee in regard to regulatory inspection, (3) establishing a system for enforcing compliance with the requirements and decisions of the regulatory body

  4. Efficient improvement of nuclear power plant safety by reorganization of risk-informed safety importance evaluation methods for piping welded portions

    Energy Technology Data Exchange (ETDEWEB)

    Irie, Takashi; Hanafusa, Hidemitsu; Suyama, Takeshi [Institute of Nuclear Safety System, Inc., Mihama, Fukui (Japan); Morota, Hidetsugu; Kojima, Sigeo; Mizuno, Yoshinobu [Computer Software Development Co., Ltd., Tokyo (Japan)

    2002-09-01

    In this work, risk information was used to evaluate the safety importance of piping welded portions which were important for plant operation and maintenance of nuclear power plants. There are two types of risk-informed safety importance evaluation methods, namely the ASME method and the EPRI method. Since both methods have advantages and disadvantages, elements of each method were combined and reorganized. Considerations included whether the degradation mechanisms would be objectively evaluated and whether plant safety would be efficiently improved. The most objective and efficient method was as follows. Piping failure potential is quantitatively and objectively evaluated for failure with probabilistic fracture mechanics (PFM) and for other degradation mechanisms with empirical failure rates, and conditional core damage probability (CCDP) is calculated with PSA. This method reduces the inspected segment numbers to 1/4 of the deterministic method and increases the ratio of risk, which is covered by the inspected segments, to total risk from 80% of the deterministic method to 95%. Piping inspection numbers decreased for safety injection systems that were required the inspections by the deterministic method. Piping inspections were required for part of main feed water and main steam systems that were not required the inspections by the deterministic method. (author)

  5. Rail inspection system based on iGPS

    Science.gov (United States)

    Fu, Xiaoyan; Wang, Mulan; Wen, Xiuping

    2018-05-01

    Track parameters include gauge, super elevation, cross level and so on, which could be calculated through the three-dimensional coordinates of the track. The rail inspection system based on iGPS (indoor/infrared GPS) was composed of base station, receiver, rail inspection frame, wireless communication unit, display and control unit and data processing unit. With the continuous movement of the inspection frame, the system could accurately inspect the coordinates of rail; realize the intelligent detection and precision measurement. According to principle of angle intersection measurement, the inspection model was structured, and detection process was given.

  6. Outline of safety regulations and administrations for commercial nuclear power plants in Japan

    International Nuclear Information System (INIS)

    Kinichi Yamamoto

    1987-01-01

    Outline of safety regulations and administrations for the commercial nuclear power plants in Japan is briefly described. The strict measures for safety assurance are always taken based on the principle of defense-indepth. In the actual procedures of regulatory control, the examinations and inspections shall be performed at each individual step in the stage of applications, and also in the stage of constructions. Thus, those regulatory examinations and inspections shall be performed in detail and carefully, and at the most suitable time; resulting in an effective regulatory control by the Ministry of International Trade and Industry. (author)

  7. Control of radioactive sources in industry through regulatory inspections

    International Nuclear Information System (INIS)

    Leocadio, J.C.; Ramalho, A.T.; Pinho, A.S.; Lourenco, M.M.J.; Nicola, M.S.; D'Avila, R.L.; Melo, I.F.; Cucco, A.C.S.

    2005-01-01

    In Brazil, the applications of ionizing radiation in industry are accomplished about 900 radioactive facilities, which handle approximately 3.000 radiation sources. The control of radioactive sources used in industrial installations authorized by the Brazilian Nuclear Energy Commission (CNEN) is accomplished by Servico de Radioprotecao na Industria Radiativa (SERIR) of the Instituto de Radioprotecao e Dosimetria (IRD), Rio de Janeiro, RJ, Brazil. This service carries out regulatory inspections in the practices of industrial radiography, nuclear gauges, industrial irradiators and oil wells logging. The frequency of inspections depends on the type of practice, ranging from a year to 5 years, depending on the risk involved. This paper presents a brief description of the situation of radiation safety in the use of radioactive sources in the industries of the country. The results obtained with regulatory inspections at industrial installations demonstrate that the conditions of safety and radiation protection in these facilities are satisfactory when compared with the technical regulations, both national and international

  8. 46 CFR 61.05-20 - Boiler safety valves.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 2 2010-10-01 2010-10-01 false Boiler safety valves. 61.05-20 Section 61.05-20 Shipping... INSPECTIONS Tests and Inspections of Boilers § 61.05-20 Boiler safety valves. Each safety valve for a drum, superheater, or reheater of a boiler shall be tested at the interval specified by table 61.05-10. [CGD 95-028...

  9. Quality inspection of anisotropic scintillating crystals through measurement of interferometric fringe pattern parameters

    CERN Document Server

    Cocozzella, N; Majni, G; Paone, N; Rinaldi, D T

    2001-01-01

    Scintillating crystals are widely used as detectors in radiographic systems, computerized axial tomography devices and in calorimeters employed in high-energy physics. This paper results from a project motivated by the development of the CMS calorimeter at CERN, which will make use of a large number of scintillating crystals. In order to prevent crystals from breaking because of internal residual stress, a quality control system based on optic inspection of interference fringe patterns was developed. The principle of measurement procedures was theoretically modelled, and then a dedicated polariscope was designed and built, in order to observe the crystals under induced stresses or to evaluate the residual internal stresses. The results are innovative and open a new perspective for scintillating crystals quality control: the photoelastic constant normal to the optic axis of the lead tungstate crystals (PbWO sub 4) was measured, and the inspection procedure developed is applicable to mass production, not only t...

  10. On site PWR fuel inspection measurements for operational and design verification

    International Nuclear Information System (INIS)

    1996-01-01

    The on-site inspection of irradiated Pressurized Water Reactor (PWR) fuel and Non-Fuel Bearing Components (NFBC) is typically limited to visual inspections during refuelings using underwater TV cameras and is intended primarily to confirm whether the components will continue in operation. These inspections do not normally provide data for design verification nor information to benefit future fuel designs. Japanese PWR utilities and Nuclear Fuel Industries Ltd. designed, built, and performed demonstration tests of on-site inspection equipment that confirms operational readiness of PWR fuel and NFBC and also gathers data for design verification of these components. 4 figs, 3 tabs

  11. Wireless Roadside Inspection Phase II Tennessee Commercial Mobile Radio Services Pilot Test Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Franzese, Oscar [ORNL; Lascurain, Mary Beth [ORNL; Capps, Gary J [ORNL; Siekmann, Adam [ORNL

    2011-05-01

    The Federal Motor Carrier Safety Administration (FMCSA) Wireless Roadside Inspection (WRI) Program is researching the feasibility and value of electronically assessing truck and bus driver and vehicle safety at least 25 times more often than is possible using only roadside physical inspections. The WRI program is evaluating the potential benefits to both the motor carrier industry and to government. These potential benefits include reduction in accidents, fatalities and injuries on our highways and keeping safe and legal drivers and vehicles moving on the highways. WRI Pilot tests were conducted to prototype, test and demonstrate the feasibility and benefits of electronically collecting safety data message sets from in-service commercial vehicles and performing wireless roadside inspections using three different communication methods. This report summarizes the design, conduct and results of the Tennessee CMRS WRI Pilot Test. The purpose of this Pilot test was to demonstrate the implementation of commercial mobile radio services to electronically request and collect safety data message sets from a limited number of commercial vehicles operating in Tennessee. The results of this test have been used in conjunction with the results of the complimentary pilot tests to support an overall assessment of the feasibility and benefits of WRI in enhancing motor carrier safety (reduction in accidents) due to increased compliance (change in motor carrier and driver behavior) caused by conducting frequent safety inspections electronically, at highway speeds, without delay or need to divert into a weigh station

  12. Study on In-Service Inspection Program and Inspection Technologies for Commercialized Sodium-Cooled Fast Reactor

    International Nuclear Information System (INIS)

    Masato Ando; Shigenobu Kubo; Yoshio Kamishima; Toru Iitsuka

    2006-01-01

    The objective of in-service inspection of a nuclear power plant is to confirm integrity of function of components necessary to safety, and satisfy the needs to protect plant investment and to achieve high plant ability. The sodium-cooled fast reactor, which is designed in the feasibility study on commercialized fast reactor cycle systems in Japan, has two characteristics related to in-service inspection. The first is that all sodium coolant boundary structures have double-wall system. Continuous monitoring of the sodium coolant boundary structures are adopted for inspection. The second characteristic is the steam generator with double-wall-tubes. Volumetric testing is adopted to make sure that one of the tubes can maintain the boundary function in case of the other tube failure. A rational in-service inspection concept was developed taking these features into account. The inspection technologies were developed to implement in-service inspection plan. The under-sodium viewing system consisted of multi ultrasonic scanning transducers, which was used for imaging under-sodium structures. The under-sodium viewing system was mounted on the under-sodium vehicle and delivered to core internals. The prototype of under-sodium viewing system and vehicle were fabricated and performance tests were carried out under water. The laboratory experiments of volumetric testing for double-wall-tubes of steam generator, such as ultrasonic testing and remote-field eddy current testing, were performed and technical feasibility was assessed. (authors)

  13. Regulatory aspects of NPP safety

    International Nuclear Information System (INIS)

    Stuller, J.; Brandejs, P.; Miasnikov, A.; Svab, M.

    1999-01-01

    In beginning, a history of legislative process regulating industrial utilisation of nuclear energy is given, including detailed list of decrees issued by the first regulatory body supervising Czech nuclear installations - Czechoslovak Atomic Energy Commission (CSKAE). Current status of nuclear regulations and radiation protection, especially in connection with Atomic Act (Act No 18/1997 Coll.), is described. The Atomic Act transfers into the Czech legal system a number of obligations following from the Vienna Convention on Civil Liability for Nuclear Damage and Joint Protocol relating to the Application of the Vienna and Paris Convention, to which the Czech Republic had acceded. Actual duties and competence of current nuclear regulatory body - State Office for Nuclear Safety (SUJB) - are given in detail. Execution of the State supervision of peaceful utilisation of nuclear energy and ionising radiation is laid out in several articles of the Act, which comprises: control activities of the SUJB, remedial measures, penalties. Material and human resources are sufficient for fulfilment of the basic functions for which SUJB is authorised by the law. For 1998, the SUJB allotted staff of 149, approximately 2/3 of that number are nuclear safety and radiation protection inspectors. The SUJB budget for 1998 is approximately 180 million Czech crowns (roughly 6 million US dollars). Inspection activity of SUJB is carried out in three different ways: routine inspections, planned specialised inspections, inspections as a response to a certain situation (ad-hoc inspections). Approach to the licensing of major plant upgrades and backfittings are mainly illustrated on the Temelin NPP licensing. Regulatory position and practices concerning review activities are presented. (author)

  14. Conceptual design of in-service inspection and maintenance for KALIMER

    International Nuclear Information System (INIS)

    Ju, Y. S.; Kim, S. H.; Koo, K. H.; You, B.

    1999-01-01

    In-service inspection and maintenance are very important for the safety and availability of nuclear power plants. The conceptual requirements of in-service inspection and maintenance should be reflected in the earlier design process for the verification of the plant operability and reliability. In this paper the fundamental approaches of the inspection and maintenance for KALIMER are established to ensure the structural integrity and operability for KALIMER. The general strategy and methodology of maintenance and inspection for the reactor system and components are proposed and described for satisfying the intents of the Section XI, Division 3, of ASME code and considering the design characteristics of KALIMER

  15. In-Service Inspection system for coolant channels of Indian PHWRS - evolution and experience

    International Nuclear Information System (INIS)

    Puri, R.K.; Singh, M.

    2006-01-01

    In-Service Inspection (ISI) is the most important of all periodic monitoring and surveillance activities for assuring the structural integrity of coolant channels in the life extension and management of pressurized heavy water reactors (PHWR-CANDU). Indian PHWRs (220 MWe) are characterized by consists by 306 coolant channels in each unit. These channels have to be inspected for various parameters over the operating life of the reactor. ISI of coolant channels necessitated the indigenous development of an inspection system called BARCIS (BARC Channel Inspection System) at Bhabha Atomic Research Center. BARCIS consists of mainly three parts; drive and control unit, special sealing plug and an inspection head carrying various NDT sensors. Five such systems have been built and deployed at various power plants. The paper deals with the development of the BARCIS system for meeting the ISI requirements of coolant channels, development cycle of this system from its conception to evolution to the present state, challenges, data generated and experience gained (ISI of nearly 900 coolant channels has been completed). Prior to BARCIS, pressure tube gauging equipment for pre-service inspection of coolant tubes was developed in 1980. Moreover a tool for ISI of coolant channels in dry condition was developed in 1990. The paper also describes evolution of various contingency procedures and devices developed over the last one decade. Future plans taking into account technological advancement, changes in the scope of inspection due to design and operating experiences and plant layout will also be covered. The paper describes the efforts put in to develop drive and control mechanism to suit the different vault layouts. The drive mechanism is responsible for linear and rotary movement of the inspection head to carry out 100% volumetric inspection. Special emphasis has been laid on the safety devices required during the inspection activity. Special measures for heavy water retention in

  16. IRSN-ANCCLI partnership. IRSN-ANCCLI seminar on decennial inspections of 900 MWe reactors - November 2010

    International Nuclear Information System (INIS)

    Rollinger, Francois; Delalonde, Jean-Claude; Hubert, F.; Paulmaz, X.; Tindillere, M.; Lheureux, Y.; Junker, R.; Sene, M.

    2010-11-01

    This seminar addressed the commitment of local information commissions (CLI) in the analysis and follow-up of the third decennial inspections of the French 900 MWe nuclear reactors. A first session addressed topics directly related to these inspections. Contributions proposed under the form of Power Point presentations by experts and representatives of the IRSN, EDF and CLIs addressed the following issues: safety re-examination of EDF 900 MWe reactors at the occasion of the third decennial inspection, activities of the IRSN related to skill management in nuclear power stations, implementation of the third decennial inspection of the unit 1 of the Fessenheim nuclear power station, the issue of follow-up by a local information commission after a decennial inspection. A second session addressed topics not related to decennial inspections and were proposed by Gravelines and Dampierre local information commissions: analysis of significant safety events, issues of skill management in nuclear power stations

  17. Evaluation and improvement in nondestructive examination (NDE) reliability for inservice inspection of light water reactors

    International Nuclear Information System (INIS)

    Doctor, S.R.; Andersen, E.S.; Bowey, R.E.; Diaz, A.A.; Good, M.S.; Heasler, P.G.; Hockey, R.L.; Simonen, F.A.; Spanner, J.C.; Taylor, T.T.; Vo, T.V.

    1991-01-01

    This program is intended to establish the effectiveness, reliability and adequacy of inservice inspection of reactor pressure vessels and primary piping systems and the impact of ISI reliability on system integrity. The objectives of the program include: (a) determine the effectiveness and reliability of ultrasonic inservice inspection (ISI) performed on commercial, light water reactor pressure vessels and piping; (b) recommend Code changes to the inspection procedures to improve the reliability of ISI; (c) using fracture mechanics analysis, determine the impact of NDE unreliability on system safety and determine the level of inspection reliability required to assure a suitably low failure probability; (d) evaluate the degree of reliability improvement which could be achieved using improved NDE techniques; and (e) based on importance of component to safety, material properties, service conditions, and NDE uncertainties, formulate improved inservice inspection criteria (including sampling plan, frequency, and reliability of inspection) for revisions to ASME Section XI and regulatory requirements needed to assure suitably low failure probabilities

  18. NRC Information Notice No. 91-29, Supplement 1: Deficiencies identified during electrical distribution system functional inspections

    International Nuclear Information System (INIS)

    Rossi, C.E.

    1993-01-01

    During multidiscipline inspections such as safety system functional inspections (SSFIs) or safety system outage modification inspections (SSOMIs), the NRC identified a number of deficiencies related to the electrical distribution system (EDS). As a result of these deficiencies, the NRC developed the EDSFI to specifically evaluate the EDS. Since 1989, the NRC has performed over 50 EDSFIs, and found design weaknesses in the following generic areas: (1) undervoltage relay setpoints for degraded grid conditions; (2) interrupting capacity of fault protection devices; (3) improper coordination of fault protection devices; (4) analysis of emergency diesel generator (EDG) capacity to power safety-related loads during postulated accidents; and (5) EDG mechanical interfaces. Each of these issues are discussed

  19. Safety status of Russian research reactors

    International Nuclear Information System (INIS)

    Morozov, S.I.

    2001-01-01

    Gosatomnadzor of Russia is conducting the safety regulation and inspection activity related to nuclear and radiation safety at nuclear research facilities, including research reactors, critical assemblies and sub-critical assemblies. It implies implementing three major activities: 1) establishing the laws and safety standards in the field of research reactors nuclear and radiation safety; 2) research reactors licensing; and 3) inspections (or license conditions tracking and inspection). The database on nuclear research facilities has recently been updated based on the actual status of all facilities. It turned out that many facilities have been shutdown, whether temporary or permanently, waiting for the final decision on their decommissioning. Compared to previous years the situation has been inevitably changing. Now we have 99 nuclear research facilities in total under Gosatomnadzor of Russia supervision (compared to 113 in previous years). Their distribution by types and operating organizations is presented. The licensing and conduct of inspection processes are briefly outlined with emphasis being made on specific issues related to major incidents that happened in 2000, spent fuel management, occupational exposure, effluents and emissions, emergency preparedness and physical protection. Finally, a summary of problems at current Russian research facilities is outlined. (author)

  20. Procedure for the determination of gap and base ground surface configurations beneath the bottom plate of storage tanks using neutron gauging inspection techniques : including radiation safety procedure and emergency procedure

    International Nuclear Information System (INIS)

    Jaafar Abdullah

    1993-01-01

    The procedure is intended for the neutron gauging inspection of gap between the bottom plate and the foundation of bulk storage tanks, which potentially exhibit uneven sinking of the bottom plate and the foundation. Its describes the requirements for the performance of neutron back scattered inspection techniques (or radiometric non-destructive evaluation techniques), using an isotopic neutron source associated with neutron detecting systems, to detect and size the gap between the bottom plate and the foundations as well as to quantify the presence of hydrogenous materials (e.g. oil or water) underneath the bottom plate. This procedure is not only outline the requirements for the neutron gauging inspection, but also describes the requirements which shall be taken into account in formulating the radiation safety and emergency procedures for the neutron gauging inspection works

  1. 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)

  2. Validation of Sizewell ''B'' ultrasonic inspections -- Messages for performance demonstration

    International Nuclear Information System (INIS)

    Conroy, P.J.; Leyland, K.S.; Waites, C.

    1994-01-01

    At the time that the decisions leading to the construction of the Sizewell ''B'' plant were being made, public concern over the potential hazards of nuclear power was increasing. This concern was heightened by the accident at USA's Three Mile Island plant. The result of this and public pressure was that an extensive public inquiry was held in addition to the UK's normal licensing process. Part of the evidence to the inquiry supporting the safety case relied upon the ability of ultrasonic inspections to demonstrate that the Reactor Pressure Vessel (RPV) and other key components were free from defects that could threaten structural integrity. Evidence from a variety of trials designed to investigate the performance capability of ultrasonic inspection revealed that although ultrasonic inspection had the potential to satisfy this requirement its performance in practice was heavily dependent upon the details of application. It was therefore generally recognized that some form of inspection validation was required to provide assurance that the equipment, procedures and operators to be employed were adequate for purpose. The concept of inspection validation was therefore included in the safety case for the licensing of Sizewell ''B''. The UK validation trials covering the ultrasonic inspections of the Sizewell ''B'' PWR Reactor Pressure Vessel are now nearing completion. This paper summarizes the results of the RPV validations and considers some of the implications for ASME 11 Appendix 8 the US code covering performance demonstration

  3. Preventive maintenance measures and repeat tests on actuators

    International Nuclear Information System (INIS)

    Hueren, H.

    1990-01-01

    At Biblis Nuclear Power Station, about 1500 electrical actuators and variable speed drives of various model ranges and with various driving end speeds and actuating times are installed and about 600 of these are located in important safety engineering systems. In order to optimize the preventive maintenance measures on the drives, a data bank has been established into which are stored, in addition to the fixed type data of each drive, inter alia, statements about location of application, valve type, inspection cycle, calendar year of next maintenance, findings during inspection measures and causes of faults. Before each unit inspection, in addition to the inspection lists, the maintenance and installation records and also the associated job instructions are produced from this data processing equipment. (orig.) [de

  4. Survey on requirements for independent reviews and inspections of electrical and I and C equipment

    International Nuclear Information System (INIS)

    Byman, Karin; Groenkvist, Stefan; Egerbo, Anders; Nilsson, Thomas

    2009-03-01

    In this survey, licensing procedures for the implementation of different kinds of components and systems in nuclear power plants have been studied in four European countries: Belgium (Finland), Germany, and Switzerland. The main focus has been to describe the general features of the licensing procedures for electrical and for instrumentation and control (IandC) equipment and systems. The regulatory framework for the operation of nuclear power plants in Belgium is based on the American regulations. The licensing procedure for each modification of significance for the safety of a plant is carried out by the authorised inspection organisation (AVN), which follows its own procedures for the review of the modification file, the commissioning, and conformity check of the installation. These procedures are very general and independent of the technical domain of the equipment or system and AVN uses the US regulations standard review plan (SRP) as a reference for technical reviews. The Federal Agency for Nuclear Control (FANC) is responsible for the surveillance of all nuclear activities in Belgium, but the private non-profit authorised inspection organisation (AVN) does perform inspections and other regulatory tasks delegated by FANC. Controls of electrical components and systems with regard to the general Belgian electrical regulations are performed by accredited inspection organisations. The regulatory framework for the safety of nuclear activities in Finland is domestic and detailed safety requirements are provided by the Radiation and Nuclear Safety Authority (STUK). They cover specific requirements for the licensing procedure for electrical and IandC equipment. In Finland, there are no general differences in the licensing procedure for electrical, instrumentation, and mechanical equipment and the licensing procedure is basically the same for all types of systems, structures and equipment. STUK has the responsibility for the regulatory control in Finland and may seek

  5. Safety evaluation for the inner canister closure station

    International Nuclear Information System (INIS)

    Glasscock, J.R.

    1987-01-01

    The Inner Canister Closure Station (ICCS), built by Remote Technology Corporation, will be operability tested. The ICCS is used to remotely leak test Inner Canister Closures (ICC's) and replace ICC's that are not water tight. After operability testing, the ICCS will be inspected and sent to the 717-F mock-up shop for remotability demonstration and dimensional checks, then installed in the Vitrification Building, 221-S. An analysis of potential safety hazards, equipment safety features, and procedural controls indicates that the ICCS can be operated without undue hazard to employees or to the public. A safety inspection and a new equipment inspection will be held before operation to verify that the ICCS meets Savannah River Site safety requirements. 4 refs., 6 figs

  6. 46 CFR 115.910 - Passenger Ship Safety Certificate.

    Science.gov (United States)

    2010-10-01

    ...) The route specified on the Certificate of Inspection and the SOLAS Passenger Ship Safety Certificate... 46 Shipping 4 2010-10-01 2010-10-01 false Passenger Ship Safety Certificate. 115.910 Section 115... MORE THAN 150 PASSENGERS OR WITH OVERNIGHT ACCOMMODATIONS FOR MORE THAN 49 PASSENGERS INSPECTION AND...

  7. Nuclear safety in Slovak Republic. Regulatory aspects of NPP nuclear safety

    International Nuclear Information System (INIS)

    Lipar, M.

    1999-01-01

    Regulatory Authority (UJD) is appointed by the Slovak Republic National Council as an Executive Authority for nuclear safety supervision. Nuclear safety legislation, organisation and resources of UJD, its role and responsibilities are described together with its inspection and licensing functions and International cooperation concerning improvements of safety effectiveness. Achievements of UJD are listed in detail

  8. Real-time line-width measurements: a new feature for reticle inspection systems

    Science.gov (United States)

    Eran, Yair; Greenberg, Gad; Joseph, Amnon; Lustig, Cornel; Mizrahi, Eyal

    1997-07-01

    The significance of line width control in mask production has become greater with the lessening of defect size. There are two conventional methods used for controlling line widths dimensions which employed in the manufacturing of masks for sub micron devices. These two methods are the critical dimensions (CD) measurement and the detection of edge defects. Achieving reliable and accurate control of line width errors is one of the most challenging tasks in mask production. Neither of the two methods cited above (namely CD measurement and the detection of edge defects) guarantees the detection of line width errors with good sensitivity over the whole mask area. This stems from the fact that CD measurement provides only statistical data on the mask features whereas applying edge defect detection method checks defects on each edge by itself, and does not supply information on the combined result of error detection on two adjacent edges. For example, a combination of a small edge defect together with a CD non- uniformity which are both within the allowed tolerance, may yield a significant line width error, which will not be detected using the conventional methods (see figure 1). A new approach for the detection of line width errors which overcomes this difficulty is presented. Based on this approach, a new sensitive line width error detector was developed and added to Orbot's RT-8000 die-to-database reticle inspection system. This innovative detector operates continuously during the mask inspection process and scans (inspects) the entire area of the reticle for line width errors. The detection is based on a comparison of measured line width that are taken on both the design database and the scanned image of the reticle. In section 2, the motivation for developing this new detector is presented. The section covers an analysis of various defect types, which are difficult to detect using conventional edge detection methods or, alternatively, CD measurements. In section 3

  9. Regulatory inspection in Spain

    International Nuclear Information System (INIS)

    Alvarez de Buergo, L.

    1977-01-01

    The 1964 Act on Nuclear Energy lays down that the Junta de Energia Nuclear is responsible for assessing the hazards of and inspecting nuclear power plants as well as for the transport of nuclear fuel for these plants. The Junta de Energia Nuclear has a specialised service, the Nuclear Safety Department in charge of performing these duties. Experience acquired from work in this field is analysed in this paper. (NEA) [fr

  10. Ultrasonic inspection of austenitic welds

    Energy Technology Data Exchange (ETDEWEB)

    Tomlinson, J R; Wagg, A R; Whittle, M J [N.D.T. Applications Centre, CEGB, Manchester (United Kingdom)

    1980-11-01

    The metallurgical structure of austenitic welds is described and contrasted with that found in ferritic welds. It is shown that this structure imparts a marked elastic anisotropy in the ultrasonic propagation parameters. Measurements of variations in the apparent attenuation of sound and deviations in the beam direction are described. The measurements are interpreted in terms of the measured velocity anisotropy. Two applications of the fundamental work are described. In the first it is shown how, by using short pulse compression wave probes, and with major modification of the welding procedure, a stainless steel fillet weld in an AGR boiler can be inspected. In the second application, alternative designs of a transition butt weld have been compared for ease of ultrasonic inspection. The effects of two different welding processes on such an inspection are described. Finally, the paper examines the prospects for future development of inspection and defect-sizing techniques for austenitic welds. (author)

  11. Farm Health and Safety

    Science.gov (United States)

    ... the United States. Farms have many health and safety hazards, including Chemicals and pesticides Machinery, tools and ... inspection and maintenance can help prevent accidents. Using safety gloves, goggles and other protective equipment can also ...

  12. Fires and Food Safety

    Science.gov (United States)

    ... Forms FSIS United States Department of Agriculture Food Safety and Inspection Service About FSIS District Offices Careers ... JSR 286) Actions ${title} Loading... Fires and Food Safety Fire! Few words can strike such terror. Residential ...

  13. Nuclear Reactor RA Safety Report, Vol. 14, Safety protection measures

    International Nuclear Information System (INIS)

    1986-11-01

    Nuclear reactor accidents can be caused by three type of errors: failure of reactor components including (1) control and measuring instrumentation, (2) errors in operation procedure, (3) natural disasters. Safety during reactor operation are secured during its design and construction and later during operation. Both construction and administrative procedures are applied to attain safe operation. Technical safety features include fission product barriers, fuel elements cladding, primary reactor components (reactor vessel, primary cooling pipes, heat exchanger in the pump), reactor building. Safety system is the system for safe reactor shutdown and auxiliary safety system. RA reactor operating regulations and instructions are administrative acts applied to avoid possible human error caused accidents [sr

  14. Historical occupational trichloroethylene air concentrations based on inspection measurements from Shanghai, China.

    Science.gov (United States)

    Friesen, Melissa C; Locke, Sarah J; Chen, Yu-Cheng; Coble, Joseph B; Stewart, Patricia A; Ji, Bu-Tian; Bassig, Bryan; Lu, Wei; Xue, Shouzheng; Chow, Wong-Ho; Lan, Qing; Purdue, Mark P; Rothman, Nathaniel; Vermeulen, Roel

    2015-01-01

    Trichloroethylene (TCE) is a carcinogen that has been linked to kidney cancer and possibly other cancer sites including non-Hodgkin lymphoma. Its use in China has increased since the early 1990s with China's growing metal, electronic, and telecommunications industries. We examined historical occupational TCE air concentration patterns in a database of TCE inspection measurements collected in Shanghai, China to identify temporal trends and broad contrasts among occupations and industries. Using a database of 932 short-term, area TCE air inspection measurements collected in Shanghai worksites from 1968 through 2000 (median year 1986), we developed mixed-effects models to evaluate job-, industry-, and time-specific TCE air concentrations. Models of TCE air concentrations from Shanghai work sites predicted that exposures decreased 5-10% per year between 1968 and 2000. Measurements collected near launderers and dry cleaners had the highest predicted geometric means (GM for 1986 = 150-190 mg m(-3)). The majority (53%) of the measurements were collected in metal treatment jobs. In a model restricted to measurements in metal treatment jobs, predicted GMs for 1986 varied 35-fold across industries, from 11 mg m(-3) in 'other metal products/repair' industries to 390 mg m(-3) in 'ships/aircrafts' industries. TCE workplace air concentrations appeared to have dropped over time in Shanghai, China between 1968 and 2000. Understanding differences in TCE concentrations across time, occupations, and industries may assist future epidemiologic studies in China. Published by Oxford University Press on behalf of the British Occupational Hygiene Society 2014.

  15. 46 CFR 61.30-20 - Automatic control and safety tests.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 2 2010-10-01 2010-10-01 false Automatic control and safety tests. 61.30-20 Section 61... TESTS AND INSPECTIONS Tests and Inspections of Fired Thermal Fluid Heaters § 61.30-20 Automatic control and safety tests. Operational tests and checks of all safety and limit controls, combustion controls...

  16. 9 CFR 312.3 - Official marks and devices to identify inspected and passed equine products.

    Science.gov (United States)

    2010-01-01

    ... inspected and passed equine products. 312.3 Section 312.3 Animals and Animal Products FOOD SAFETY AND... § 312.3 Official marks and devices to identify inspected and passed equine products. (a) The official... § 317.2 of this subchapter to identify inspected and passed mule and other (nonhorse) equine carcasses...

  17. Research on UAV Intelligent Obstacle Avoidance Technology During Inspection of Transmission Line

    Science.gov (United States)

    Wei, Chuanhu; Zhang, Fei; Yin, Chaoyuan; Liu, Yue; Liu, Liang; Li, Zongyu; Wang, Wanguo

    Autonomous obstacle avoidance of unmanned aerial vehicle (hereinafter referred to as UAV) in electric power line inspection process has important significance for operation safety and economy for UAV intelligent inspection system of transmission line as main content of UAV intelligent inspection system on transmission line. In the paper, principles of UAV inspection obstacle avoidance technology of transmission line are introduced. UAV inspection obstacle avoidance technology based on particle swarm global optimization algorithm is proposed after common obstacle avoidance technologies are studied. Stimulation comparison is implemented with traditional UAV inspection obstacle avoidance technology which adopts artificial potential field method. Results show that UAV inspection strategy of particle swarm optimization algorithm, adopted in the paper, is prominently better than UAV inspection strategy of artificial potential field method in the aspects of obstacle avoidance effect and the ability of returning to preset inspection track after passing through the obstacle. An effective method is provided for UAV inspection obstacle avoidance of transmission line.

  18. Saclay transparency and nuclear safety report 2009

    International Nuclear Information System (INIS)

    2006-01-01

    After a general presentation of the Saclay CEA Centre, this report presents the various safety arrangements in the different basic nuclear installations it possesses. These arrangements can be administrative, technical, or related to emergency situations or to inspections. It describes the organisation of radioprotection in the Saclay CEA Centre, indicates highlights for 2009, and gives results of dose measurements performed on the personnel. It reports significant events regarding nuclear safety and radioprotection in the various installations, gives and comments release measurements results and their impact on the environment (gaseous and liquid releases). It gives an overview of radioactive wastes stored in the different installations

  19. Regulatory inspection: a powerful tool to control industrial radioactive sources

    International Nuclear Information System (INIS)

    Silva, F.C.A. da; Leocadio, J.C.; Ramalho, A.T.

    2008-01-01

    An important contribution for Brazilian development, especially for the quality control of products, is the use of radiation sources by conventional industries. There are in Brazil roughly 3,000 radioactive sources spread out among 950 industries. The main industrial practices involved are: industrial radiography, industrial irradiators, industrial accelerators, well logging petroleum and nuclear gauges. More than 1,800 Radiation Protection Officers (RPOs) were qualified to work in these practices. The present work presents a brief description of the safety control over industrial radioactive installations performed by the Brazilian Regulatory Authority, i.e. the National Commission of Nuclear Energy (CNEN). This paper also describes the national system for radiation safety inspections, the regulation infrastructure and the national inventory of industrial installations. The inspections are based on specific indicators, and their periodicity depends on the risk and type of installation. The present work discusses some relevant aspects that must be considered during the inspections, in order to make the inspections more efficient in controlling the sources. One of these aspects regards the evaluation of the storage place for the sources, a very important parameter for preventing future risky situations. (author)

  20. Development of Surveillance and In-Service Inspection Programme for Indian Research Reactors Cirus and Dhruva

    International Nuclear Information System (INIS)

    Shukla, D.K.

    2006-01-01

    Many safety requirements for research reactors are quite similar to those of power reactors. For research reactors with a higher hazard potential, the use of safety codes and guides for power reactors is more appropriate. However, there are many important differences between power reactors and research reactors that must be taken into account to ensure that adequate safety margins are available in design and operation of the research reactor. Most research reactors may have small potential for hazard to the public compared to power reactors but may pose a greater potential hazard to the plant operators. The need for greater flexibility in use of research reactors for individual experiments requires a different safety approach. Safety rules for power reactors are required to be substantially modified for application to specific research reactor. Following the intent of the available safety guides for surveillance and In-Service Inspection of Nuclear Power Plants, guidelines were formulated to develop surveillance and In-Service Inspection programme for research reactors Cirus and Dhruva. Based on the specific design of these research reactors, regulatory requirements, the degree of sophistication and experience of the technical organization involved in operating the research reactor, guidelines were evolved for developing and implementing the surveillance and In-Service Inspection programme for research reactors Cirus (40 MWt) and Dhruva (100 MWt) located at Bhabha Atomic Research Centre, Trombay, Mumbai, India. Paper describes the approach adopted for formulation of surveillance and In-service Inspection programme for Dhruva reactor in detail. (author)

  1. Common QA/QM Criteria for Multinational Vendor Inspection

    International Nuclear Information System (INIS)

    2014-01-01

    This VICWG document provides the 'Common QA/QM Criteria' which will be used in Multinational Vendor Inspection. The 'Common QA/QM Criteria' provides the basic consideration when performing the Vendor Inspection. These criteria has been developed in conformity with International Codes and Standards such as IAEA, ISO and so on that MDEP member countries adopted. The purpose of the VICWG is to establish areas of co-operation in the Vendor Inspection practices among MDEP member countries as described in the MDEP issue-specific Terms of Reference (ToR). As part of this, from the beginning, a survey was performed to understand and to identify areas of commonality and differences between regulatory practices of member countries in the area of vendor inspection. The VICWG also collaborated by performing Witnessed Inspections and Joint Inspections. Through these activities, it was recognized that member countries commonly apply the IAEA safety standard (GS-R-3) to the vendor inspection criteria, and almost ail European member countries apply the ISO standard (ISO9001). In the US, the NRC regulatory requirement in 10 CFR, Part 50, Appendix B is used. South Korea uses the same criteria as in the US. As a result of the information obtained, a comparison table between codes and standards (IAEAGS-R-3, ISO 9001:2008.10CFR50 Appendix Band ASME NQA-1) has been developed in order to inform the development of 'Common QA/QM Criteria'. The result is documented in Table 1, 'MDEP CORE QA/QM Requirement and Comparison between Codes and Standards'. In addition, each country's criteria were compared with the US 10CFR50 Appendix B as a template. Table 2 shows VICWG Survey on Quality Assurance Program Requirements. Through these activities above, we considered that the core requirements should be consistent with both IAEA safety standard and ISO standard, and considered that the common requirements in the US 10CFR50 Appendix B used to the survey

  2. Operational inspections

    International Nuclear Information System (INIS)

    Bystersky, M.

    1997-01-01

    Special equipment is described, designed for inspection of reactor pressure vessels performed from the inside. Central shaft manipulator ZMM-5 is available for crack detection control using ultrasound and eddy currents, for visual check of surfaces, repair works at the reactor pressure vessel, and hardness measurements. The manipulator consists of the manipulator bridge, a cable container, shaft segments, a control mechanism and auxiliary parts. Eight inspections were performed at the Bohunice nuclear power plant and two at the Paks nuclear power plant. (M.D.)

  3. The construction of solid waste form test and inspection facility

    International Nuclear Information System (INIS)

    Park, Hun Hwee; Lee, Kang Moo; Jung, In Ha; Kim, Sung Hwan; Yoo, Jeong Woo; Lee, Jong Youl; Bae, Sang Min

    1988-01-01

    The solid waste form test and inspection facility is a facility to test and inspect the characteristics of waste forms, such as homogenity, mechanical structure, thermal behaviour, water resistance and leachability. Such kinds of characteristics in waste forms are required to meet a certain conditions for long-term storage or for final disposal of wastes. The facility will be used to evaluate safety for the disposal of wastes by test and inspection. At this moment, the efforts to search the most effective management of the radioactive wastes generated from power plants and radioisotope user are being executed by the people related to this field. Therefore, the facility becomes more significant tool because of its guidance of sucessfully converting wastes into forms to give a credit to the safety of waste disposal for managing the radioactive wastes. In addition the overall technical standards for inspecting of waste forms such as the standardized equipment and processes in the facility will be estabilished in the begining of 1990's when the project of waste management will be on the stream. Some of the items of the project have been standardized for the purpose of localization. In future, this facility will be utilized not only for the inspection of waste forms but also for the periodic decontamination apparatus by remote operation techniques. (Author)

  4. Improvement of remote control system of automatic ultrasonic equipment for inspection of reactor pressure vessel

    International Nuclear Information System (INIS)

    Cheong, Yong Moo; Jung, H. K.; Joo, Y. S.; Koo, K. M.; Hyung, H.; Sim, C. M.; Gong, U. S.; Kim, S. H.; Lee, J. P.; Rhoo, H. C.; Kim, M. S.; Ryoo, S. K.; Choi, C. H.; Oh, K. I.

    1999-12-01

    One of the important issues related to the nuclear safety is in-service inspection of reactor pressure vessel (RPV). A remote controlled automatic ultrasonic method is applied to the inspection. At present the automatic ultrasonic inspection system owned by KAERI is interrupted due to degradation of parts. In order to resume field inspection new remote control system for the equipment was designed and installed to the existing equipment. New ultrasonic sensors and their modules for RPV inspection were designed and fabricated in accordance with the new requirements of the inspection codes. Ultrasonic sensors were verified for the use in the RPV inspection. (author)

  5. Camber Angle Inspection for Vehicle Wheel Alignments.

    Science.gov (United States)

    Young, Jieh-Shian; Hsu, Hong-Yi; Chuang, Chih-Yuan

    2017-02-03

    This paper introduces an alternative approach to the camber angle measurement for vehicle wheel alignment. Instead of current commercial approaches that apply computation vision techniques, this study aims at realizing a micro-control-unit (MCU)-based camber inspection system with a 3-axis accelerometer. We analyze the precision of the inspection system for the axis misalignments of the accelerometer. The results show that the axes of the accelerometer can be aligned to the axes of the camber inspection system imperfectly. The calibrations that can amend these axis misalignments between the camber inspection system and the accelerometer are also originally proposed since misalignments will usually happen in fabrications of the inspection systems. During camber angle measurements, the x -axis or z -axis of the camber inspection system and the wheel need not be perfectly aligned in the proposed approach. We accomplished two typical authentic camber angle measurements. The results show that the proposed approach is applicable with a precision of ± 0.015 ∘ and therefore facilitates the camber measurement process without downgrading the precision by employing an appropriate 3-axis accelerometer. In addition, the measured results of camber angles can be transmitted via the medium such as RS232, Bluetooth, and Wi-Fi.

  6. Camber Angle Inspection for Vehicle Wheel Alignments

    Directory of Open Access Journals (Sweden)

    Jieh-Shian Young

    2017-02-01

    Full Text Available This paper introduces an alternative approach to the camber angle measurement for vehicle wheel alignment. Instead of current commercial approaches that apply computation vision techniques, this study aims at realizing a micro-control-unit (MCU-based camber inspection system with a 3-axis accelerometer. We analyze the precision of the inspection system for the axis misalignments of the accelerometer. The results show that the axes of the accelerometer can be aligned to the axes of the camber inspection system imperfectly. The calibrations that can amend these axis misalignments between the camber inspection system and the accelerometer are also originally proposed since misalignments will usually happen in fabrications of the inspection systems. During camber angle measurements, the x-axis or z-axis of the camber inspection system and the wheel need not be perfectly aligned in the proposed approach. We accomplished two typical authentic camber angle measurements. The results show that the proposed approach is applicable with a precision of ± 0.015 ∘ and therefore facilitates the camber measurement process without downgrading the precision by employing an appropriate 3-axis accelerometer. In addition, the measured results of camber angles can be transmitted via the medium such as RS232, Bluetooth, and Wi-Fi.

  7. Items to be reflected to the nuclear power safety measures in Japan (concerning the examination, design and operation management) (excluding the items to be reflected to the standards)

    Energy Technology Data Exchange (ETDEWEB)

    1980-10-01

    In connection with the Three Mile Island nuclear power accident in March, 1979, in the United States, in order to introduce the lessons from it in the nuclear power safety regulations in Japan, 52 items to be reflected to the nuclear power safety measures were chosen by the Nuclear Safety Commission. Of these, 16 items were examined by the Committee on Examination of Reactor Safety. It was decided that these results would be introduced in the nuclear safety regulations, by the Nuclear Safety Commission. The following 16 items are described. For the examination, four items concerning the automatic operation of safety systems and others; for the design, five items concerning a small rupture accident, the monitoring of the state of primary coolant, control room layout and others; for the operation management, seven items concerning the inspection at the time of repair, the prevention of faulty handlings by operators and others.

  8. Remote inspection of a buried pipeline using a mobile ultrasonic testing system

    Energy Technology Data Exchange (ETDEWEB)

    Muralidhar, S; Ghosh, J K [Bhabha Atomic Research Centre, Bombay (India). Radiometallurgy Div.; Rajendran, S; Ramakumar, M S [Bhabha Atomic Research Centre, Mumbai (India). Division of Remote Handling and Robotics

    1994-12-31

    The nuclear reactor, Cirus, has now been in operation for three decades. As part of a programme to ascertain the integrity and safety of the various reactor parts in-service inspection of the embedded portion of the main coolant pipeline will be carried out. A mobile ultrasonic testing system has been developed and tested in the laboratory to measure the wall thickness of an underground pipe from the inner corroded surface using a water-bubbler technique. 3 figs.

  9. Pipe inspection by intelligent pigs. What is possible today? What will the future be like?

    International Nuclear Information System (INIS)

    Schneider, Ulrich; Barbian, Alfred; Beller, Michael

    2010-01-01

    Pipeline operators seek to enhance the safety and availability of their pipe networks and reduce costs at the same time. Savings potentials must be found which do not detract from the safety of these systems. Even optimally planned, built and maintained pipes develop weak spots in their lifetime which affect their integrity and safety. Pipes near the end of their planned service life or damaged by external impacts constitute a risk. Operators formerly used to have mainly 2 options: - Wait for the damage to occur and then make targeted repairs at the risk of jeopardizing persons and the environment and of incalculable failures. - Conduct a costly total or partial refurbishment in time of a pipe as a safe alternative, which may reveal the pipe to be in almost pristine condition and the replacement to have been unnecessary. An ideal solution is a system allowing pipe condition to be examined fully and precisely in such a way that targeted maintenance, repair, and refurbishment minimizes costs without entailing a safety risk. Non-destructive inspection systems have been developed since 1965 mainly for inspections of oil and gas pipes; these inspections are carried out inside pipes. They have been further optimized continuously to this day and are used as standard procedures in many countries. The so-called 'intelligent pigs' are pumped through the pipes together with the fluid and use various techniques to measure, for instance, corrosion, cracks, and bulges, and store the data for the duration of the run. Subsequently, the data are evaluated by automatic programs and assessed further by experts in non-destructive testing (NDT). (orig.)

  10. Experience on inspection at PFPF

    International Nuclear Information System (INIS)

    Aoki, I.; Yamamoto, Y.; Takahashi, Saburo; Ooshima, Hirofumi; Kuniyasu, Kazufusa.

    1993-01-01

    In order to reduce a personal radiation exposure, Plutonium Fuel Production Facility (PFPF) introduced an automated MOX fabrication technology. Safeguards system for the PFPF was designed and installed so as to be compatible with automated process operation as much as possible. Introduction of these system in PFPF made possible to do the inspection measurements with unattended mode and Near Real Time Material Accountancy (NRTA), consequently inspection has been carrying out effectively and efficiently. This paper describes the new Inspection activities as a comparison with old Inspection activities based on our experience. (author)

  11. Examples from Member State Inspection Programmes: Canada. Appendix VII

    International Nuclear Information System (INIS)

    2014-01-01

    Section 26 of the Nuclear Safety and Control Act (NSCA) prohibits any person from preparing a site, constructing, operating, decommissioning or abandoning a nuclear facility without a licence granted by the Canadian Nuclear Safety Commission (CNSC) Tribunal. Subsection 24(4) of the NSCA states the following: 'No licence shall be issued, renewed, amended or replaced unless, in the opinion of the Commission, the applicant: (a) is qualified to carry on the activity that the licence will authorize the licensee to carry on; and (b) will, in carrying on that activity, make adequate provision for the protection of the environment, the health and safety of persons and the maintenance of national security and measures required to implement international obligations to which Canada has agreed.' Subsection 24(5) of the NSCA gives the CNSC Tribunal the authority to include in licences any term or condition that it considers necessary for the purposes of the NSCA. Section 30 of the NSCA authorizes CNSC staff to carry out inspections to verify licensee compliance with regulatory requirements, including any licence conditions. Licensees are expected to have a set of programmes and processes in place to adequately protect the environment, and the health and safety of workers and the public. The CNSC licensing system is administered in cooperation with federal, provincial and territorial government departments and agencies in such areas as health, environment, aboriginal consultation, transport and labour. Before the CNSC issues a licence, the concerns and responsibilities of these departments and agencies are taken into account in the licensing basis. Where necessary, agreements may be set up between the CNSC and those departments and agencies to determine roles and responsibilities for inspection activities where the licensee is concerned

  12. Safety aspects of a fuel reprocessing plant

    International Nuclear Information System (INIS)

    Donoghue, J.K.; Charlesworth, F.R.; Fairbairn, A.

    1977-01-01

    The establishment of the basic process must include the determination of the sensitivity of the process to operational errors or plant failures. The probability, and consequences of escapes of activity must be evaluated and emergency procedures set up to deal with accidents which might lead to such escapes. The administrative arrangements for safety should include a safety evaluation and advisory service independent of line management. A quality assurance strategy for the construction and commissioning stages is important. The design and construction of the plant must include: (i) Attention to plant reliability. Maintenance and inspection procedures to maintain reliability must be adopted and the design should include measures to facilitate in-service inspection of highly-active plant. (ii) Suitable and sufficient means of detection and prevention of malfunction, including criticality, bearing in mind both the timescale of development of the fault and its consequences. (iii) Measures for containment of activity. Penetrations from active into operating areas should be eliminated or minimised and maintenance should be separated from operational areas. Secondary containment beyond that provided for operations of a significant magnitude. A ventilation system with appropriate gas clean-up, monitoring and discharge facilities is required. (iv) Adequate shielding, with particular attention paid to multiple activities in a single operational area which might lead to an operator being exposed to radiation from operations which are beyond his control. (v) Means of accounting for active materials and for their recovery, transfer and disposal in the event of a forced shut down. (vi) Suitable methods for segregation and control of wastes within the plant and for their discharge. Solid or liquid wastes should be subject to delay and monitoring procedures before release. Facilities for storage of waste must be subject to the same safety principles as the plant itself. (vii) Final

  13. Preliminary conceptual design of inspection and maintenance for KALIMER reactor system

    Energy Technology Data Exchange (ETDEWEB)

    Joo, Young Sang; Kim, Seok Hun; Yoo, Bong

    2000-08-01

    In-service inspection and maintenance are very important for improving the safety and availability of nuclear power plants. The conceptual requirements of in-service inspection and maintenance should be reflected in the earlier design process for the verification of the plant operability and reliability. In this report the fundamental approaches of the inspection and maintenance for KALIMER are established to ensure the structural integrity and operability for KALIMER. The general strategy and methodology of maintenance and inspection for the reactor system and components are proposed and described for satisfying the intents of the section XI, division 3, of ASME code and considering the design characteristics of KALIMER.

  14. An analysis of OSHA inspections assessing contaminant exposures in general medical and surgical hospitals.

    Science.gov (United States)

    Knight, Jordan L; Sleeth, Darrah K; Larson, Rodney R; Pahler, Leon F

    2013-04-01

    This study analyzed data from the Occupational Safety and Health Administration's (OSHA) Chemical Exposure Health Database to assess contaminant exposures in general medical and surgical hospitals. Seventy-five inspections conducted in these hospitals from 2005 through 2009 were identified. Five categories of inspections were conducted, the three most common being complaint-based, planned, and referral-based inspections. Complaint-based inspections comprised the majority of inspections-55 (73%) of the 75 conducted. The overall violation rate for all inspection types was 68%. This finding was compared to the violation rates of planned inspections (100%), referral-based inspections (83%), and complaint-based inspections (62%). Asbestos was the hazardous substance most commonly sampled and cited by OSHA in hospitals, with 127 samples collected during 24 inspections; 31% of the total 75 inspections resulting in one or more violations were due to asbestos. Copyright 2013, SLACK Incorporated.

  15. Recurrent inspection of tubes

    International Nuclear Information System (INIS)

    Andersson, S.

    1984-01-01

    Recommendations concerning the selection of areas for the inspection of tubes have been outlined. The aim is to focus the control on the regions which are important for the safety and where damage is supposed to take place. The number of zones will depend on the risk factors as judged by experts. The localizing will be based upon probable damaging mechanisms. A certain number of areas should be chosen at random. (G.B.)

  16. State health agency workforce shortages and implications for public health: a case study of restaurant inspections in Louisiana.

    Science.gov (United States)

    Realmuto, Lindsey; Hunting, Katherine L; Parkin, Rebecca

    2013-12-01

    The study described in this article evaluated the effects of public health workforce cuts on routine food safety inspections and the occurrence of critical violations. Routine inspection information was collected from two Louisiana databases for permanent food establishments categorized as risk category 3 or 4 in East Baton Rouge Parish, Louisiana, for the years 2005, 2007, and 2009. The length of time between routine inspections nearly quadrupled from 2005 to 2009. For risk category 4 establishments, a significant increase occurred in the proportion of inspections that resulted in a critical violation between the three years. The amount of time between routine inspections was significantly higher for inspections that resulted in a critical violation versus those that did not. Lastly, the amount of time between routine inspections, an establishment's risk category, and history of complaint were found to have significant predictive effects on the incidence of a critical violation during a routine inspection, although results varied by year. Study results indicate that decreased workforce capacity in Louisiana may negatively affect the outcomes of routine food safety inspections.

  17. Inspection of Nuclear Power Plant Containment Structures

    Energy Technology Data Exchange (ETDEWEB)

    Graves, H.L.; Naus, D.J.; Norris, W.E.

    1998-12-01

    Safety-related nuclear power plant (NPP) structures are designed to withstand loadings from a number of low-probability external and interval events, such as earthquakes, tornadoes, and loss-of-coolant accidents. Loadings incurred during normal plant operation therefore generally are not significant enough to cause appreciable degradation. However, these structures are susceptible to aging by various processes depending on the operating environment and service conditions. The effects of these processes may accumulate within these structures over time to cause failure under design conditions, or lead to costly repair. In the late 1980s and early 1990s several occurrences of degradation of NPP structures were discovered at various facilities (e.g., corrosion of pressure boundary components, freeze- thaw damage of concrete, and larger than anticipated loss of prestressing force). Despite these degradation occurrences and a trend for an increasing rate of occurrence, in-service inspection of the safety-related structures continued to be performed in a somewhat cursory manner. Starting in 1991, the U.S. Nuclear Regulatory Commission (USNRC) published the first of several new requirements to help ensure that adequate in-service inspection of these structures is performed. Current regulatory in-service inspection requirements are reviewed and a summary of degradation experience presented. Nondestructive examination techniques commonly used to inspect the NPP steel and concrete structures to identify and quantify the amount of damage present are reviewed. Finally, areas where nondestructive evaluation techniques require development (i.e., inaccessible portions of the containment pressure boundary, and thick heavily reinforced concrete sections are discussed.

  18. A plan for safety and integrity of research reactor components

    International Nuclear Information System (INIS)

    Moatty, Mona S. Abdel; Khattab, M.S.

    2013-01-01

    Highlights: ► A plan for in-service inspection of research reactor components is put. ► Section XI of the ASME Code requirements is applied. ► Components subjected to inspection and their classes are defined. ► Flaw evaluation and its acceptance–rejection criteria are reviewed. ► A plan of repair or replacement is prepared. -- Abstract: Safety and integrity of a research reactor that has been operated over 40 years requires frequent and thorough inspection of all the safety-related components of the facility. The need of increasing the safety is the need of improving the reliability of its systems. Diligent and extensive planning of in-service inspection (ISI) of all reactor components has been imposed for satisfying the most stringent safety requirements. The Safeguards Officer's responsibilities of Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code ASME Code have been applied. These represent the most extensive and time-consuming part of ISI program, and identify the components subjected to inspection and testing, methods of component classification, inspection and testing techniques, acceptance/rejection criteria, and the responsibilities. The paper focuses on ISI planning requirements for welded systems such as vessels, piping, valve bodies, pump casings, and control rod-housing parts. The weld in integral attachments for piping, pumps, and valves are considered too. These are taken in consideration of safety class (1, 2, 3, etc.), reactor age, and weld type. The parts involve in the frequency of inspection, the examination requirements for each inspection, the examination method are included. Moreover the flaw evaluation, the plan of repair or replacement, and the qualification of nondestructive examination personnel are considered

  19. Travelling type monitoring and inspection device

    International Nuclear Information System (INIS)

    Ito, Takao; Maruki, Hideaki.

    1994-01-01

    The present invention sufficiently ensures video output images even if lenses of a television camera of a monitoring means are degraded to reduce the quantity of transmission light. That is, a light amount control mechanism capable of controlling the quantity of illumination light irradiated from an illumination device at an output level of a sensor of an inspection device main body. A test chart for measuring a luminance which is an output level of the sensor is disposed. During plant operation, the lenses of the television camera undergo influences of radioactivity and are degraded to reduce the quantity of transmission light on every periodical monitoring and inspection using a travelling type monitoring inspection device. In this case, the test chart disposed near the equipment to be monitored and inspected is caught by the television camera to measure a sensor output luminance. Then, the light amount control mechanism of the illumination device is controlled so as to provide a luminance which has been set at an initial stage of the plant inspection. With such procedures, video data of the objective equipment to be monitored and inspected can be obtained at a constant luminance during inspection. (I.S.)

  20. Study of a risk-based piping inspection guideline system.

    Science.gov (United States)

    Tien, Shiaw-Wen; Hwang, Wen-Tsung; Tsai, Chih-Hung

    2007-02-01

    A risk-based inspection system and a piping inspection guideline model were developed in this study. The research procedure consists of two parts--the building of a risk-based inspection model for piping and the construction of a risk-based piping inspection guideline model. Field visits at the plant were conducted to develop the risk-based inspection and strategic analysis system. A knowledge-based model had been built in accordance with international standards and local government regulations, and the rational unified process was applied for reducing the discrepancy in the development of the models. The models had been designed to analyze damage factors, damage models, and potential damage positions of piping in the petrochemical plants. The purpose of this study was to provide inspection-related personnel with the optimal planning tools for piping inspections, hence, to enable effective predictions of potential piping risks and to enhance the better degree of safety in plant operations that the petrochemical industries can be expected to achieve. A risk analysis was conducted on the piping system of a petrochemical plant. The outcome indicated that most of the risks resulted from a small number of pipelines.

  1. Computer-aided ultrasonic inspection of steam turbine rotors

    Energy Technology Data Exchange (ETDEWEB)

    Mayer, K H; Weber, M; Weiss, M [GEC ALSTHOM Energie GmbH, Nuremberg (Germany)

    1999-12-31

    As the output and economic value of power plants increase, the detection and sizing of the type of flaws liable to occur in the rotors of turbines using ultrasonic methods assumes increasing importance. An ultrasonic inspection carried out at considerable expense is expected to bring to light all safety-relevant flaws and to enable their size to be determined so as to permit a fracture-mechanics analysis to assess the reliability of the rotor under all possible stresses arising in operation with a high degree of accuracy. The advanced computer-aided ultrasonic inspection of steam turbine rotors have improved reliability, accuracy and reproducibility of ultrasonic inspection. Further, there has been an improvement in the resolution of resolvable group indications by applying reconstruction and imagine methods. In general, it is also true for the advanced computer-aided ultrasonic inspection methods that, in the case of flaw-affected forgings, automated data acquisition provides a substantial rationalization and a significant documentation of the results for the fracture mechanics assessment compared to manual inspection. (orig.) 8 refs.

  2. Computer-aided ultrasonic inspection of steam turbine rotors

    Energy Technology Data Exchange (ETDEWEB)

    Mayer, K.H.; Weber, M.; Weiss, M. [GEC ALSTHOM Energie GmbH, Nuremberg (Germany)

    1998-12-31

    As the output and economic value of power plants increase, the detection and sizing of the type of flaws liable to occur in the rotors of turbines using ultrasonic methods assumes increasing importance. An ultrasonic inspection carried out at considerable expense is expected to bring to light all safety-relevant flaws and to enable their size to be determined so as to permit a fracture-mechanics analysis to assess the reliability of the rotor under all possible stresses arising in operation with a high degree of accuracy. The advanced computer-aided ultrasonic inspection of steam turbine rotors have improved reliability, accuracy and reproducibility of ultrasonic inspection. Further, there has been an improvement in the resolution of resolvable group indications by applying reconstruction and imagine methods. In general, it is also true for the advanced computer-aided ultrasonic inspection methods that, in the case of flaw-affected forgings, automated data acquisition provides a substantial rationalization and a significant documentation of the results for the fracture mechanics assessment compared to manual inspection. (orig.) 8 refs.

  3. Chapter No.3. Assessment and inspection of nuclear installations

    International Nuclear Information System (INIS)

    2002-01-01

    2001. The total number of operational events shows decreasing tendency. According to the INES scale, 19 events have been assessed by level '0' and 1 event by level 'out of scale'. Based on the result of the inspection a permit for further operation of the unit was issued. On the basis of complex assessment, UJD consider the operation of Bohunice V-1 NPP in 2001 safe and reliable. Bohunice V-2 Nuclear Power Plant consists of two units with WWER 440 type reactors of improved V-213 type, which were put into operation in 1984 and 1985. Both units operated in 2001 according to the needs of the energy dispatch centre in based load, or also in the regime of 'tertiary regulation' and 'primary regulation' respectively. From both unit of Bohunice V-2 NPP also the non-electric production heat was used by steam bleeding from the turbine which served as a heat source for heating Trnava, Hlohovec and Leopoldov towns. In 2001 the planned refuelling outage was performed at both units. The ongoing review and assessment of the document 'Concept of modernisation and safety improvement of Bohunice V-2 NPP', submitted by the operator based on UJD decision was a significant activity of UJD in connection with safety assessment of Bohunice V-2 NPP in 2001. Consequently the top management of the Slovak Republic power utility SE, a.s. definitely approved the modernisation programme for Bohunice V-2 NPP. In 2001 a refuelling outages on units 3 and 4 of Bohunice V-2 NPP were performed. UJD reviewed the programmes of in-service inspection for refuelling outages on units 3 and 4 and conducted the current inspections aimed at the fulfilment of these programmes and assessment of the results obtained. During the in-service inspections no significant indication were found which would require an extraordinary measures. State of the plant equipment was assessed as a good one and not limiting further operation of the both units of Bohunice V-2 NPP. In 2001 the programme of systematic improvement of

  4. Quality assurance inspections in the transportation packaging supplier industry

    International Nuclear Information System (INIS)

    Jankovich, J.P.

    1991-01-01

    In this paper the quality assurance inspections of the transportation packaging supplier industry, conducted by the U.S. Nuclear Regulatory Commission (NRC) on a routine basis since 1989 are discussed. The term supplier is used to include designers, fabricators, and distributors that hold NRC approved Quality Assurance Programs and Certificates of Compliance for packagings to transport radioactive materials. The objective of the inspections is to provide assurance that transportation packagings are fabricated and procured in accordance with 10 CFR Parts 21 and 71 requirements. The inspections are conducted in a systematic and comprehensive manner, utilizing uniform inspection techniques in order to assure uniformity and comparability. During the April 1989 and May 1991 period approximately 21 inspections were conducted by the Transportation Branch, Office of Nuclear Material Safety and Safeguards of the NRC. The majority of the findings were identified in the areas of quality assurance procedures, control of special processes (e.g. welding, radiography), and maintenance of QA records

  5. 7 CFR 1730.21 - Inspections and tests.

    Science.gov (United States)

    2010-01-01

    ... reliability and security of the electric power grid, cause significant risk to the safety and health of the... AGRICULTURE ELECTRIC SYSTEM OPERATIONS AND MAINTENANCE Operations and Maintenance Requirements § 1730.21... parts of its electric system, annually exercise its ERP, and maintain records of such inspections and...

  6. MNR's role in public safety around dams

    Energy Technology Data Exchange (ETDEWEB)

    Keyes, Jennifer [Ministry of Natural Resources, Peterborough, ON (Canada)

    2011-07-01

    The Ministry of Natural Resources (MNR) is the largest dam owner in Ontario with around 400 dams located all across the province. MNR works to exercise stewardship of Ontario's water resources in a context of public safety, employee safety and environmental awarenes. This presentation shows the different measures MNR implemented to reduce risks. Warning signs, safety booms, barrel buoys and pedestrian fencing have been installed around dams to alert the public to possible dangers. In addition, MNR employees receive training in how to inspect dams for safety concerns, how to identify problems which could result in hazards to the public and how to work safely.

  7. An overview of in-service inspection for nuclear power plants in Japan

    International Nuclear Information System (INIS)

    Takano, Eishiro

    1996-01-01

    In nuclear power stations, for maintaining the safety of machinery and equipment, it is stipulated to carry out periodic inspection. The contents of the periodic inspection and the inspections of important matters are explained. In-service inspection (ISI) is the nondestructive inspection for confirming the soundness of reactor pressure vessels, main pipings, valves and others. The stipulations on the scope and time of the periodic inspection and ISI, the course of introducing ISI into Japan, and the basic way of thinking on ISI are described. Pre-service inspection (PSI) is carried out for the purpose of collecting and recording the initial data for ISI. The range of the objects of nondestructive inspection and leak test and the range of the objects of leak test only are shown. As to nondestructive inspection, the parts to be inspected, the frequency of inspection and the methods of inspection, and the method of leak test are described. As the present state of inspection technology, the automatic ultrasonic flow detectors for reactor vessels, piping welded parts and reactor vessel stud bolts, and the eddy current flaw detector for steam generator tubes are explained. (K.I.)

  8. Estimated incident cost savings in shipping due to inspections.

    Science.gov (United States)

    Knapp, Sabine; Bijwaard, Govert; Heij, Christiaan

    2011-07-01

    The effectiveness of safety inspections of ships has been analysed from various angles, but until now, relatively little attention has been given to translate risk reduction into incident cost savings. This paper provides a monetary quantification of the cost savings that can be attributed to port state control inspections and industry vetting inspections. The dataset consists of more than half a million ship arrivals between 2002 and 2007 and contains inspections of port state authorities in the USA and Australia and of three industry vetting regimes. The effect of inspections in reducing the risk of total loss accidents is estimated by means of duration models, in terms of the gained probability of survival. The monetary benefit of port state control inspections is estimated to range, on average, from about 70 to 190 thousand dollars, with median values ranging from about 20 to 45 thousand dollars. Industry inspections have even higher benefits, especially for tankers. The savings are in general higher for older and larger vessels, and also for vessels with undefined flag and unknown classification society. As inspection costs are relatively low in comparison to potential cost savings, the results underline the importance of determining ships with relatively high risk of total loss. Copyright © 2011 Elsevier Ltd. All rights reserved.

  9. 9 CFR 381.204 - Marking of poultry products offered for entry; official import inspection marks and devices.

    Science.gov (United States)

    2010-01-01

    ... Products FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE AGENCY ORGANIZATION AND TERMINOLOGY; MANDATORY MEAT AND POULTRY PRODUCTS INSPECTION AND VOLUNTARY INSPECTION AND CERTIFICATION POULTRY PRODUCTS... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Marking of poultry products offered...

  10. Nuclear fuel shipping inspection device

    International Nuclear Information System (INIS)

    Takahashi, Toshio; Hada, Koji.

    1988-01-01

    Purpose: To provide an nuclear fuel shipping inspection device having a high detection sensitivity and capable of obtaining highly reliable inspection results. Constitution: The present invention concerns a device for distinguishing a fuel assembly having failed fuel rods in LMFBR type reactors. Coolants in a fuel assembly to be inspected are collected by a sampling pipeway and transferred to a filter device. In the filter device, granular radioactive corrosion products (CP) in the coolants are captured, to reduce the background. The coolants, after being passed through the filter device, are transferred to an FP catching device and gamma-rays of iodine and cesium nuclides are measured in FP radiation measuring device. Subsequently, the coolants transferred to a degasing device to separate rare gas FP in the coolants from the liquid phase. In a case if rare gas fission products are detected by the radiation detector, it means that there is a failed fuel rod in the fuel assembly to be inspected. Since the CP and the soluble FP are separated and extracted for the radioactivity measurement, the reliability can be improved. (Kamimura, M.)

  11. Fuel assembly inspection device

    International Nuclear Information System (INIS)

    Yaginuma, Yoshitaka

    1998-01-01

    The present invention provides a device suitable to inspect appearance of fuel assemblies by photographing the appearance of fuel assemblies. Namely, the inspection device of the present invention measures bowing of fuel assembly or each of fuel rods or both of them based on the partially photographed images of fuel assembly. In this case, there is disposed a means which flashily projects images in the form of horizontal line from a direction intersecting obliquely relative to a horizontal cross section of the fuel assembly. A first image processing means separates the projected image pictures including projected images and calculates bowing. A second image processing means replaces the projected image pictures of the projected images based on projected images just before and after the photographing. Then, images for the measurement of bowing and images for inspection can be obtained simultaneously. As a result, the time required for the photographing can be shortened, the time for inspection can be shortened and an effect of preventing deterioration of photographing means by radiation rays can be provided. (I.S.)

  12. Some considerations on the safety of nuclear ships

    International Nuclear Information System (INIS)

    Kuramoto, Masaaki

    1978-01-01

    For realizing the practical utilization of nuclear merchant ships, it is essential to gain their acceptance by maritime countries on an equal footing with conventional vessels, and to have the administrative procedures for their admission simplified. This, however cannot be expected to be attained overnight, and progressive measures will have to be adopted, to approach the ultimate goal step by step. The first step should be to demonstrate the safety of nuclear propulsion, for which nuclear ships must accumulate their mileages of safe service. The second important step is to simplify the procedures demanded of nuclear ships for access to ports, through the establishment of international safety standards and design criteria, the enforcement of safety measures covering the entrance of nuclear ships into ports, and the assurance of safety in he repair, inspection and refuelling operations of these ships. Among these measures, the considerations relevant to port entry are the subject of vital interest to both ship operators and port authorities

  13. Methodology for the inspection of items important to safety

    International Nuclear Information System (INIS)

    Ishack, G.

    1981-11-01

    A description is given of the inspection methods adopted by the Canadian Atomic Energy Control Board. From the outset of the industry in Canada, resident officers have been assigned to nuclear power stations. These inspectors have unlimited access to equipment, documents and personnel at the station. They work closely with Head Office specialists, provincial authorities, and private consultants

  14. Improvement of remote control system of automatic ultrasonic equipment for inspection of reactor pressure vessel

    Energy Technology Data Exchange (ETDEWEB)

    Cheong, Yong Moo; Jung, H. K.; Joo, Y. S.; Koo, K. M.; Hyung, H.; Sim, C. M.; Gong, U. S.; Kim, S. H.; Lee, J. P.; Rhoo, H. C.; Kim, M. S.; Ryoo, S. K.; Choi, C. H.; Oh, K. I

    1999-12-01

    One of the important issues related to the nuclear safety is in-service inspection of reactor pressure vessel (RPV). A remote controlled automatic ultrasonic method is applied to the inspection. At present the automatic ultrasonic inspection system owned by KAERI is interrupted due to degradation of parts. In order to resume field inspection new remote control system for the equipment was designed and installed to the existing equipment. New ultrasonic sensors and their modules for RPV inspection were designed and fabricated in accordance with the new requirements of the inspection codes. Ultrasonic sensors were verified for the use in the RPV inspection. (autho0008.

  15. application of christer's inspection model for building maintenance

    African Journals Online (AJOL)

    system. Information was collected by means of forms and 100 were completed for trades including painter, plumber ... the threat poorly maintained buildings pose to public safety [2]. 2. ..... by operating an inspection system as,. ∫ ∞ h=T. ∫ h.

  16. Reliability-Based Inspection Planning for Structural Systems

    DEFF Research Database (Denmark)

    Sørensen, John Dalsgaard

    1993-01-01

    A general model for reliability-based optimal inspection and repair strategies for structural systems is described. The total expected costs in the design lifetime is minimized with the number of inspections, the inspection times and efforts as decision variables. The equivalence of this model...... with a preposterior analysis from statistical decision theory is discussed. It is described how information obtained by an inspection can be used in a repair decision. Stochastic models for inspection, measurement and repair actions are presented. The general model is applied for inspection and repair planning...

  17. Outlines of guidelines for the inspection and evaluation of reactor vessel internals

    International Nuclear Information System (INIS)

    Seki, Hiroaki; Kobayashi, Hiroyuki; Nakano, Morihito; Murai, Soutarou; Nomoto, Toshiharu

    2014-01-01

    'The guideline committee for the inspection and evaluation of Reactor Vessel Internals' of JANSI (Japan Nuclear Safety Institute) has been developing many guidelines based on principle which the conservative methodology, and covered both individual inspection method of reactor internals and application of repair methods for reactor internals. In this paper, some aspects of the JANSI-VIP-03 (Guidelines for the inspection and evaluation of Reactor Vessel Internals, revised Dec.2013) which is summary document of the committee activity, are introduced. (author)

  18. PWR fuel inspection and repair technology development in the Republic of Korea

    International Nuclear Information System (INIS)

    Park, J.Y.

    1998-01-01

    As of September 1997, 10 PWRs and 2 PHWRs generate 10,320MW electricity in Korea. And another 8 PWRs and 2 PHWRs will be constructed by 2006. These will need about 400 MTU of PWR fuels and 400 MTU of PHWR fuels. To improve average burnup, thermal power, fuel usability and plant safety, better poolside fuel service technologies are strongly recommended as well as the fuel design and fabrication technology improvements. During the last twenty years of nuclear power plant operation in Korea, more than 4,000 fuel assemblies has been used. At the site, continuous coolant activity measurement, pool-side visual inspection and ultrasonic tests have been performed. Some of the fuels are damaged or failed for various reasons. Some of the defected fuels were examined in hot cell to investigate the cause of failure. Even though 30 PWR fuel assemblies were repaired by foreign engineers, fuel inspection and repair technologies are not established yet. Various kind of design for the fuel make the inspection, repair and reconstitution equipment more complex. As a result, recently, a plant to obtain overall technology for poolside fuel inspection, failed fuel repair and reconstitution through R and D activities are set forth. (author)

  19. Items to be reflected to the nuclear power safety measures in Japan (concerning the examination, design and operation management) (excluding the items to be reflected to the standards)

    International Nuclear Information System (INIS)

    1980-01-01

    In connection with the Three Mile Island nuclear power accident in March, 1979, in the United States, in order to introduce the lessons from it in the nuclear power safety regulations in Japan, 52 items to be reflected to the nuclear power safety measures were chosen by the Nuclear Safety Commission. Of these, 16 items were examined by the Committee on Examination of Reactor Safety. It was decided that these results would be introduced in the nuclear safety regulations, by the Nuclear Safety Commission. The following 16 items are described. For the examination, four items concerning the automatic operation of safety systems and others; for the design, five items concerning a small rupture accident, the monitoring of the state of primary coolant, control room layout and others; for the operation management, seven items concerning the inspection at the time of repair, the prevention of faulty handlings by operators and others. (J.P.N.)

  20. Do school inspections improve primary school performance?

    OpenAIRE

    Dinand Webbink; Rob Luginbuhl; I. de Wolf

    2007-01-01

    Inspectors from the Dutch Inspectorate of Education inspect primary schools, write inspection reports on each inspected school, and make recommendations as to how each school can improve. We test whether these inspections result in better school performance. Using a fixed-effects model, we find evidence that school inspections do lead to measurably better school performance. Our assessment of school performance is based on the Cito test scores of pupils in their final year of primary school. ...

  1. Evaluation of piping reliability and failure data for use in risk-based inspections of nuclear power plants

    International Nuclear Information System (INIS)

    Vasconcelos, V. de; Soares, W.A.; Costa, A.C.L. da; Rabello, E.G.; Marques, R.O.

    2016-01-01

    During operation of industrial facilities, components and systems can deteriorate over time, thus increasing the possibility of accidents. Risk-Based Inspection (RBI) involves inspection planning based on information about risks, through assessing of probability and consequence of failures. In-service inspections are used in nuclear power plants, in order to ensure reliable and safe operation. Traditional deterministic inspection approaches investigate generic degradation mechanisms on all systems. However, operating experience indicates that degradation occurs where there are favorable conditions for developing a specific mechanism. Inspections should be prioritized at these places. Risk-Informed In-service Inspections (RI-ISI) are types of RBI that use Probabilistic Safety Assessment results, increasing reliability and plant safety, and reducing radiation exposure. These assessments use both available generic reliability and failure data, as well as plant specific information. This paper proposes a method for evaluating piping reliability and failure data important for RI-ISI programs, as well as the techniques involved. (author)

  2. Evaluation of piping reliability and failure data for use in risk-based inspections of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Vasconcelos, V. de; Soares, W.A.; Costa, A.C.L. da; Rabello, E.G.; Marques, R.O., E-mail: vasconv@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2016-07-01

    During operation of industrial facilities, components and systems can deteriorate over time, thus increasing the possibility of accidents. Risk-Based Inspection (RBI) involves inspection planning based on information about risks, through assessing of probability and consequence of failures. In-service inspections are used in nuclear power plants, in order to ensure reliable and safe operation. Traditional deterministic inspection approaches investigate generic degradation mechanisms on all systems. However, operating experience indicates that degradation occurs where there are favorable conditions for developing a specific mechanism. Inspections should be prioritized at these places. Risk-Informed In-service Inspections (RI-ISI) are types of RBI that use Probabilistic Safety Assessment results, increasing reliability and plant safety, and reducing radiation exposure. These assessments use both available generic reliability and failure data, as well as plant specific information. This paper proposes a method for evaluating piping reliability and failure data important for RI-ISI programs, as well as the techniques involved. (author)

  3. 29 CFR 1960.26 - Conduct of inspections.

    Science.gov (United States)

    2010-07-01

    ... information which pertains to the occupational safety and health of the workplace to be inspected, including..., installation, facility, construction site, or other area, workplace, or environment where work is performed by... times, and within reasonable limits and in a reasonable manner, any such place of employment and all...

  4. Periodic safety analyses; Les essais periodiques

    Energy Technology Data Exchange (ETDEWEB)

    Gouffon, A; Zermizoglou, R

    1990-12-01

    The IAEA Safety Guide 50-SG-S8 devoted to 'Safety Aspects of Foundations of Nuclear Power Plants' indicates that operator of a NPP should establish a program for inspection of safe operation during construction, start-up and service life of the plant for obtaining data needed for estimating the life time of structures and components. At the same time the program should ensure that the safety margins are appropriate. Periodic safety analysis are an important part of the safety inspection program. Periodic safety reports is a method for testing the whole system or a part of the safety system following the precise criteria. Periodic safety analyses are not meant for qualification of the plant components. Separate analyses are devoted to: start-up, qualification of components and materials, and aging. All these analyses are described in this presentation. The last chapter describes the experience obtained for PWR-900 and PWR-1300 units from 1986-1989.

  5. The structural integrity safety case for Sizewell B power station

    International Nuclear Information System (INIS)

    Gerachty, J.E.

    1993-01-01

    This paper presents the safety case approach adopted for the components of the Sizewell 'B' Power Station for which a high degree of structural integrity is required. Such components include the Reactor Pressure Vessel, Steam Generator and Pressuriser for which Incredibility of Failure is claimed. The two parts of the case involve achievement and demonstration of integrity. This is achieved by extensive measures involving design, manufacture, materials and inspection. The demonstration has required a fracture mechanics approach. The specific role of inspection validation and its relation to critical defect size is described. (author)

  6. A study on improvements of inspection efficiency with remote transmission of inspection data

    International Nuclear Information System (INIS)

    Kikuchi, Masahiro

    2010-01-01

    Current information networks technology brought secure and convenient condition of information transmission, so that inspectorates intend to apply such technology to optimize current inspection efforts. IAEA established the Remote Monitoring Project (RMP) in 1996 and started to draft safeguards concepts, and approaches to refer the implementation of remote monitoring technology and to compromise with relationship between current inspection activities and the remote monitoring technologies. Although communications costs and conditions of secured communication should be further investigated, the technologies would have a possibility to reduce current inspection efforts. We would face at the step to study on the several issues such as what measures could be candidate to use, how much cost we needs, what kind of technical risks would be concerned, further improvements could be achieved by comparison with current inspection costs and effectiveness. This paper reports on the expectation points and relevant technical attention points which are related to apply unattended inspection system with remote data transmission to the flows and inventory verification of item and bulk facility, respectively, in order to improve inspection efforts. (author)

  7. Remotely deployable aerial inspection using tactile sensors

    Science.gov (United States)

    MacLeod, C. N.; Cao, J.; Pierce, S. G.; Sullivan, J. C.; Pipe, A. G.; Dobie, G.; Summan, R.

    2014-02-01

    For structural monitoring applications, the use of remotely deployable Non-Destructive Evaluation (NDE) inspection platforms offer many advantages, including improved accessibility, greater safety and reduced cost, when compared to traditional manual inspection techniques. The use of such platforms, previously reported by researchers at the University Strathclyde facilitates the potential for rapid scanning of large areas and volumes in hazardous locations. A common problem for both manual and remote deployment approaches lies in the intrinsic stand-off and surface coupling issues of typical NDE probes. The associated complications of these requirements are obviously significantly exacerbated when considering aerial based remote inspection and deployment, resulting in simple visual techniques being the preferred sensor payload. Researchers at Bristol Robotics Laboratory have developed biomimetic tactile sensors modelled on the facial whiskers (vibrissae) of animals such as rats and mice, with the latest sensors actively sweeping their tips across the surface in a back and forth motion. The current work reports on the design and performance of an aerial inspection platform and the suitability of tactile whisking sensors to aerial based surface monitoring applications.

  8. Nuclear data needs for non-intrusive inspection

    International Nuclear Information System (INIS)

    Smith, D. L.; Michlich, B. J.

    2000-01-01

    Various nuclear-based techniques are being explored for use in non-intrusive inspection. Their development is motivated by the need to prevent the proliferation of nuclear weapons, to thwart trafficking in illicit narcotics, to stop the transport of explosives by terrorist organizations, to characterize nuclear waste, and to deal with various other societal concerns. Non-intrusive methods are sought in order to optimize inspection speed, to minimize damage to packages and containers, to satisfy environmental, health and safety requirements, to adhere to legal requirements, and to avoid inconveniencing the innocent. These inspection techniques can be grouped into two major categories: active and passive. They almost always require the use of highly penetrating radiation and therefore are generally limited to neutrons and gamma rays. Although x-rays are widely employed for these purposes, their use does not constitute nuclear technology and therefore is not discussed here. This paper examines briefly the basic concepts associated with nuclear inspection and investigates the related nuclear data needs. These needs are illustrated by considering four of the methods currently being developed and tested

  9. Nuclear data needs for non-intrusive inspection

    International Nuclear Information System (INIS)

    Smith, D.L.; Micklich, B.J.

    2001-01-01

    Various nuclear-based techniques are being explored for use in non-intrusive inspection. Their development is motivated by the need to prevent the proliferation of nuclear weapons, to thwart trafficking in illicit narcotics, to stop the transport of explosives by terrorist organizations, to characterize nuclear waste, and to deal with various other societal concerns. Non-intrusive methods are sought in order to optimize inspection speed, to minimize damage to packages and containers, to satisfy environmental, health and safety requirements, to adhere to legal requirements, and to avoid inconveniencing the innocent. These inspection techniques can be grouped into two major categories: active and passive. They almost always require the use of highly penetrating radiation and therefore are generally limited to neutrons and gamma rays. Although x-rays are widely employed for these purposes, their use does not constitute 'nuclear technology' and therefore is not discussed here. This paper examines briefly the basic concepts associated with nuclear inspection and investigates the related nuclear data needs. These needs are illustrated by considering four of the methods currently being developed and tested. (author)

  10. 76 FR 24713 - Cooperative Inspection Programs: Interstate Shipment of Meat and Poultry Products

    Science.gov (United States)

    2011-05-02

    ... amenable species, such as processing game meat or for busy times in their retail shops around holidays. The... Service 9 CFR Parts 321, 332, and 381 Cooperative Inspection Programs: Interstate Shipment of Meat and... Shipment of Meat and Poultry Products AGENCY: Food Safety and Inspection Service, USDA. ACTION: Final rule...

  11. Regulatory inspection activities on nuclear power plant sites during construction in the United Kingdom

    International Nuclear Information System (INIS)

    Jeffery, J.V.

    1977-01-01

    The work of regulatory inspection of the construction of the plant on the site is performed not only by the inspector who has been allocated to inspection duties for that site but also by the specialist staff who are involved with the safety assessment of the plant. The co-ordination of this work is described in the paper and examples are given of inspection activities associated with the enforcement requirements of licence conditions as well as those related to the inspection of the plant itself. (author)

  12. Piping inspection round robin

    International Nuclear Information System (INIS)

    Heasler, P.G.; Doctor, S.R.

    1996-04-01

    The piping inspection round robin was conducted in 1981 at the Pacific Northwest National Laboratory (PNNL) to quantify the capability of ultrasonics for inservice inspection and to address some aspects of reliability for this type of nondestructive evaluation (NDE). The round robin measured the crack detection capabilities of seven field inspection teams who employed procedures that met or exceeded the 1977 edition through the 1978 addenda of the American Society of Mechanical Engineers (ASME) Section 11 Code requirements. Three different types of materials were employed in the study (cast stainless steel, clad ferritic, and wrought stainless steel), and two different types of flaws were implanted into the specimens (intergranular stress corrosion cracks (IGSCCs) and thermal fatigue cracks (TFCs)). When considering near-side inspection, far-side inspection, and false call rate, the overall performance was found to be best in clad ferritic, less effective in wrought stainless steel and the worst in cast stainless steel. Depth sizing performance showed little correlation with the true crack depths

  13. Poolside fuel assembly inspection campaigns performed at Kernkraftwerk Leibstadt during summer 1997

    International Nuclear Information System (INIS)

    Zwicky, H.U.; Wiktor, C.G.; Schrire, D.

    1998-01-01

    In order to minimise fuel cycle costs, fuel assembly discharge burnup and average U-235 enrichment were increasing over past years in the Kernkraftwerk Leibstadt (KKL) plant. In parallel, high burnup verification programs were defined in collaboration with fuel suppliers. The aim of these programs is to demonstrate safe and reliable fuel performance up to the designed burnup limit and to identify any problems in due time. This is not only achieved by detailed poolside inspections of lead test assemblies, but also by hot cell post-irradiation examination of selected rods. In the frame of a hot cell examination campaign, enhanced localised corrosion in the vicinity of spacers on SVEA-96 fuel rods was identified in May 1997 as a potential problem. The average rod burnup of the investigated rods was around 50 MWd/kgU after 5 one year cycles of operation. As fuel operation up to six cycles is foreseen in KKLs fuel management plants, the risk of fuel failures caused by enhanced localised corrosion could not be excluded. An action plan was therefore developed in order to identify the root cause. Part of the action plan were two poolside inspection campaigns: 1. Visual inspection of 38 assemblies unloaded during refuelling outage 1996 after 5 cycles in operation. This campaign was performed in June 1997. It gave a broader data base to develop a concept for fuel management for the upcoming refuelling outage scheduled in August 1997. 2. Visual inspection, oxide layer thickness measurements, crud sampling and rod diameter measurements on 29 assemblies with different operation histories. This campaign was performed during the outage. A large portion of the inspected bundles was re-inserted for continued operation. The collected data confirmed that assumptions made for reload licensing and safety analyses were conservative. The inspection campaigns performed at KKL during summer 1997 by ABB Atom demonstrated that it is possible to address unexpected problems in a short time

  14. 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.

  15. Quality inspection of anisotropic scintillating lead tungstate (PbWO4) crystals through measurement of interferometric fringe pattern parameters

    International Nuclear Information System (INIS)

    Cocozzella, N.; Lebeau, M.; Majni, G.; Paone, N.; Rinaldi, D.

    2001-01-01

    Scintillating crystals are widely used as detectors in radiographic systems, computerized axial tomography devices and in calorimeters employed in high-energy physics. This paper results from a project motivated by the development of the CMS calorimeter at CERN, which will make use of a large number of scintillating crystals. In order to prevent crystals from breaking because of internal residual stress, a quality control system based on optic inspection of interference fringe patterns was developed. The principle of measurement procedures was theoretically modelled, and then a dedicated polariscope was designed and built, in order to observe the crystals under induced stresses or to evaluate the residual internal stresses. The results are innovative and open a new perspective for scintillating crystals quality control: the photoelastic constant normal to the optic axis of the lead tungstate crystals (PbWO 4 ) was measured, and the inspection procedure developed is applicable to mass production, not only to optimize the crystal processing, but also to establish a quality inspection procedure

  16. Quality inspection of anisotropic scintillating lead tungstate (PbWO 4) crystals through measurement of interferometric fringe pattern parameters

    Science.gov (United States)

    Cocozzella, N.; Lebeau, M.; Majni, G.; Paone, N.; Rinaldi, D.

    2001-08-01

    Scintillating crystals are widely used as detectors in radiographic systems, computerized axial tomography devices and in calorimeters employed in high-energy physics. This paper results from a project motivated by the development of the CMS calorimeter at CERN, which will make use of a large number of scintillating crystals. In order to prevent crystals from breaking because of internal residual stress, a quality control system based on optic inspection of interference fringe patterns was developed. The principle of measurement procedures was theoretically modelled, and then a dedicated polariscope was designed and built, in order to observe the crystals under induced stresses or to evaluate the residual internal stresses. The results are innovative and open a new perspective for scintillating crystals quality control: the photoelastic constant normal to the optic axis of the lead tungstate crystals (PbWO 4) was measured, and the inspection procedure developed is applicable to mass production, not only to optimize the crystal processing, but also to establish a quality inspection procedure.

  17. Lean Six-Sigma in Aviation Safety: An implementation guide for measuring aviation system’s safety performance

    OpenAIRE

    Panagopoulos, I.; Atkin, C.J.; Sikora, I.

    2016-01-01

    The paper introduces a conceptual framework that could improve the safety performance measurement process and ultimately the aviation system safety performance. The framework provides an implementation guide on how organisations could design and develop a proactive, measurement tool for assessing and measuring the Acceptable Level of Safety Performance (ALoSP) at sigma (σ) level, a statistical measurement unit. In fact, the methodology adapts and combines quality management tools, a leading i...

  18. A quadcopter with heterogeneous sensors for autonomous bridge inspection.

    Science.gov (United States)

    2014-02-01

    Continuously monitoring a bridges health by sensor technologies has been widely used to maintain the operation of : a : roadwork while protecting public users safety. However, monitoring and inspecting numerous bridges in a state is a labor : -...

  19. University building safety index measurement using risk and implementation matrix

    Science.gov (United States)

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

    2018-04-01

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

  20. INSPECT: a package of computer programs for planning and evaluating safeguards inspections

    International Nuclear Information System (INIS)

    Mullen, M.F.

    1980-01-01

    As part of the US Program of Technical Assistance to IAEA Safeguards, PNL has developed a package of computer programs, called INSPECT, that can be used in planning and evaluating safeguards inspections of various types of nuclear facilities. The programs are based on the statistical methods described in Part F of the IAEA Safeguards Technical Manual and can be used to calculate the variance components of the MUF (Material Unaccounted For) statistic, the variance components of the D (difference) statistic, attribute and variables sampling plans, and a measure of the effectiveness of the inspection plan. The paper describes the programs, reviews a number of applications, and indicates areas for future work

  1. An overview of applications and radiation safety aspects of linear accelerators in Brazilian industry

    International Nuclear Information System (INIS)

    Lourenco, M.J.M.; Silva, F.C.A. da

    2002-01-01

    This work presents a brief description of the situation of Brazilian Regulatory Authority about safety control on Industrial Linear Accelerators Installations. It shows the national regulatory infrastructure responsible for radiation safety inspections, the regulation infrastructure, the national inventory of industrial installations, the national system of inspection and enforcement and the national system for qualifying the radiation protection officer. Some results of regulatory safety inspections are also showed in this work. (author)

  2. Information-Driven Inspections

    International Nuclear Information System (INIS)

    Laughter, Mark D.; Whitaker, J. Michael; Lockwood, Dunbar

    2010-01-01

    New uranium enrichment capacity is being built worldwide in response to perceived shortfalls in future supply. To meet increasing safeguards responsibilities with limited resources, the nonproliferation community is exploring next-generation concepts to increase the effectiveness and efficiency of safeguards, such as advanced technologies to enable unattended monitoring of nuclear material. These include attribute measurement technologies, data authentication tools, and transmission and security methods. However, there are several conceptual issues with how such data would be used to improve the ability of a safeguards inspectorate such as the International Atomic Energy Agency (IAEA) to reach better safeguards conclusions regarding the activities of a State. The IAEA is pursuing the implementation of information-driven safeguards, whereby all available sources of information are used to make the application of safeguards more effective and efficient. Data from continuous, unattended monitoring systems can be used to optimize on-site inspection scheduling and activities at declared facilities, resulting in fewer, better inspections. Such information-driven inspections are the logical evolution of inspection planning - making use of all available information to enhance scheduled and randomized inspections. Data collection and analysis approaches for unattended monitoring systems can be designed to protect sensitive information while enabling information-driven inspections. A number of such inspections within a predetermined range could reduce inspection frequency while providing an equal or greater level of deterrence against illicit activity, all while meeting operator and technology holder requirements and reducing inspector and operator burden. Three options for using unattended monitoring data to determine an information-driven inspection schedule are to (1) send all unattended monitoring data off-site, which will require advances in data analysis techniques to

  3. Role of Laws and Regulations For Nuclear Energy Installation in Developing Safety Measures Against Accident

    International Nuclear Information System (INIS)

    Hussein, A.Z.; Zakaria, Kh.M.

    2011-01-01

    The energy industry has been considered as an economic development driver. The fundamental safety policy for nuclear facilities is to protect health and safety of the public and the site personnel against undue risks associated with radiation and radioactive materials resulting from normal operation and abnormal conditions. This policy is implemented, based on the as low as reasonably achievable (ALARA) principle for normal operation and the defense-in-depth principle (prevention of the occurrence of anomalies, prevention of the escalation of anomalies into accidents, and prevention of excessive release of radioactive materials into the environment), through establishment of safety guides and standards. More over the consideration of suitable site selection and safety design, verification by safety evaluation, quality assurance for manufacturing, construction and operation, periodic testing and inspection, confirmation by regulatory bodies, and reflection of experienced troubles to safety countermeasures. Are of these paramount importance concepts are applied variety of nuclear facilities, which is, nuclear reactors, uranium enrichment plants, fuel conversion/fabrication plants, reprocessing plants, radioactive waste management facilities, and so on, considering unique features of each facility.

  4. Conceptual design for transmission line inspection robot

    International Nuclear Information System (INIS)

    Jalal, M F Abdul; Sahari, K S Mohamed; Anuar, A; Arshad, A D Mohd; Idris, M S

    2013-01-01

    Power transmission line is used for power distribution purposes due to their cost effective measure compared to underlying cable. However, prolonged exposure to natural weather may cause fatigue stress to the lines as well as induce material failure. Therefore, periodical line inspection is considered uttermost important as a preventive measure to avoid power outage. However, transmission line inspection has always been a high risk and expensive work. Hazardous works that may harm operator as well as routine that requires precise handling can be performed by robots. Various types of robots have been designed and developed for line inspection but only perform well on a straight and continuous line. As these robots encounter an obstacle during the inspection, then the real problem in terms of robot stability and smooth operation arises. In this paper, conceptual design and evaluation for transmission line inspection robot is presented. The inspection robot mobile robot must be able to bypass or avoid obstacles as it travels along the power transmission line.

  5. Improvement and optimization for in-service inspection of M310 nuclear power station

    International Nuclear Information System (INIS)

    Wang Chen; Sun Haitao; Gao Chen; Deng Dong

    2015-01-01

    In-service inspection (ISI) is an important method to ensure the safety of the mechanical equipment in nuclear power stations. According to the in-service inspection experience feedback from the domestic nuclear power stations, the reasonableness of some provisions in the RSE-M code are discussed and the applications of risk-informed in-service inspection (RI-ISI) are introduced, and the advices for the optimization of the ISI of the domestic M310 nuclear power stations are proposed. (authors)

  6. Fully Employing Software Inspections Data

    Science.gov (United States)

    Shull, Forrest; Feldmann, Raimund L.; Seaman, Carolyn; Regardie, Myrna; Godfrey, Sally

    2009-01-01

    Software inspections provide a proven approach to quality assurance for software products of all kinds, including requirements, design, code, test plans, among others. Common to all inspections is the aim of finding and fixing defects as early as possible, and thereby providing cost savings by minimizing the amount of rework necessary later in the lifecycle. Measurement data, such as the number and type of found defects and the effort spent by the inspection team, provide not only direct feedback about the software product to the project team but are also valuable for process improvement activities. In this paper, we discuss NASA's use of software inspections and the rich set of data that has resulted. In particular, we present results from analysis of inspection data that illustrate the benefits of fully utilizing that data for process improvement at several levels. Examining such data across multiple inspections or projects allows team members to monitor and trigger cross project improvements. Such improvements may focus on the software development processes of the whole organization as well as improvements to the applied inspection process itself.

  7. Survey on requirements for independent reviews and inspections of electrical and I and C equipment

    Energy Technology Data Exchange (ETDEWEB)

    Byman, Karin; Groenkvist, Stefan; Egerbo, Anders; Nilsson, Thomas (AaF Consult AB, Stockholm (Sweden))

    2009-03-15

    In this survey, licensing procedures for the implementation of different kinds of components and systems in nuclear power plants have been studied in four European countries: Belgium (Finland), Germany, and Switzerland. The main focus has been to describe the general features of the licensing procedures for electrical and for instrumentation and control (IandC) equipment and systems. The regulatory framework for the operation of nuclear power plants in Belgium is based on the American regulations. The licensing procedure for each modification of significance for the safety of a plant is carried out by the authorised inspection organisation (AVN), which follows its own procedures for the review of the modification file, the commissioning, and conformity check of the installation. These procedures are general and independent of the technical domain of the equipment or system and AVN uses the US regulations standard review plan (SRP) as a reference for technical reviews. The Federal Agency for Nuclear Control (FANC) is responsible for the surveillance of all nuclear activities in Belgium, but the private non-profit authorised inspection organisation (AVN) does perform inspections and other regulatory tasks delegated by FANC. Controls of electrical components and systems with regard to the general Belgian electrical regulations are performed by accredited inspection organisations. The regulatory framework for the safety of nuclear activities in Finland is domestic and detailed safety requirements are provided by the Radiation and Nuclear Safety Authority (STUK). They cover specific requirements for the licensing procedure for electrical and IandC equipment. In Finland, there are no general differences in the licensing procedure for electrical, instrumentation, and mechanical equipment and the licensing procedure is basically the same for all types of systems, structures and equipment. STUK has the responsibility for the regulatory control in Finland and may seek

  8. Unannounced inspection for integrated safeguards: A theoretical perspective

    International Nuclear Information System (INIS)

    Canty, M.J.; Avenhaus, R.

    2001-01-01

    Full text: The application of a safeguards verification regime based on existing agreements under INFCIRC/153 and on the Additional Protocol, INFCIRC/540, has the potential to allow the International Atomic Energy Agency (IAEA) to relax its traditional facility and material-oriented inspection procedures. The relaxation will take into account the IAEA's enhanced access to information as well as complementary access to locations gained through the application of extended measures foreseen under the Additional Protocol. It will reflect the associated confidence achieved at the State level. It is generally agreed that such a trade-off between the new strengthening measures and the traditional measures is reasonable and desirable, both from the point of view of the inspected State, which would like to receive tangible credit for providing increased openness and transparency in its peaceful nuclear activities, and from the viewpoint of the IAEA, which must apportion its limited inspection resources efficiently. An often-discussed proposal to reduce routine inspection effort while maintaining safeguards effectiveness is to replace scheduled interim inspections with a smaller number of random, unannounced visits. Intuitively, the unpredictability aspect is appealing, as it places the potential diverter in a permanent state of uncertainty. There are also some disadvantages, however, such as the difficulty of planning and implementing truly random inspections and the burden experienced by facility operators obliged to accommodate them. An objective evaluation of a randomized inspection regime vis-a-vis conventional routine inspections requires an objective measure of effectiveness and a means of optimizing that measure - in other words a theoretical framework for analyzing verification problems. In our paper we provide such a framework by quantifying the notion of timely detection and by treating the problem consistently a strategic one. We present a series of models which

  9. Savannah River Plant waste tank inspection manual

    International Nuclear Information System (INIS)

    McNatt, F.G.

    1979-01-01

    This manual is to aid in making visual and photographic inspections and steel thickness measurements of Building 241-F and -H underground waste storage tanks. It describes the inspection program, the storage tanks, the equipment and techniques used and the results of their application, and the inspection recordkeeping methods

  10. Optical microtopographic inspection of asphalt pavement surfaces

    Science.gov (United States)

    Costa, Manuel F. M.; Freitas, E. F.; Torres, H.; Cerezo, V.

    2017-08-01

    Microtopographic and rugometric characterization of surfaces is routinely and effectively performed non-invasively by a number of different optical methods. Rough surfaces are also inspected using optical profilometers and microtopographer. The characterization of road asphalt pavement surfaces produced in different ways and compositions is fundamental for economical and safety reasons. Having complex structures, including topographically with different ranges of form error and roughness, the inspection of asphalt pavement surfaces is difficult to perform non-invasively. In this communication we will report on the optical non-contact rugometric characterization of the surface of different types of road pavements performed at the Microtopography Laboratory of the Physics Department of the University of Minho.

  11. Supervision and inspection plans of plants activities

    International Nuclear Information System (INIS)

    Feijoo, J. P.

    2009-01-01

    Any idea of hierarchization between supervisor and supervised in inspection and supervision activities should necessarily be dismissed, and the independence of the supervisor when executing has tasks should be guaranteed. The inspection and supervision program enable the detection and resolution of materials and human problems alike. In addition, they are a solution to anticipate potential problems in the future, which results in a very significant reduction of industrial accidents and human errors, as well as better use and upkeep of equipment. With these programs we improve our management and our work, and without a doubt they help to strengthen the safety culture in Cofrentes Nuclear Power Plant. (Author)

  12. Risk measures in living probabilistic safety assessment

    International Nuclear Information System (INIS)

    Holmberg, J.; Niemelae, I.

    1993-05-01

    The main objectives of the study are: to define risk measures and suggested uses of them in various living PSA applications for the operational safety management and to describe specific model features required for living PSA applications. The report is based on three case studies performed within the Nordic research project Safety Evaluation by Use of Living PSA and Safety Indicators. (48 refs., 11 figs., 17 tabs.)

  13. Advancing Measurement of Patient Safety Culture

    Science.gov (United States)

    Ginsburg, Liane; Gilin, Debra; Tregunno, Deborah; Norton, Peter G; Flemons, Ward; Fleming, Mark

    2009-01-01

    Objective To examine the psychometric and unit of analysis/strength of culture issues in patient safety culture (PSC) measurement. Data Source Two cross-sectional surveys of health care staff in 10 Canadian health care organizations totaling 11,586 respondents. Study Design A cross-validation study of a measure of PSC using survey data gathered using the Modified Stanford PSC survey (MSI-2005 and MSI-2006); a within-group agreement analysis of MSI-2006 data. Extraction Methods Exploratory factor analyses (EFA) of the MSI-05 survey data and confirmatory factor analysis (CFA) of the MSI-06 survey data; Rwg coefficients of homogeneity were calculated for 37 units and six organizations in the MSI-06 data set to examine within-group agreement. Principal Findings The CFA did not yield acceptable levels of fit. EFA and reliability analysis of MSI-06 data suggest two reliable dimensions of PSC: Organization leadership for safety (α=0.88) and Unit leadership for safety (α=0.81). Within-group agreement analysis shows stronger within-unit agreement than within-organization agreement on assessed PSC dimensions. Conclusions The field of PSC measurement has not been able to meet strict requirements for sound measurement using conventional approaches of CFA. Additional work is needed to identify and soundly measure key dimensions of PSC. The field would also benefit from further attention to strength of culture/unit of analysis issues. PMID:18823446

  14. Apparatus for inspecting a irradiated nuclear fuel rod

    International Nuclear Information System (INIS)

    Saura, Hideaki; Yonemura, Eizo.

    1975-01-01

    Object: To increase safety and inspection efficiency by operating irradiated fuel rods, which are accommodated in a water-filled pool after being taken out from the reactor. Structure: When making inspection of irradiated fuel rods, particularly the cladding tube thereof, a fuel box which stores irradiated fuel rods in a water pool is secured to a securement mechanism with slime removal apparatus and inspection apparatus on either side capable of being vertically moved, and it is then stopped at a water depth of about 2 meters. When the lid of the box is opened, irradiated fuel rods are taken out with gripping means and then secured together with the gripping means to an operation base provided on the outside of the pool. Thereafter, the box is lowered by operating pedals on the operation base to completely pull out the irradiated fuel rods from the box, and the irradiated fuel rods are then horizontally moved and then held in a suspended state. Next a slime removal apparatus in raised by operating pedals and an inspection element assembly are progressively raised for inspection of the state of the cladding tube of each fuel rod after removal of slime therefrom. (Nakamura, S.)

  15. Developments in mechanical ultrasonic inspection and qualification of NDE

    International Nuclear Information System (INIS)

    Kauppinen, P.; Pitkaenen, J.; Kuusinen, P.

    2001-01-01

    Reliability of non-destructive testing results has a direct influence on structural integrity assessment and safety of the inspected structures e.g. NPP primary circuit pressure boundaries. Advanced technology together with highly skilled and experienced personnel is required. One of the current trends is automation. Mechanised equipment can replace tedious manual work in positioning and moving of the transducers. Large areas can be scanned, analysed and numerically documented for direct comparison of eventual later repeated inspections. Another major trend is qualification, which aims to ensure that the inspection results are correct and fit the purpose. The suitability and proper operation of equipment, methods and personnel i.e. the whole chain shall be proven. This presentation summarises the advances in automation and qualification of non-destructive inspection during the second project year, Monitoring of material degradation was included in the studied topics and will also be shortly described. (author)

  16. Measurement of 37Ar to support technology for On-Site Inspection under the Comprehensive Nuclear-Test-BanTreaty

    Science.gov (United States)

    Aalseth, C. E.; Day, A. R.; Haas, D. A.; Hoppe, E. W.; Hyronimus, B. J.; Keillor, M. E.; Mace, E. K.; Orrell, J. L.; Seifert, A.; Woods, V. T.

    2011-10-01

    On-Site Inspection (OSI) is a key component of the verification regime for the Comprehensive Nuclear-Test-Ban Treaty (CTBT). Measurements of radionuclide isotopes created by an underground nuclear explosion are a valuable signature of a Treaty violation. Argon-37 is produced by neutron interaction with calcium in soil, 40Ca( n, α) 37Ar. For OSI, the 35-day half-life of 37Ar provides both high specific activity and sufficient time for completion of an inspection before decay limits sensitivity. This paper presents a low-background internal-source gas proportional counter with an 37Ar measurement sensitivity level equivalent to 45 mBq/SCM in wholeair.

  17. 76 FR 49975 - Inspection of Towing Vessels

    Science.gov (United States)

    2011-08-11

    ... Position Indicating Radio Beacon FAST Fatigue Avoidance Scheduling Tool FMCSA Federal Motor Carrier Safety... human sleep and rest requirements. H.R. Conf. Rep. 108-617, 2004 U.S.C.C.A.N. 936, 951. B. Regulatory... owners and managing operators. The Coast Guard has proposed a traditional inspection scheme as one option...

  18. Operation safety at Ignalina NPP

    International Nuclear Information System (INIS)

    Zheltobriukh, G.

    1999-01-01

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

  19. Metallurgical engineering and inspection practices in the chemical process industries

    International Nuclear Information System (INIS)

    Moller, G.E.

    1987-01-01

    The process industries, in particular the petroleum refining industry, adopted materials engineering and inspection (ME and I) practices years ago and regularly updated them because they were faced with the handling and refining of flammable, toxic, and corrosive feed stocks. These industries have a number of nonproprietary techniques and procedures, some of which may be applicable in the nuclear power generation field. Some specific inspection and engineering techniques used by the process industries within the framework of the guidelines for inspections and worthy of detailed description include the following: (1) sentry drilling or safety drilling of piping subject to relatively uniform corrosion, such as feedwater heater piping, steam piping, and extraction steam piping; (2) on-stream radiography for thickness measurement and detection of unusual conditions - damaged equipment such as valve blockage; (3) critical analysis of the chemical and refining processes for the relative probability of corrosion; (4) communication of valuable experience within the industry; (5) on-stream ultrasonic thickness testing; and (6) on-stream and off-stream crack and flaw detection. The author, trained in the petroleum refining industry but versed in electric utilities, pulp and paper, chemical process, marine, mining, water handling, waste treatment, and geothermal processes, discusses individual practices of these various industries in the paper

  20. Monitoring and inspection techniques for long term storage of higher activity waste packages

    International Nuclear Information System (INIS)

    Bolton, Gary

    2013-01-01

    In 2009, following recent changes in United Kingdom (UK) Government Policy, the Nuclear Decommissioning Authority (NDA) identified a knowledge gap in the area of long term interim storage of waste packages. A cross-industry Integrated Project Team (IPT) for Interim Storage was created with responsibility for delivering Industry Guidance on the storage of packaged Higher Activity Waste (HAW) for the current UK civil decommissioning and clean-up programmes. This included a remit to direct research and development projects via the NDA's Direct Research Portfolio (DRP) to fill the knowledge gap. The IPT for Interim Storage published Industry Guidance in 2012 which established a method to define generic package performance criteria and made recommendations on monitoring and inspection. The package performance method consists of the following steps; identification of the package safety function, identification of evolutionary processes that may affect safety function performance, determination of measurable indicators of these evolutionary processes and calibration of the indicators into package performance zones. This article provides an overview of three projects funded by the NDA's DRP that the UK National Nuclear Laboratory (NNL) have completed to address monitoring and inspection needs of waste packages in interim storage. (orig.)

  1. Inspection of Candu Nuclear Reactor Fuel Channels

    International Nuclear Information System (INIS)

    Baron, J.; Jarvis, G.N.; Dolbey, M.P.; Hayter, D.M.

    1986-01-01

    The Channel Inspection and Gauging Apparatus of Reactors (CIGAR) is a fully atomated, remotely operated inspection system designed to perform multi-channel, multi-task inspection of CANDU reactor fuel channels. Ultrasonic techniques are used for flaw detection, (with a sensitivity capable of detecting a 0.075 mm deep notch with a signal to noise ratio of 10 dB) and pressure tube wall thickness and diameter measurements. Eddy currrent systems are used to detect the presence of spacers between the coaxial pressure tube and calandria tube, as well as to measure their relative spacing. A servo-accelerometer is used to estimate the sag of the fuel channels. This advanced inspection system was commissioned and declared in service in September 1985. The paper describes the inspection systems themselves and discussed the results achieved to-date. (author) [pt

  2. Development of a measure of safety climate

    Directory of Open Access Journals (Sweden)

    N. R. Barnes

    1990-06-01

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

  3. A Laboratory Safety Program at Delaware.

    Science.gov (United States)

    Whitmyre, George; Sandler, Stanley I.

    1986-01-01

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

  4. Safety Commission databases support

    CERN Document Server

    Petit, S; CERN. Geneva. TS Department

    2005-01-01

    A collaboration project between the Safety Commission (SC) and the Controls, Safety and Engineering databases group (TS/CSE) started last year. The aim of this collaboration is to transfer several SC applications from their local environments onto the D7i-MTF EDMS framework, for which the TS/CSE group is responsible. Different domains of activity and projects have been defined in the areas of equipment management, safety inspections, accidents and risks management. Priorities have been established in collaboration with SC. This paper presents the new Safety Inspections Management system (SIM) which will be put in production before the summer 2005 and reviews the constraints of both the users and the development and operational framework that needed to be taken into account. The technical solutions adopted to assure a successful production start-up and operation of the SIM system are described. Progress on other on-going projects and plans for the next year are also reported.

  5. 16 CFR 1605.2 - Conduct and scope of inspections.

    Science.gov (United States)

    2010-01-01

    ... Section 1605.2 Commercial Practices CONSUMER PRODUCT SAFETY COMMISSION FLAMMABLE FABRICS ACT REGULATIONS INVESTIGATIONS, INSPECTIONS AND INQUIRIES PURSUANT TO THE FLAMMABLE FABRICS ACT Procedures for Investigations... any product, fabric, or related material and all pertinent equipment, materials, substances, products...

  6. Mochovce NPP safety measures evaluation from point of view of operational safety enhancement

    International Nuclear Information System (INIS)

    Cillik, I.; Vrtik, L.

    2000-01-01

    Mochovce NPP consists of four reactor units of WWER 440/V213 type and it is located in the south-middle part of Slovakia. At present first unit operated and the second one under the construction finishing. As these units represent second generation of WWER reactor design, the additional safety measures (SM) were implemented to enhance operational and nuclear safety according to the recommendations of performed international audits and operational experience based on exploitation of other similar units (as Dukovany and J. Bohunice NPPs). These requirements result into a number of SMs grouped according to their purpose to reach recent international requirements on nuclear and operational safety. The paper presents the bases used for safety measures establishing including their grouping into the comprehensive tasks covering different areas of safety goals as well as structural organization of a project management of including participating companies and work performance. More, results are given regarding contribution of selected SMs to the total core damage frequency decreasing. (author)

  7. In service inspection of pipes based on risk methods

    International Nuclear Information System (INIS)

    Mendoza G, G.; Viais J, J.; Carmona C, M.

    2006-01-01

    The politics of the Nuclear Regulatory Commission (by its initials in English NRC) of the United States of America on the use of the Probabilistic Safety Analysis (PSA) in activities of nuclear regulation it foments the use of this analysis technique to improve the decisions making, to reduce the unnecessary work in maintenance aspects, inspection and tests and to improve the regulatory efficiency. The inspection programs in service (ISI by its initials in English) developed by the American Society of Mechanical Engineers (by its initials in English ASME) it has been the one primary mechanism to prove the mechanical equipment in plants of nuclear energy, these programs indeed have been carried out in plants of nuclear energy by more of two decades. Their purpose is to identify the conditions, such as indications of cracks that are precursory of flights and ruptures which violate the integrity principles of the pressure frontier. The inspection in service activities include ultrasonic tests, surface tests and penetrating liquids test, also activities that include the scaffolds construction, removal of insulations and welding polishing. The inspections in service every 18 months during the times outside of service are executed. One of the objectives is to lower the costs of the inspections during the times outside of service and to reduce the exposure to the radiation by part of the personnel during these times out for inspections, while it is increased or it maintains the personnel's safety and the reliability. As part of the methodology a pipe segment is selected for which a fault in any point has the same consequences, being calculated the fault probability of the tube using the dimensions of the segment. In this work the inspection in service methodology is applied based on risk to an aspersion system of low pressure of the Laguna Verde Nucleo electric Central. For this system a reduction in the number of welding to inspect of 103 to only 15 is obtained

  8. Safety and Health in Nuclear Malaysia workplace

    International Nuclear Information System (INIS)

    Wo, Y.M.

    2013-01-01

    Safety and health at work place is essential to ensure the health of their workers as required under the Occupational Safety and Health Act 1994 (Act 514). In Malaysian Nuclear Agency, each building / block was appointed with one/ two supervisors, known as Area Supervisor to ensure the safety of buildings / blocks. The area supervisor will conduct periodic bimonthly inspections of the building / block under their supervision. This paper presents the results of the inspection of 80 supervisors over 45 buildings / blocks at the Malaysian Nuclear Agency for the first six months of the year 2013. (author)

  9. Studying the Safety Impact of Autonomous Vehicles Using Simulation-Based Surrogate Safety Measures

    OpenAIRE

    Morando, Mark Mario; Tian, Qingyun; Truong, Long T.; Vu, Hai L.

    2018-01-01

    Autonomous vehicle (AV) technology has advanced rapidly in recent years with some automated features already available in vehicles on the market. AVs are expected to reduce traffic crashes as the majority of crashes are related to driver errors, fatigue, alcohol, or drugs. However, very little research has been conducted to estimate the safety impact of AVs. This paper aims to investigate the safety impacts of AVs using a simulation-based surrogate safety measure approach. To this end, safety...

  10. Refurbishment and safety management of JMTR in extended showdown

    International Nuclear Information System (INIS)

    Ide, Hiroshi; Hori, Naohiko; Gorai, Shigeru; Kusunoki, Tsuyoshi

    2011-06-01

    inspection of equipments during reactor refurbishment is difference from it of reactor operation term. And, refurbishment work is paid attention to work with special measures during reactor refurbishment. This report summarized JMTR refurbishment and safety management during reactor shutdown. (author)

  11. Development of safety performance indicators in Japan

    International Nuclear Information System (INIS)

    Ohashi, H.; Tamao, S.; Tanaka, J.; Sawayama, T.

    2001-01-01

    For the purpose of safety regulations of operating nuclear power stations in Japan, the regulatory authorities utilize two types of regulations. One is the direct regulation, such as periodical inspection to inspect the function and performance of equipment important to safety, and the other is the audit type regulation such as preservation inspection to audit the compliance with the safety preservation rules. As performance indicators are expected to be an effective tool to evaluate the activities by audit type regulations, NUPEC is studying a comprehensive set of operational performance indicators to meet the effective evaluation method for the safety preservation activities in the audit type regulations under the frame of current safety regulation system. The study includes the establishment of comprehensive operational performance indicators applicable in Japan, the effective application of performance indicators to the current Japanese regulation, the clarification of the applicable scope of utilization, the possibility of applying the performance indicators. This report describes the present status of our performance indicator studies. After the completion of these studies the regulatory authorities will evaluate if and how the new set of comprehensive performance indicators could be introduced to Japanese regulatory scheme. (author)

  12. Standard Practice for Visual Inspections of Photovoltaic Modules

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2008-01-01

    1.1 This practice covers procedures and criteria for visual inspections of photovoltaic modules. 1.2 Visual inspections of photovoltaic modules are normally performed before and after modules have been subjected to environmental, electrical, or mechanical stress testing, such as thermal cycling, humidity-freeze cycling, damp heat exposure, ultraviolet exposure, mechanical loading, hail impact testing, outdoor exposure, or other stress testing that may be part of photovoltaic module testing sequence. 1.3 This practice does not establish pass or fail levels. The determination of acceptable or unacceptable results is beyond the scope of this practice. 1.4 There is no similar or equivalent ISO standard. 1.5 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

  13. Proceedings of the 13. International Workshop on Inspection Practices. 13. International Nuclear Regulatory Inspection Workshop, 17-21 April 2016, Bruges, Belgium

    International Nuclear Information System (INIS)

    Bens, Jan; De Boeck, Benoit; Wertelaers, An; Van Haesendonck, Michel; Barras, Pierre; Leblanc, Alexandre; Regan, Christopher; Smith, Paul; Kupila, Jukka; Crespo, Julio; Meskens, Gaston; Schneider, Matthias

    2017-01-01

    The main purpose of the workshop was to provide a forum for information exchange on the regulatory inspection activities. Participants had the opportunity to meet with their counterparts from other countries and organisations to discuss current and future issues on the selected topics. They developed conclusions regarding these issues and identified methods that may help to improve their own inspection programmes. The CNRA believes that an essential factor in ensuring the safety of nuclear installations is the continuing exchange and analysis of technical information and data. To facilitate this exchange the Committee has established working groups and groups of experts in specialised topics. The Working Group on Inspection Practices (WGIP) was formed in 1990 with the mandate '...to concentrate on the conduct of inspections and how the effectiveness of inspections could be evaluated..'. The WGIP facilitates the exchange of information and experience related to regulatory safety inspections between CNRA member countries. These proceedings cover the 13. International Nuclear Regulatory Inspection Workshop held by WGIP on regulatory inspection activities. This workshop, which is the 13. in a series, along with many other activities performed by the working group, is directed towards this goal. The consensus from participants at previous workshops noted that the value of meeting with people from other inspection organisations was one of the most important achievements. The focus of this workshop was on experience gained from regulatory inspection activities in three areas: - experience from the inspection activities during the transition from an operating reactor to a de-fueled status with a commitment to permanently cease power operations; - inspection of modifications; - the inspectors' role in the enforcement process. As part of the registration, participants were asked to respond to a questionnaire describing practices within their own countries on these topics

  14. Postearthquake safety evaluation of buildings at DOE (Department of Energy) facilities

    International Nuclear Information System (INIS)

    Gallagher, R.

    1989-01-01

    New postearthquake building safety evaluation procedures have been developed. The procedures cover inspection and safety assessment of the principal types of building construction found in the US, including wood, masonry, tilt-up, concrete, and steel frame structures. Guidelines are also provided for appraising the structural safety significance of ground movements resulting from geologic hazards and for the inspection of nonstructural elements for falling and other hazards

  15. Evaluation of inspection and enforcement programs of other regulatory, safety, and professional organizations: Phase I

    International Nuclear Information System (INIS)

    Thompson, S.R.; Speaker, D.M.; Cohen, S.

    1977-09-01

    This volume presents findings in five topical areas from a survey of the inspection and enforcement programs of 20 agencies and an in-depth study of six of those agencies. It was found that agencies using resident inspectors generally assign them in groups to prevent capture and improve supervision, use some sort of performance appraisal system, and place enforcement power in the field. Enforcement powers vary: many have ''shutdown'' power, and the majority combine inspection and enforcement in the field. Civil and administrative remedies appear easier to use than criminal remedies. Inspector management techniques include training, career planning, and evaluation. Inspection methods usually include hands-on verification, and inspection frequency is often based on past performance. Most programs assess their effectiveness in some way, and about half rate licensee performance. Information is seldom formally transmitted from I and E to other agency elements. After examining these areas, a variety of topics were recommended for further study, including assigning residents in pairs, developing a performance appraisal system, placing more enforcement power in the field, and providing more ''hands-on'' inspection activities

  16. Evaluating the effectiveness of a priori information on process measures in a virtual reality inspection task

    Directory of Open Access Journals (Sweden)

    Shannon Raye Bowling

    2010-06-01

    Full Text Available 72 1024x768 Normal 0 false false false Due to the nature of the complexity of the aircraft maintenance industry, much emphasis has been placed on improving aircraft inspection performance. One proven technique for improving inspection performance is the use of training. Several strategies have been implemented for training, one of which is giving feedforward information. The use of a priori (feedforward information is known to positively affect inspection performance (Ernst and Yovits, 1972; Long and Rourke, 1989; McKernan, 1989; Gramopadhye et al., 1997.  This information can consist of knowledge about defect characteristics (types, severity/criticality, and location and the probability of occurrence. Although several studies have been conducted that demonstrate the usefulness of feedforward as a training strategy, there are certain research issues that need to be addressed. This study evaluates the effects of feedforward information on process measures in a simulated 3-dimensional environment (aircraft cargo bay by the use of virtual reality.

  17. Targeted In-service Inspections Using Risk Insights

    International Nuclear Information System (INIS)

    Kulat, S.; Montgomery, B.; Robin Graybeal, M.

    2012-01-01

    This paper includes a discussion of the historical background and rationale for development of a targeted In-service Inspection (ISI) program using risk insights, known as Risk-Informed In-service Inspection (RI-ISI). RI-ISI programs are optimized inspection programs which target specific welds for inspection based upon potential degradation mechanisms and consequences of failure. Inspections are performed on those welds that are the highest contributors to plant risk. Additionally the inspections are tailored to detect the specific postulated degradation mechanisms. As a result, the numbers of inspections are reduced along with the associated cost and radiation exposure, while maintaining or improving the level of quality and safety. Provided in this paper are the basic principles of RI-ISI program development, and a summary of the impact of the implementation of such programs. For example, implementation of a Risk-Informed In-service Inspection program results in a reduction of both cost and radiation exposure. Cost savings are estimated at between USD 1,000,000 and USD 2,300,000 per unit per ten year interval for a Class 1 and2 RI-ISI application. Cost savings are estimated based on average cost per weld of USD 7600 for examination, including the following activities: erection and removal of scaffolding, removal and replacement of insulation, removal and replacement of interferences, weld preparation, examination, documentation, craft support. Reduction in radiation exposure is estimated at 75% to 90% for a Class 1 and2 RI-ISI application. Reduction in radiation exposure is due to the following factors: number of welds selected for examination decreases by 60% to 75%, surface examinations essentially eliminated, within a given risk category, welds can be selected for examination based on additional factors such as the minimization of radiation exposure.(author).

  18. Proceedings of the 5th annual meeting of Japanese Society of Radiation Safety Management 2006 Nagoya

    International Nuclear Information System (INIS)

    2006-01-01

    This is the program and the proceedings of the 5th annual meeting of Japanese Society of Radiation Safety Management held from November 29th through December 1st of 2006. The sessions held are: (1) Radiation Measurement 1, (2) Education Method, (3) Radiation Control, (4) Waste Handling, Contamination Inspection, and Renewal, (5) Exposure Reduction, Radiation Evaluation, and Radioactivity Control (6) Radiation Measurement 2, (7) Operation Environment, (8) Medical Exposure, (9) Radiation Measurement 3, (10) Software, IT Technology, and Data Processing, (11) Emission and Drainage Handling, and (12) Radiation Effect and Contamination Countermeasure. The poster sessions held are: (1) Radiation Measurement, (2) Environmental Radiation, (3) Scattering Rate, Penetration Rate, and Contamination Inspection, (4) Education Method, (5) Medical Exposure, (6) Access Control and Software, and (7) Radiation Control Method and Monitoring. The symposia held are: (1) 'Toward Establishment of Guideline for Safe X-ray Handling Education' and 'International Situation of Radiation Safety'. 2 keynote lectures were also held. (S.K.)

  19. Food safety security: a new concept for enhancing food safety measures.

    Science.gov (United States)

    Iyengar, Venkatesh; Elmadfa, Ibrahim

    2012-06-01

    The food safety security (FSS) concept is perceived as an early warning system for minimizing food safety (FS) breaches, and it functions in conjunction with existing FS measures. Essentially, the function of FS and FSS measures can be visualized in two parts: (i) the FS preventive measures as actions taken at the stem level, and (ii) the FSS interventions as actions taken at the root level, to enhance the impact of the implemented safety steps. In practice, along with FS, FSS also draws its support from (i) legislative directives and regulatory measures for enforcing verifiable, timely, and effective compliance; (ii) measurement systems in place for sustained quality assurance; and (iii) shared responsibility to ensure cohesion among all the stakeholders namely, policy makers, regulators, food producers, processors and distributors, and consumers. However, the functional framework of FSS differs from that of FS by way of: (i) retooling the vulnerable segments of the preventive features of existing FS measures; (ii) fine-tuning response systems to efficiently preempt the FS breaches; (iii) building a long-term nutrient and toxicant surveillance network based on validated measurement systems functioning in real time; (iv) focusing on crisp, clear, and correct communication that resonates among all the stakeholders; and (v) developing inter-disciplinary human resources to meet ever-increasing FS challenges. Important determinants of FSS include: (i) strengthening international dialogue for refining regulatory reforms and addressing emerging risks; (ii) developing innovative and strategic action points for intervention {in addition to Hazard Analysis and Critical Control Points (HACCP) procedures]; and (iii) introducing additional science-based tools such as metrology-based measurement systems.

  20. Public knowledge and attitudes regarding public health inspections of restaurants.

    Science.gov (United States)

    Jones, Timothy F; Grimm, Karen

    2008-06-01

    Foodborne diseases cause 76 million illnesses in the U.S. each year, and almost half of all money spent on food is spent in restaurants. Restaurant inspections are a critical public health intervention for the prevention of foodborne disease. A telephone survey of randomly selected Tennessee residents aged > or =18 was performed. Data were collected on respondents' demographics, knowledge, attitudes, and expectations regarding restaurant inspections. Of 2000 respondents, 97% were aware that restaurants are inspected regularly by the health department. More than half of the respondents believed that inspections should be performed at least 12 times per year; only one third were aware that inspections currently occur only twice per year in Tennessee. More than one third of the respondents considered an inspection score of > or =90 acceptable for a restaurant at which they would eat; the mean score in Tennessee is 82. When presented with a variety of scenarios, an overwhelming number of respondents felt that public health responses to safety violations should be far more draconian than they actually are. Survey answers did not differ consistently based on respondents' race, gender, or history of having worked in a restaurant. This study identified a number of public misconceptions and unrealistically high expectations of the public health restaurant-inspection system. It is important to improve consumers' understanding of inspection scores and the limitations of regulatory inspections, as well as the role of such inspections in disease prevention.

  1. Acoustic-Seismic Coupling in Porous Ground - Measurements and Analysis for On-Site-Inspection Support

    Science.gov (United States)

    Liebsch, Mattes; Gorschlüter, Felix; Altmann, Jürgen

    2014-05-01

    During on-site inspections (OSI) of the Comprehensive Nuclear Test Ban Treaty Organisation (CTBTO) a local seismic network can be installed to measure seismic aftershock signals of an assumed underground nuclear explosion. These signals are caused by relaxation processes in and near the cavity created by the explosion and when detected can lead to a localisation of the cavity. This localisation is necessary to take gas samples from the ground which are analysed for radioactive noble gas isotopes to confirm or dismiss the suspicion of a nuclear test. The aftershock signals are of very low magnitude so they can be masked by different sources, in particular periodic disturbances caused by vehicles and aircraft in the inspection area. Vehicles and aircraft (mainly helicopters) will be used for the inspection activities themselves, e.g. for overhead imagery or magnetic-anomaly sensing. While vehicles in contact with the ground can excite soil vibrations directly, aircraft and vehicles alike emit acoustic waves which excite soil vibrations when hitting the ground. These disturbing signals are of periodic nature while the seismic aftershock signals are pulse-shaped, so their separation is possible. The understanding of the coupling of acoustic waves to the ground is yet incomplete, a better understanding is necessary to improve the performance of an OSI, e.g. to address potential consequences for the sensor placement, the helicopter trajectories etc. In a project funded by the Young Scientist Research Award of the CTBTO to one of us (ML), we investigated the acoustic-seismic coupling of airborne signals of jet aircraft and artificially induced ones by a speaker. During a measurement campaign several acoustic and seismic sensors were placed below the take-off trajectory of an airport at 4 km distance. Therefore taking off and landing jet aircraft passed nearly straightly above the setup. Microphones were placed close to the ground to record the sound pressure of incident

  2. Eddy current system for inspection of train hollow axles

    Energy Technology Data Exchange (ETDEWEB)

    Chady, Tomasz; Psuj, Grzegorz; Sikora, Ryszard; Kowalczyk, Jacek; Spychalski, Ireneusz [Department of Electrical and Computer Engineering, Faculty of Electrical Engineering, West Pomeranian University of Technology, Szczecin (Poland)

    2014-02-18

    The structural integrity of wheelsets used in rolling stock is of great importance to the safety. In this paper, electromagnetic system with an eddy current transducer suitable for the inspection of hollow axles have been presented. The transducer was developed to detect surface braking defects having depth not smaller than 0.5 mm. Ultrasound technique can be utilized to inspect the whole axle, but it is not sufficiently sensitive to shallow defects located close to the surface. Therefore, the electromagnetic technique is proposed to detect surface breaking cracks that cannot be detected by ultrasonic technique.

  3. Advanced Inspection and Repair Welding Techniques for SCC Countermeasures

    International Nuclear Information System (INIS)

    Takagi, T.; Nishimoto, K.; Uchimoto, T.

    2012-01-01

    Feasibility studies of advanced inspection and repair welding techniques were conducted in the framework of the Nuclear and Industry Safety Agency of Japan (NISA) project on the enhancement of ageing management and maintenance of NPPs. In this paper, features of NDE methods investigated in the projects, main results of research activities and prospect of nickel based alloy weld inspection are discussed. We also make a review for the integrity and reliability evaluation techniques for repair welding of ageing plants which were intensively investigated in view of regulatory criteria, in NISA project. (author)

  4. Radiometric evaluation of cargo and container inspection systems with X-ray emitting accelerators; Avaliação radiométrica de sistemas de inspeção de cargas e contêineres com aceleradores emissores de raios-X

    Energy Technology Data Exchange (ETDEWEB)

    Fideles, L.; Costa, J., E-mail: lazarofideles@gmail.com [Faculdade Casa Branca, SP (Brazil). Pós-Graduação de Proteção Radiológica em Aplicações Médicas, Industriais e Nucleares; Pelegrineli, S.Q. [MAXIM Cursos, Rio de Janeiro-RJ (Brazil); Lima, A.R. [Comissão Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil)

    2017-07-01

    In X-ray scanners for non-invasive safety inspection of vehicles, cargoes and containers from linear accelerators, installed at borders, boundaries and port terminals, the exposure rates in the supervised and controlled areas of the facility may vary considerably, depending on the type of body of the inspected vehicle. The study emerges as a way to reassess safety insulation and create additional shielding means as increased radiation levels during inspections can increase the likelihood of stochastic effects for occupationally exposed individuals and public individuals. The objective of the study is to measure and analyze the variation of the radiation exposure rate in the installation, considering trucks with metal and canvas bodies, which are inspected in these scanners. This is an experimental field study in X-ray scanners for inspection of cargoes and containers, the exposure rates being obtained by means of a radiation detector type ionization chamber.

  5. 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

  6. Optimal allocation of international atomic energy agency inspection resources

    International Nuclear Information System (INIS)

    Markin, J.T.

    1987-01-01

    Each year the Department of Safeguards of the International Atomic Energy Agency (IAEA) conducts inspections to confirm that nuclear materials and facilities are employed for peaceful purposes. Because of limited inspection resources, however, the IAEA cannot fully attain its safeguards goals either quantitatively as measured by the inspection effort negotiated in the facility attachments or qualitatively as measured by the IAEA criteria for evaluating attainment of safeguards goals. Under current IAEA procedures the allocation of inspection resources assigns essentially equal inspection effort to facilities of the same type. An alternative approach would incorporate consideration of all material categories and facilities to be assigned inspection resources when allocating effort to a particular facility. One such method for allocating inspection resources is based on the IAEA criteria. The criteria provide a framework for allocating inspection effort that includes a ranking of material types according to their safeguards importance, an implicit definition of inspection activities for each material and facility type, and criteria for judging the attainment of safeguards goals in terms of the quality and frequency of these inspection activities. This framework is applicable to resource allocation for an arbitrary group of facilities such as a state's fuel cycle, the facilities inspected by an operations division, or all of the facilities inspected by the IAEA

  7. OSE inspection of computer security: Review

    International Nuclear Information System (INIS)

    Jaehne, E.M.

    1987-01-01

    The inspection process within the Department of Energy (DOE) serves the function of analyzing and reporting on the performance of security measures and controls in specific areas at sites throughout DOE. Three aspects of this process are discussed based on experience in computer security: Policy basis of performance inspections; Role and form of standards and criteria in inspections; and Conducting an inspection using the standards and criteria. Inspections are based on DOE and other applicable policy in each area. These policy statements have a compliance orientation in which the paper trail is often more clearly discernible than the security intention. The relationship of policy to performance inspections is discussed. To facilitate bridging the gap between the paper trail and the security intention defined by policy, standards and criteria were developed in each area. The consensus process and structure of the resulting product for computer security are discussed. Standards and criteria are inspection tools that support the site in preparing for an inspection and the inspector in conducting one. They form a systematic approach that facilitates consistency in the analysis and reporting of inspection results. Experience using the computer security standards and criteria is discussed

  8. Monitor for safety engineering facility

    International Nuclear Information System (INIS)

    Sato, Akira; Kaneda, Mitsunori.

    1982-01-01

    Purpose: To improve the reactor safety and decrease misoperation upon periodical inspection by instantly obtaining the judgement for the stand-by states in engineering safety facilities of a nuclear power plant. Constitution: Process inputs representing the states of valves, pumps, flowrates or the likes of the facility are gathered into an input device and inputted to a status monitor. The status of the facility inputted to the input device are judged for each of the inputs in a judging section and recognized as a present system stand-by pattern of the system (Valve) to be inspected. While on the other hand, a normal system stand-by pattern previously stored in a memory unit is read out by an instruction from an operator console and judged by comparison with the system stand-by pattern in a comparison section. The results are displayed on a display device. Upon periodical inspection, inspection procedures stored in the memory unit are displayed on the display device by the instruction from the operator console. (Seki, T.)

  9. Problems in determining the optimal use of road safety measures

    DEFF Research Database (Denmark)

    Elvik, Rune

    2014-01-01

    for intervention that ensures maximum safety benefits. The third problem is how to develop policy options to minimise the risk of indivisibilities and irreversible choices. The fourth problem is how to account for interaction effects between road safety measures when determining their optimal use. The fifth......This paper discusses some problems in determining the optimal use of road safety measures. The first of these problems is how best to define the baseline option, i.e. what will happen if no new safety measures are introduced. The second problem concerns choice of a method for selection of targets...... problem is how to obtain the best mix of short-term and long-term measures in a safety programme. The sixth problem is how fixed parameters for analysis, including the monetary valuation of road safety, influence the results of analyses. It is concluded that it is at present not possible to determine...

  10. GASVOL 18'' gas pipeline - risk based inspection study

    Energy Technology Data Exchange (ETDEWEB)

    Bjoernoey, Ola H.; Etterdal, Birger A. [Det Norske Veritas (DNV), Oslo (Norway); Guarize, Rosimar; Oliveira, Luiz F.S. [Det Norske Veritas (DNV) (Brazil); Faertes, Denise; Dias, Ricardo [TRANSPETRO - PETROBRAS Transporte S.A., Rio de Janeiro, RJ (Brazil)

    2003-07-01

    This paper describes a risk based approach and inspection planning as part of the Pipeline Integrity Management (PIM) system for the 95.5 km long 18'' GASVOL gas pipeline in the South eastern region of Brazil transporting circa 5 000 000 m3 dry gas per day. Pipeline systems can be subject to several degradation mechanisms and inspection and monitoring are used to ensure system integrity. Modern pipeline regulations and codes are normally based on a core safety or risk philosophy. The detailed design requirements presented in design codes are practical interpretations established so as to fulfill these core objectives. A given pipeline, designed, constructed and installed according to a pipeline code is therefore the realization of a structure, which, along its whole length, meets the applicable safety objectives of that code. The main objective of Pipeline Integrity Management (PIM) is to control and document the integrity of the pipeline for its whole service life, and to do this in a cost-effective manner. DNV has a specific approach to RBI planning, starting with an initial qualitative assessment where pipelines and damage type are ranked according to risk and potential risk reduction by an inspection and then carried forward to a quantitative detailed assessment where the level of complexity and accuracy can vary based on availability of information and owner needs. Detailed assessment requires significant effort in data gathering. The findings are dependent upon the accuracy of the inspection data, and on DNV's interpretation of the pipeline reference system and simplifications in the inspection data reported. The following specific failure mechanisms were investigated: internal corrosion, external corrosion, third party interference, landslides and black powder. RBI planning, in general words, is a 'living process'. In order to optimize future inspections, it is essential that the analyses utilize the most recent information regarding

  11. Interaction between periodic in-service inspection requirements and design

    International Nuclear Information System (INIS)

    Prot, A.C.; Saglio, R.

    1979-03-01

    After reviewing the requirements specific of periodic In-Service Inspection related to safety problems, especially for the pressure vessels, and taking into account the experience gained with several PWR reactors, the authors show these requirements could lead to modify the primary circuit design

  12. Regulatory aspects of NPP safety

    International Nuclear Information System (INIS)

    Kastchiev, G.

    1999-01-01

    Extensive review of the NPP Safety is presented including tasks of Ministry of Health, Ministry of Internal Affairs, Ministry of Environment and Waters, Ministry of Defense in the field of national system for monitoring the nuclear power. In the frame of national nuclear safety legislation Bulgaria is in the process of approximation of the national legislation to that of EC. Detailed analysis of the status of regulatory body, its functions, organisation structure, responsibilities and future tasks is included. Basis for establishing the system of regulatory inspections and safety enforcement as well as intensification of inspections is described. Assessment of safety modifications is concerned with complex program for reconstruction of Units 1-4 of Kozloduy NPP, as well as for modernisation of Units 5 and 6. Qualification and licensing of the NPP personnel, Year 2000 problem, priorities and the need of international assistance are mentioned

  13. Improving health, safety and energy efficiency in New Zealand through measuring and applying basic housing standards.

    Science.gov (United States)

    Gillespie-Bennett, Julie; Keall, Michael; Howden-Chapman, Philippa; Baker, Michael G

    2013-08-02

    Substandard housing is a problem in New Zealand. Historically there has been little recognition of the important aspects of housing quality that affect people's health and safety. In this viewpoint article we outline the importance of assessing these factors as an essential step to improving the health and safety of New Zealanders and household energy efficiency. A practical risk assessment tool adapted to New Zealand conditions, the Healthy Housing Index (HHI), measures the physical characteristics of houses that affect the health and safety of the occupants. This instrument is also the only tool that has been validated against health and safety outcomes and reported in the international peer-reviewed literature. The HHI provides a framework on which a housing warrant of fitness (WOF) can be based. The HHI inspection takes about one hour to conduct and is performed by a trained building inspector. To maximise the effectiveness of this housing quality assessment we envisage the output having two parts. The first would be a pass/fail WOF assessment showing whether or not the house meets basic health, safety and energy efficiency standards. The second component would rate each main assessment area (health, safety and energy efficiency), potentially on a five-point scale. This WOF system would establish a good minimum standard for rental accommodation as well encouraging improved housing performance over time. In this article we argue that the HHI is an important, validated, housing assessment tool that will improve housing quality, leading to better health of the occupants, reduced home injuries, and greater energy efficiency. If required, this tool could be extended to also cover resilience to natural hazards, broader aspects of sustainability, and the suitability of the dwelling for occupants with particular needs.

  14. Risk based maintenance to increase safety and decrease costs

    International Nuclear Information System (INIS)

    Phillips, J.H.

    2000-01-01

    Risk-Based techniques have been developed for commercial nuclear power plants for the last eight years by a team working through the ASME Center for Research and Technology Development (CRTD). System boundaries and success criteria is defined using the Probabilistic Risk Analysis or Probabilistic Safety Analysis developed to meet the Individual Plant Evaluation. Final ranking of components is by a plant expert panel similar to the one developed for the Maintenance Rule. Components are identified as being high risk-significant or low risk-significant. Maintenance and resources are focused on those components that have the highest risk-significance. The techniques have been developed and applied at a number of plants. Results from the first risk-based inspection pilot plant indicates safety due to pipe failure can be doubled while the inspection reduced to about 80% when compared with current inspection programs. Pilot studies on risk-based testing indicate that about 60% of pumps and 25 to 30% of valves in plants are high safety-significant The reduction in inspection and testing reduces the person-rem exposure and resulting in further increases in safety. These techniques have been documented in publications by the ASME CRTD which are referenced. (author)

  15. Operation Procedure of Inspection Equipment for TRISO-coated Fuel Particle

    International Nuclear Information System (INIS)

    Kim, S. H.; Kim, Y. K.; Cho, M. S.; Kim, Y. M.; Park, J. Y.; Kim, W. J.; Jeong, K. C.; Oh, S. C.; Lee, Y. W.

    2007-03-01

    TRISO-coated fuel particle for HTGR(high temperature gas cooled reactor) is composed of fuel kernel and coating layers. The kernel and coated particle are characterized by inspection processes for inspection items such as diameter of kernel, thickness, density and an-isotropy of coating layer. The coating thickness can be nondestructively measured by X-ray inspection equipment. The coating thickness as well as the sphericity can be also measured by optical inspection system as a ceramography method. The an-isotropy can be characterized by photometer. The density of coating layer can be measured by density column. The size and sphericity of particles can be measured by PSA(particle size analyzer). The thermo-chemical characteristics of kernel can be analyzed by TG/DTA(Thermogravimetric/Differential Thermal Analyzer). The inspection objective, equipment composition, operation principle, operation manual for each equipment was described in this operation procedure, which will be used for the characterization of inspection items described above

  16. Terahertz Radome Inspection

    Directory of Open Access Journals (Sweden)

    Fabian Friederich

    2018-01-01

    Full Text Available Radomes protecting sensitive radar, navigational, and communications equipment of, e.g., aircraft, are strongly exposed to the environment and have to withstand harsh weather conditions and potential impacts. Besides their significance to the structural integrity of the radomes, it is often crucial to optimize the composite structures for best possible radio performance. Hence, there exists a significant interest in non-destructive testing techniques, which can be used for defect inspection of radomes in field use as well as for quality inspection during the manufacturing process. Contactless millimeter-wave and terahertz imaging techniques provide millimeter resolution and have the potential to address both application scenarios. We report on our development of a three-dimensional (3D terahertz imaging system for radome inspection during industrial manufacturing processes. The system was designed for operation within a machining center for radome manufacturing. It simultaneously gathers terahertz depth information in adjacent frequency ranges, from 70 to 110 GHz and from 110 to 170 GHz by combining two frequency modulated continuous-wave terahertz sensing units into a single measurement device. Results from spiraliform image acquisition of a radome test sample demonstrate the successful integration of the measurement system.

  17. Fire Safety Deficiencies

    Data.gov (United States)

    U.S. Department of Health & Human Services — A list of all fire safety deficiencies currently listed on Nursing Home Compare, including the nursing home that received the deficiency, the associated inspection...

  18. Joint road safety operations in tunnels and open roads

    Science.gov (United States)

    Adesiyun, Adewole; Avenoso, Antonio; Dionelis, Kallistratos; Cela, Liljana; Nicodème, Christophe; Goger, Thierry; Polidori, Carlo

    2017-09-01

    The objective of the ECOROADS project is to overcome the barrier established by the formal interpretation of the two Directives 2008/96/EC and 2004/54/EC, which in practice do not allow the same Road Safety Audits/Inspections to be performed inside tunnels. The projects aims at the establishment of a common enhanced approach to road infrastructure and tunnel safety management by using the concepts and criteria of the Directive 2008/96/CE on road infrastructure safety management and the results of related European Commission (EC) funded projects. ECOROADS has already implemented an analysis of national practices regarding Road Safety Inspections (RSI), two Workshops with the stakeholders, and an exchange of best practices between European tunnel experts and road safety professionals, which led to the definition of common agreed safety procedures. In the second phase of the project, different groups of experts and observers applied the above common procedures by inspecting five European road sections featuring both open roads and tunnels in Belgium, Albania, Germany, Serbia and Former Yugoslav Republic of Macedonia. This paper shows the feedback of the 5 joint safety operations and how they are being used for a set of - recommendations and guidelines for the application of the RSA and RSI concepts within the tunnel safety operations.

  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. AREVA General Inspectorate Annual Report 2013 - Status of safety in nuclear facilities

    International Nuclear Information System (INIS)

    Oursel, Luc; Riou, Jean

    2014-06-01

    This annual report by AREVA's General Inspectorate deals with the status of nuclear safety and radiation protection in the group's facilities and operations over the course of 2013. Based on the findings made during implementation of the annual inspection program, this annual report also includes the results of the analysis of significant events and the observations and assessments of specialists in the Safety Health Security Sustainable Development Department (SHSSDD), supplemented by regular interaction with the safety regulators, different government agencies, stakeholders and other nuclear operators. Additionally, this report presents the action plans put into motion and the directions taken for continuous improvement in risk prevention for operations conducted in France and internationally. In 2013, the level of safety in the group's nuclear facilities and operations remained satisfactory, although improvements are necessary in some domains. This report is based on established indicators, analyses of reported events, responses to commitments made to the regulators, and the results of different improvement actions reported on in the inspected and supported entities. In 2013, no level 2 event on the International Nuclear and Radiological Event Scale (INES) was reported, the bottom-up reporting of weak signals was confirmed, dose levels were low and there were no radiological impacts on the environment. The General Inspectorate conducted 45 inspections in 30 of the group's entities in 2013. Of these, 10 concerned sites outside France and 7 were conducted following events or particular situations. These inspections gave rise to 176 recommendations, which the inspected entities have translated into action plans. Verification of these different action plans according to planned procedures and announced schedules gave rise to 16 follow-up inspections. The major lessons learned from these inspections relate to project management, facility compliance and operational

  1. 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....

  2. Safety for fuel assembly handling in the nuclear ship Mutsu

    International Nuclear Information System (INIS)

    Ando, Yoshio

    1978-01-01

    The safety for fuel assembly handling in the nuclear ship Mutsu is deliberated by the committee of general inspection and repair technique examination for Mutsu. The result of deliberation for both cases of removing fuel assemblies and keeping them in the reactor is outlined. The specification of fuel assemblies, and the nuclides and designed radioactivity of fission products of fuel are described. The possibility of shielding repair work and general safety inspection keeping the fuel assemblies in the reactor, the safety consideration when the fuel assemblies are removed at a quay, in a dry dock and on the ocean, the safety of fuel transport in special casks and fuel storage are explained. It is concluded finally that the safety of shielding repair work and general inspection work is secured when the fuel assemblies are kept in the reactor and also when the fuel assemblies are removed from the reactor by cautious working. (Nakai, Y.)

  3. Optimizing the design of international safeguards inspection systems

    International Nuclear Information System (INIS)

    Markin, J.T.; Coulter, C.A.; Gutmacher, R.G.; Whitty, W.J.

    1983-01-01

    Efficient implementation of international inspections for verifying the operation of a nuclear facility requires that available resources be allocated among inspection activities to maximize detection of misoperation. This report describes a design and evaluation method for selecting an inspection system that is optimal for accomplishing inspection objectives. The discussion includes methods for identifying system objectives, defining performance measures, and choosing between candidate systems. Optimization theory is applied in selecting the most preferred inspection design for a single nuclear facility, and an extension to optimal allocation of inspection resources among States containing multiple facilities is outlined. 3 figures, 5 tables

  4. Evaluation of structural welds with respect to reliability and inservice inspection

    International Nuclear Information System (INIS)

    Marci, G.

    1980-01-01

    The ongoing developments with respect to large forgings for nuclear pressure vessels and the present philosophy of inservice inspection in the Federal Republic of Germany (FRG) (inspection of weld regions only) seem to be oriented towards a monolithic pressure vessel requiring no inservice inspection. This raises questions as to the task of inservice inspection in the framework of the total reliability of a nuclear pressure vessel. The inherent 'weak spots' associated with welds of ferritic low alloyed steels are the microstructural features of stress relief cracks and regions of coarse grains. An analysis as to the effects of stress relief cracks and regions of coarse grains in the heat affected zones of welds on subcritical crack growth is performed. It is shown that these 'weak spots' cannot be considered a particular safety hazard to vessel integrity. Therefore welds per se should not constitute the criteria for the performance of inservice inspection. Rather, the inservice inspection programme should check the regions where manufacturing history, loading conditions, and materials degradation are expected to enhance subcritical crack growth. (author)

  5. NASA safety standard for lifting devices and equipment

    Science.gov (United States)

    1990-09-01

    NASA's minimum safety requirements are established for the design, testing, inspection, maintenance, certification, and use of overhead and gantry cranes (including top running monorail, underhung, and jib cranes), mobile cranes, derrick hoists, and special hoist supported personnel lifting devices (these do not include elevators, ground supported personnel lifts, or powered platforms). Minimum requirements are also addressed for the testing, inspection, and use of Hydra-sets, hooks, and slings. Safety standards are thoroughly detailed.

  6. China's nuclear safety regulatory body: The national nuclear safety administration

    International Nuclear Information System (INIS)

    Zhang Shiguan

    1991-04-01

    The establishment of an independent nuclear safety regulatory body is necessary for ensuring the safety of nuclear installations and nuclear fuel. Therefore the National Nuclear Safety Administration was established by the state. The aim, purpose, organization structure and main tasks of the Administration are presented. At the same time the practical examples, such as nuclear safety regulation on the Qinshan Nuclear Power Plant, safety review and inspections for the Daya Bay Nuclear Power Plant during the construction, and nuclear material accounting and management system in the nuclear fuel fabrication plant in China, are given in order to demonstrate the important roles having been played on nuclear safety by the Administration after its founding

  7. Optimal inspection planning for onshore pipelines subject to external corrosion

    International Nuclear Information System (INIS)

    Gomes, Wellison J.S.; Beck, André T.; Haukaas, Terje

    2013-01-01

    Continuous operation of pipeline systems involves significant expenditures in inspection and maintenance activities. The cost-effective safety management of such systems involves allocating the optimal amount of resources to inspection and maintenance activities, in order to control risks (expected costs of failure). In this context, this article addresses the optimal inspection planning for onshore pipelines subject to external corrosion. The investigation addresses a challenging problem of practical relevance, and strives for using the best available models to describe random corrosion growth and the relevant limit state functions. A single pipeline segment is considered in this paper. Expected numbers of failures and repairs are evaluated by Monte Carlo sampling, and a novel procedure is employed to evaluate sensitivities of the objective function with respect to design parameters. This procedure is shown to be accurate and more efficient than finite differences. The optimum inspection interval is found for an example problem, and the robustness of this optimum to the assumed inspection and failure costs is investigated. It is shown that optimum total expected costs found herein are not highly sensitive to the assumed costs of inspection and failure. -- Highlights: • Inspection, repair and failure costs of pipeline systems considered. • Optimum inspection schedule (OIS) obtained by minimizing total expected life-cycle costs. • Robustness of OIS evaluated w.r.t. estimated costs of inspection and failure. • Accurate non-conservative models of corrosion growth employed

  8. Extra environmental impact assessment and recommendable measures for their minimization in arranging sanitary inspection room site

    International Nuclear Information System (INIS)

    Rud'ko, V.M.; Batij, V.G.; Kuz'menko, V.A.; Paskevich, S.A.

    2003-01-01

    Environmental impact assessments during the works for preparation of sanitary inspection room site are presented. A range of measures to minimize environmental impact from the works to be implemented,is offered. Impacts on such environmental components as soil,air and aqueous medium,are considered

  9. Development of a remote inspection robot for high pressure structures

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jae C.; Kim, Jae H.; Choi, Yu R.; Moon, Soon S

    1999-10-01

    The high pressure structures in industrial plants must be periodically inspected for ensure their safety. Currently, the examination of them is manually performed by human inspectors, and there are many restrictions to examine the large containers which enclose dangerous chemicals or radioactive materials. We developed a remotely operated robot to examine these structures using recent mobile robot and computer technologies. Our robot has two magnetic caterpillars that make the robot can adhere to the structures made of steel like materials. The robot moves to the position for examination, and scans that position using ultrasonic probes equipped on it's arm, and transmits the result to the inspector according to his/her commands. Without building any auxiliary structures the robot can inspect the places where manual inspection can't reach. Therefore the robot can make shortening the inspection time as well as preventing the inspector from an accident. (author)

  10. Development of a remote inspection robot for high pressure structures

    International Nuclear Information System (INIS)

    Lee, Jae C.; Kim, Jae H.; Choi, Yu R.; Moon, Soon S.

    1999-10-01

    The high pressure structures in industrial plants must be periodically inspected for ensure their safety. Currently, the examination of them is manually performed by human inspectors, and there are many restrictions to examine the large containers which enclose dangerous chemicals or radioactive materials. We developed a remotely operated robot to examine these structures using recent mobile robot and computer technologies. Our robot has two magnetic caterpillars that make the robot can adhere to the structures made of steel like materials. The robot moves to the position for examination, and scans that position using ultrasonic probes equipped on it's arm, and transmits the result to the inspector according to his/her commands. Without building any auxiliary structures the robot can inspect the places where manual inspection can't reach. Therefore the robot can make shortening the inspection time as well as preventing the inspector from an accident. (author)

  11. Legal issues, authoritative licenses and tasks in relation with nuclear safety in Hungary

    International Nuclear Information System (INIS)

    Oerdoegh, J.; Voeroess, L.

    1998-01-01

    After a brief historical overview of nuclear authorities in Hungary, the role and functions of the National Atomic Energy Office are presented. It is the primary authority in this country on nuclear safety, with tasks and functions of licensing, inspection and enforcing safety measures. The organizational structure of NAEO and its position as a Governmental body is shown. Other tasks include the promotion of R and D coordination and international cooperation. (R.P.)

  12. Measurement techniques and safety culture in radiation protection -reflections after 37 years of occupation with measuring instruments

    International Nuclear Information System (INIS)

    Maushart, R.

    1994-01-01

    Safety Culture in radiation use and radiation protection implies primarily knowledge and competence of the decision makers. As the measuring techniques are basic for practical radiation protection, only such person can be called competent who has sufficient expertise on measuring techniques, and is able to evaluate its application and results. Safety Culture also implies the readiness to expose errors, and to learn from them. ''Believing in infallibility'' excludes Safety Culture. Therefore, correctly applied measuring technique contributes to recognize weak points early. How far it is used consciously and actively to prevent undesirable developments and exceeding of limits, can be considered outright as a yardstick for a high-ranking safety culture. Safety Culture as a whole, however, needs more than more measuring techniques. It requires its own and adequate Measurement Culture, presupposing also motivation and determination to measure. Therefore, education, training, knowledge and consciousness of safety of the people who are responsible for measurements are decisive for successful radiation protection. (orig.) [de

  13. 46 CFR 153.812 - Inspection for Certificate of Inspection.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 5 2010-10-01 2010-10-01 false Inspection for Certificate of Inspection. 153.812... CARGOES SHIPS CARRYING BULK LIQUID, LIQUEFIED GAS, OR COMPRESSED GAS HAZARDOUS MATERIALS Design and Equipment Testing and Inspection § 153.812 Inspection for Certificate of Inspection. The rules governing the...

  14. Grade pending: lessons for hospital quality reporting from the New York City restaurant sanitation inspection program.

    Science.gov (United States)

    Ryan, Andrew M; Detsky, Allan S

    2015-02-01

    Public quality reporting programs have been widely implemented in hospitals in an effort to improve quality and safety. One such program is Hospital Compare, Medicare's national quality reporting program for US hospitals. The New York City sanitary grade inspection program is a parallel effort for restaurants. The aims of Hospital Compare and the New York City sanitary inspection program are fundamentally similar: to address a common market failure resulting from consumers' lack of information on quality and safety. However, by displaying easily understandable information at the point of service, the New York City sanitary inspection program is better designed to encourage informed consumer decision making. We argue that this program holds important lessons for public quality reporting of US hospitals. © 2014 Society of Hospital Medicine.

  15. Human error considerations and annunciator effects in determining optimal test intervals for periodically inspected standby systems

    International Nuclear Information System (INIS)

    McWilliams, T.P.; Martz, H.F.

    1981-01-01

    This paper incorporates the effects of four types of human error in a model for determining the optimal time between periodic inspections which maximizes the steady state availability for standby safety systems. Such safety systems are characteristic of nuclear power plant operations. The system is modeled by means of an infinite state-space Markov chain. Purpose of the paper is to demonstrate techniques for computing steady-state availability A and the optimal periodic inspection interval tau* for the system. The model can be used to investigate the effects of human error probabilities on optimal availability, study the benefits of annunciating the standby-system, and to determine optimal inspection intervals. Several examples which are representative of nuclear power plant applications are presented

  16. Comprehensive review of the maritime safety regimes.

    NARCIS (Netherlands)

    S. Knapp (Sabine); Ph.H.B.F. Franses (Philip Hans)

    2007-01-01

    textabstractThis report presents a comprehensive review of the maritime safety regimes and provides recommendations on how to improve the system. The results show a complex legal framework which generates a high amount of inspections and overlapping of inspection areas where no cross-recognition is

  17. Multiparty Evolutionary Game Model in Coal Mine Safety Management and Its Application

    Directory of Open Access Journals (Sweden)

    Rongwu Lu

    2018-01-01

    Full Text Available Coal mine safety management involves many interested parties and there are complex relationships between them. According to game theory, a multiparty evolutionary game model is established to analyze the selection of strategies. Then, a simplified three-party model is taken as an example to carry out detailed analysis and solution. Based on stability theory of dynamics system and phase diagram analysis, this article studies replicator dynamics of the evolutionary model to make an optimization analysis of the behaviors of those interested parties and the adjustment mechanism of safety management policies and decisions. The results show how the charge of supervision of government department and inspection of coal mine enterprise impact the efficiency of safety management and the effect of constraint measures and incentive and other measures in safety management.

  18. Measuring safety climate in elderly homes.

    Science.gov (United States)

    Yeung, Koon-Chuen; Chan, Charles C

    2012-02-01

    Provision of a valid and reliable safety climate dimension brings enormous benefits to the elderly home sector. The aim of the present study was to make use of the safety climate instrument developed by OSHC to measure the safety perceptions of employees in elderly homes such that the factor structure of the safety climate dimensions of elderly homes could be explored. In 2010, surveys by mustering on site method were administered in 27 elderly homes that had participated in the "Hong Kong Safe and Healthy Residential Care Home Accreditation Scheme" organized by the Occupational Safety and Health Council. Six hundred and fifty-one surveys were returned with a response rate of 54.3%. To examine the factor structure of safety climate dimensions in our study, an exploratory factor analysis (EFA) using principal components analysis method was conducted to identify the underlying factors. The results of the modified seven-factor's safety climate structure extracted from 35 items better reflected the safety climate dimensions of elderly homes. The Cronbach alpha range for this study (0.655 to 0.851) indicated good internal consistency among the seven-factor structure. Responses from managerial level, supervisory and professional level, and front-line staff were analyzed to come up with the suggestion on effective ways of improving the safety culture of elderly homes. The overall results showed that managers generally gave positive responses in the factors evaluated, such as "management commitment and concern to safety," "perception of work risks and some contributory influences," "safety communication and awareness," and "safe working attitude and participation." Supervisors / professionals, and frontline level staff on the other hand, have less positive responses. The result of the lowest score in the factors - "perception of safety rules and procedures" underlined the importance of the relevance and practicability of safety rules and procedures. The modified OSHC

  19. Safety measuring for sodium handling

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Ji Young; Jeong, K C; Kim, T J; Kim, B H; Choi, J H

    2001-09-01

    This is the report for the safety measures of sodium handling. These contents are prerequisites for the development of sodium technology and thus the workers participate in sodium handling and experiments have to know them perfectly. As an appendix, the relating parts of the laws are presented.

  20. Safety culture in nuclear installations - The role of the regulator

    International Nuclear Information System (INIS)

    Karigi, Alice W.

    2002-01-01

    Safety culture is an amalgamation of values, standards, morals and norms of acceptable behavior by the licensees, Radiation workers and the Regulator. The role played by a Regulator in establishing safety culture in a nuclear installation is that related to Authorization, review, assessment, inspection and enforcement. The regulator is to follow the development of a facility or activity from initial selection of the site through design, construction, commissioning, radioactive waste management through to decommissioning and closure. He is to ensure safety measures are followed through out the operation of the facility by laying down in the license conditions of controlling construction of nuclear installations and ensuring competence of the operators. (author)

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