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Sample records for equipment qualification program

  1. Equipment qualification research program: program plan

    International Nuclear Information System (INIS)

    Dong, R.G.; Smith, P.D.

    1982-01-01

    The Lawrence Livermore National Laboratory (LLNL) under the sponsorship of the US Nuclear Regulatory Commission (NRC) has developed this program plan for research in equipment qualification (EQA). In this report the research program which will be executed in accordance with this plan will be referred to as the Equipment Qualification Research Program (EQRP). Covered are electrical and mechanical equipment under the conditions described in the OBJECTIVE section of this report. The EQRP has two phases; Phase I is primarily to produce early results and to develop information for Phase II. Phase I will last 18 months and consists of six projects. The first project is program management. The second project is responsible for in-depth evaluation and review of EQ issues and EQ processes. The third project is responsible for detailed planning to initiate Phase II. The remaining three projects address specific equipment; i.e., valves, electrical equipment, and a pump

  2. Environmental/dynamic mechanical equipment qualification and dynamic electrical equipment qualification program (EDQP)

    International Nuclear Information System (INIS)

    Hunter, J.A.

    1984-01-01

    Equipment qualification research is being conducted to investigate acceptable criteria, requirements, and methodologies for the dynamic (including seismic) and environmental qualification of mechanical equipment and for the dynamic (including seismic) qualification of electrical equipment. The program is organized into three elements: (1) General Research, (2) Environmental Research, and (3) Dynamic Research. This paper presents the highlights of the results to date in these three elements of the program

  3. Electrical equipment qualification

    International Nuclear Information System (INIS)

    Farmer, W.S.

    1983-01-01

    Electrical equipment qualification research programs being carried out by CEA, JAERI, and Sandia Laboratories are discussed. Objectives of the program are: (1) assessment of accident simulation methods for electrical equipment qualification testing; lower coarse (2) evaluation of equipment aging and accelerated aging methods; (3) determine radiation dose spectrum to electrical equipment and assess simulation methods for qualification; (4) identify inadequacies in electrical equipment qualification procedures and standards and potential failure modes; and (5) provide data for verifying and improving standards, rules and regulatory guides

  4. Environmental qualification program of electric equipment for Angra 1

    International Nuclear Information System (INIS)

    Muzitano, Grazielle F.; Justino, Marcelo C.; Silva, Marcos C.

    2017-01-01

    This paper describes the development of the environmental qualification program for important electrical equipment (EQPEE) used for safety in Angra 1 Nuclear Power Plant (NPP). The environmental qualification program started in United States of America by the Nuclear Regulatory Commission (NRC) after the Three Mile Island (TMI) Nuclear Power Plant Accident in 1979. In that event, some equipment installed inside the reactor containment of TMI failed due the harsh conditions that occurred after the accident. Because of this fact, the NRC issued the Regulation 50.49 'Environmental qualification of electric equipment important to safety for nuclear power plants'. The Brazilian regulatory commission CNEN also asked Angra 1 to follow this regulation and to implement an EQPEE similar to the programs adopted by American and other NPPs around the world. Due to the importance to maintain the critical equipment operating in normal and abnormal environment conditions, the program aims to assure that this equipment remains qualified to work under the harsh conditions found inside the reactor containment. The aging of these components are also analyzed in this program that is important in the process to extend the operating life of Angra 1 for more 20 years, which is normally referred as Long Term Operation (LTO). (author)

  5. Environmental qualification program of electric equipment for Angra 1

    Energy Technology Data Exchange (ETDEWEB)

    Muzitano, Grazielle F.; Justino, Marcelo C.; Silva, Marcos C., E-mail: grazi@eletronuclear.gov.br, E-mail: justino@eletronuclear.gov.br, E-mail: candeia@eletronuclear.gov.br [Eletrobras Termonuclear S.A. (ELETRONUCLEAR), Rio de Janeiro, RJ (Brazil)

    2017-11-01

    This paper describes the development of the environmental qualification program for important electrical equipment (EQPEE) used for safety in Angra 1 Nuclear Power Plant (NPP). The environmental qualification program started in United States of America by the Nuclear Regulatory Commission (NRC) after the Three Mile Island (TMI) Nuclear Power Plant Accident in 1979. In that event, some equipment installed inside the reactor containment of TMI failed due the harsh conditions that occurred after the accident. Because of this fact, the NRC issued the Regulation 50.49 'Environmental qualification of electric equipment important to safety for nuclear power plants'. The Brazilian regulatory commission CNEN also asked Angra 1 to follow this regulation and to implement an EQPEE similar to the programs adopted by American and other NPPs around the world. Due to the importance to maintain the critical equipment operating in normal and abnormal environment conditions, the program aims to assure that this equipment remains qualified to work under the harsh conditions found inside the reactor containment. The aging of these components are also analyzed in this program that is important in the process to extend the operating life of Angra 1 for more 20 years, which is normally referred as Long Term Operation (LTO). (author)

  6. Program plan for environmental qualification of mechanical and dynamic (including seismic) qualification of mechanical and electrical equipment program (EDQP)

    International Nuclear Information System (INIS)

    Weidenhamer, G.H.

    1986-06-01

    The equipment qualification program described in this plan is intended to provide the technical basis for resolving uncertainties in existing equipment qualification standards. In addition, research results are contributing to the resolution of safety issues GI-23, GI-87, USI-A44, titled, ''Reactor Coolant Pump Seal Failure,'' ''Failure of HPCI Steam Line Without Isolation,'' and ''Station Blackout,'' respectively. Also, research effort is being directed at providing information on the behavior of containment isolation valves under severe accident environments. Although the results of the latter research will not contribute to resolving uncertainties in qualification standards, it has proven cost effective to obtain this information under this program

  7. Seismic qualification of equipment

    International Nuclear Information System (INIS)

    Heidebrecht, A.C.; Tso, W.K.

    1983-03-01

    This report describes the results of an investigation into the seismic qualification of equipment located in CANDU nuclear power plants. It is particularly concerned with the evaluation of current seismic qualification requirements, the development of a suitable methodology for the seismic qualification of safety systems, and the evaluation of seismic qualification analysis and testing procedures

  8. Research program for seismic qualification of nuclear plant electrical and mechanical equipment. Task 3. Recommendations for improvement of equipment qualification methodology and criteria. Volume 3

    International Nuclear Information System (INIS)

    Kana, D.D.; Pomerening, D.J.

    1984-08-01

    The Research Program for Seismic Qualification of Nuclear Plant Electrical and Mechanical Equipment has spanned a period of three years and resulted in seven technical summary reports, each of which covered in detail the findings of different tasks and subtasks, and have been combined into five NUREG/CR volumes. Volume 3 presents recommendations for improvement of equipment qualification methodology and procedural clarification/modification. The fifth category identifies issues where adequate information does not exist to allow a recommendation to be made

  9. Challenges of equipment qualification using today's standards with emphasis on a class 1E motor program

    International Nuclear Information System (INIS)

    Deaton, K.

    1995-01-01

    This paper describes qualification of new equipment for safety related service in the nuclear power industry in accordance with current industry standards. This topic is presented from the perspective of an original equipment manufacturer J(OEM). Equipment qualification is first discussed in a general way then an example is provided of an electric motor qualification. A review of alternative qualification methods including commercial dedication is included. Potential difficulties with alternative/expedited qualification methods are also discussed

  10. The french safety approach regarding equipment qualification

    International Nuclear Information System (INIS)

    Jalouneix, J.; Deletre, G.; Henry, J.Y.; Rousseau, L.

    1989-10-01

    The qualification of the equipment, used in France on nuclear reactors and reactor components, is discussed. The approach on safety involves the qualification of mechanical and electrical components, under operating and under seismic conditions. The principles of the qualification program and the list of the equipment concerned, are given. The conditions in which qualification tests are performed and the methods applied, are summarized. The actions for preserving the qualification procedures, are considered

  11. Return of IEEE Std 627 and its Value to Equipment Qualification Programs

    International Nuclear Information System (INIS)

    Horvath, D.A.

    2012-01-01

    IEEE Std 627 ''Design Qualification of Safety Systems Equipment Used in Nuclear Power Generating Stations'' was issued to more generically establish qualification requirements in the form of a high level umbrella document. Efforts on this standard began in late 1975 at the request of the IEEE Nuclear Standards Management Board. In 1977 a joint ASME/IEEE agreement established responsibility for qualification and quality assurance standards preparation. ASME accepted responsibility for Quality Assurance and IEEE for qualification. In accordance with that agreement, IEEE completed the generic qualification standard in 1980. This document provided high level approaches, criteria, guidance, and principles for qualification of both electrical and mechanical equipment that at that time appeared in no other industry standard. IEEE Std 627-1980 was later reaffirmed in 1996. In 1986, ASME's Board on Nuclear Codes and Standards directed its Committee on Qualification of Mechanical Equipment (QME) to develop a standard for qualifying mechanical equipment. This task was completed in several parts during the time frame from 1992 to 1994. Partly in response to this activity, IEEE Std 627 was withdrawn in 2002. Later although withdrawn, it was found that IEEE Std 627 was continuing to be used and referenced by many entities both in the US and other countries including in ASME's QME-1-2002 ''Qualification of Active Mechanical Equipment Used in Nuclear Power Plants'', US NRC's NUREG-0800 Standard Review Plan Section 3.11, at least one reactor vendor's Design Certification Document (DCD), several international licensing documents, and elsewhere. As a result, in 2007, the IEEE Standards Board authorized Working Group 2.10 of Subcommittee 2 (Qualification) of the Power and Energy Society's Nuclear Power Engineering Committee to resurrect and update IEEE Std 627-1980 (Reaff 1996). The result was the culmination IEEE Std 627 in 2010. This paper will report on the eight improvements made

  12. Summary of work completed under the Environmental and Dynamic Equipment Qualification research program (EDQP)

    International Nuclear Information System (INIS)

    Steele, R. Jr.; Bramwell, D.L.; Watkins, J.C.; DeWall, K.G.

    1994-02-01

    This report documents the results of the main projects undertaken under the Environmental and Dynamic Equipment Qualification Research Program (EDQP) sponsored by the U.S. Nuclear Regulatory Commission (NRC) under FIN A6322. Lasting from fiscal year 1983 to 1987, the program dealt with environmental and dynamic (including seismic) equipment qualification issues for mechanical and electromechanical components and systems used in nuclear power plants. The research results have since been used by both the NRC and industry. The program included seven major research projects that addressed the following issues: (a) containment purge and vent valves performing under design basis loss of coolant accident loads, (b) containment piping penetrations and isolation valves performing under seismic loadings and design basis and severe accident containment wall displacements, (c) shaft seals for primary coolant pumps performing under station blackout conditions, (d) electrical cabinet internals responding to in-structure generated motion (rattling), and (e) in situ piping and valves responding to seismic loadings. Another project investigating whether certain containment isolation valves will close under design basis conditions was also started under this program. This report includes eight main section, each of which provides a brief description of one of the projects, a summary of the findings, and an overview of the application of the results. A bibliography lists the journal articles, papers, and reports that document the research

  13. Selection of equipment for equipment qualification

    International Nuclear Information System (INIS)

    Torr, K.G.

    1989-01-01

    This report describes the methodology applied in selecting equipment in the special safety systems for equipment qualification in the CANDU 600 MW nuclear generating stations at Gentilly 2 and Point Lepreau. Included is an explanation of the selection procedure adopted and the rationale behind the criteria used in identifying the equipment. The equipment items on the list have been grouped into three priority categories as a planning aid to AECB staff for a review of the qualification status of the special safety systems

  14. Changing nature of equipment and parts qualification

    International Nuclear Information System (INIS)

    Bucci, R.M.

    1988-01-01

    Ideally, the original supplier of a piece of nuclear safety-related equipment has performed a qualification program and will continue to support that equipment throughout the lifetime of the nuclear power plants in which in equipment is installed. The supplier's nuclear quality assurance program will be maintained and he will continue to offer all necessary replacement parts. These parts will be identical to the original parts, certified to the original purchase order requirements, and the parts will be offered at competitive prices. Due to the changing nature of the nuclear plant equipment market, however, one or more of those ideal features are frequently unavailable when safety-related replacement equipment or parts are required. Thus, the process of equipment and parts qualification has had to adjust in order to ensure obtaining qualified replacements when needed. This paper presents some new directions taken in the qualification of replacement equipment and parts to meet changes in the marketplace

  15. Challenges of equipment qualification using today`s standards with emphasis on a class 1E motor program

    Energy Technology Data Exchange (ETDEWEB)

    Deaton, K.

    1995-02-01

    This paper describes qualification of new equipment for safety related service in the nuclear power industry in accordance with current industry standards. This topic is presented from the perspective of an original equipment manufacturer J(OEM). Equipment qualification is first discussed in a general way then an example is provided of an electric motor qualification. A review of alternative qualification methods including commercial dedication is included. Potential difficulties with alternative/expedited qualification methods are also discussed.

  16. Research program for seismic qualification of nuclear plant electrical and mechanical equipment. Task 4. Use of fragility in seismic design of nuclear plant equipment. Volume 4

    International Nuclear Information System (INIS)

    Kana, D.D.; Pomerening, D.J.

    1984-08-01

    The Research Program for Seismic Qualification of Nuclear Plant Electrical and Mechanical Equipment has spanned a period of three years and resulted in seven technical summary reports, each of which have covered in detail the findings of different tasks and subtasks, and have been combined into five NUREG/CR volumes. Volume 4 presents study of the use of fragility concepts in the design of nuclear plant equipment and compares the results of state-of-the-art proof testing with fragility testing

  17. Equipment qualification testing methodology research at Sandia Laboratories

    International Nuclear Information System (INIS)

    Jeppesen, D.

    1983-01-01

    The Equipment Qualification Research Testing (EQRT) program is an evolutionary outgrowth of the Qualification Testing Evaluation (QTE) program at Sandia. The primary emphasis of the program has been qualification methodology research. The EQRT program offers to the industry a research-oriented perspective on qualification-related component performance, as well as refinements to component testing standards which are based upon actual component testing research

  18. Equipment qualification testing - a practical approach

    International Nuclear Information System (INIS)

    Davies, G.A.; McDougall, R.I.; Poirier, M.P.

    1996-01-01

    When nuclear safety equipment is credited with a Required Safety Function it must properly perform that function to facilitate safe control and/or shutdown of the plant during a design basis accident. When such equipment is required to be environmentally (EQ) and/or seismically qualified (SQ) for safety related use in CANDU nuclear power plants, the preferred method of qualification is by type testing. The qualification testing process requires that the test specimen equipment be subjected to the aging stressors associated with the normal service conditions that it would experience during it's required qualified (or service) life. Following the aging process, the test specimen is in a condition representative of that in which it would be at the end of its service life in the plant. The test specimen is then subjected to a simulated accident during which it must satisfy performance requirements thereby demonstrating that it can perform its required safety function. The performance requirements specified for the qualification testing must be designed to ensure that satisfactory performance of the safety function is demonstrated during the qualification program. This paper provides descriptions of practical methods used in the deriving and satisfying of relevant performance requirements during the qualification testing of safety related equipment. (author)

  19. Progress on EPRI electrical equipment qualification research

    International Nuclear Information System (INIS)

    Sliter, G.E.

    1983-01-01

    The objective of EPRI's electrical equipment qualification research program is to provide technical assistance to utilities in meeting nuclear plant safety requirements in a manner consistent with the state of the art. This paper reports progress on several research projects including: radiation effects studies, which compile data on degradation of organic materials in electrical equipment exposed to operational and accident radiation doses; the Equipment Qualification Data Bank, which is a remotely accessible computer system for disseminating qualification information on in-plant equipment, seismic data, and materials data; an aging/seismic correlation program, which is providing test data showing that, in many cases, age degradation has a negligibly small effect on the performance of electrical components under seismic excitation; a review of condition monitoring techniques, which has identified surveillance methods for measuring key performance parameters that have the potential for predicting remaining equipment life; and large-scale hydrogen burn equipment response tests, which are providing data to assess the ability of equipment to remain functional during and after hydrogen burning in postulated degraded core accidents

  20. Total qualification of class 1E electric equipment

    International Nuclear Information System (INIS)

    Chauvin, G.

    1982-09-01

    For nuclear power plant projects in France, Framatome and its partners Electricite de France (EDF) and the Commissariat a l'Energie Atomique (CEA) have responded to the present qualification context by implementing a wide-ranging qualification program to acquire significant organizational and practical experience. The following sections detail Framatome's approach to the activities of an organization mandated to provide a complete spectrum of qualification services. Thorough implementation of a Class 1E electric equipment qualification program by the competent organization or qualifier entails completion of three consecutive steps: 1) program preparation, 2) program implementation, and 3) analysis of test results and conclusion. The qualifier assumes extensive responsibility for each of these steps. The following sections present test facilities used in France to conduct a total qualification program for Class 1E electric equipment

  1. Ageing management and equipment qualification

    International Nuclear Information System (INIS)

    Stahl, Gunnar

    2014-01-01

    The knowledge of how the environment and load of organic material in general and especially polymers and lubricants, is affecting the degradation of important properties, have increased during the last decade. However the restrictions using established additives like some color pigments due to their poisonousness e.g. pigments based at cadmium, lead, mercury etc. have caused problems when replacing additives to polymers. The replacement additives have often been used in new design without going through the required material qualification procedure. There have also been observed that some non-qualified and non-approved materials have been installed in some power plants due to false documentation. There are also a lot of new manufacturers, of materials similar to the previously qualified materials, active at the market. This increases the difficulty to ensure that the required material quality is used. New materials, new additives and new manufacturers makes if more and more difficult to assure that the expected material is present. This causes more strict demands of how the new materials often used in equipment at type-testing and in replacement materials are analyzed and documented. By implementing new steps for chemical, mechanical and electrical analysis and increase the general quality assurance content this issue can be managed. (authors)

  2. Similarity principles for equipment qualification by experience

    International Nuclear Information System (INIS)

    Kana, D.D.; Pomerening, D.J.

    1988-07-01

    A methodology is developed for seismic qualification of nuclear plant equipment by applying similarity principles to existing experience data. Experience data are available from previous qualifications by analysis or testing, or from actual earthquake events. Similarity principles are defined in terms of excitation, equipment physical characteristics, and equipment response. Physical similarity is further defined in terms of a critical transfer function for response at a location on a primary structure, whose response can be assumed directly related to ultimate fragility of the item under elevated levels of excitation. Procedures are developed for combining experience data into composite specifications for qualification of equipment that can be shown to be physically similar to the reference equipment. Other procedures are developed for extending qualifications beyond the original specifications under certain conditions. Some examples for application of the procedures and verification of them are given for certain cases that can be approximated by a two degree of freedom simple primary/secondary system. Other examples are based on use of actual test data available from previous qualifications. Relationships of the developments with other previously-published methods are discussed. The developments are intended to elaborate on the rather broad revised guidelines developed by the IEEE 344 Standards Committee for equipment qualification in new nuclear plants. However, the results also contribute to filling a gap that exists between the IEEE 344 methodology and that previously developed by the Seismic Qualification Utilities Group. The relationship of the results to safety margin methodology is also discussed. (author)

  3. Establishment of nuclear equipment qualification system

    International Nuclear Information System (INIS)

    Joo, Po Kook; Lim, Nam Jin; Lee, Young Gun

    2003-04-01

    This study is carried out by KEARI(Korea Atomic Energy Research Institute) as the lead organization in cooperation with KIMM(Korea Institute of Machinery and Materials), KTL(Korea Testing Laboratory) and KRISS(Korea Research Institute of Standards and Science) to construct a basis of efficient management of nuclear equipment qualification business by expanding test equipment of each of participating organization, and developing qualification technologies. As for KIMM, control system of large scale shaker was replaced with advanced system, and LOCA(Loss of Coolant Accident) test facility was installed. KTL is now capable of conducting seismic tests of nuclear I and C as a result of installation of seismic test equipment during the first two project years. KRISS participated in the Project with a view to have large scale EMI test equipment and related technologies. In parallel with expansion of test equipment, a industrial-educational-research cooperation committee, as an intermediate step toward integrated equipment qualification system to maximize the usage of test equipment, was established and cooperation methods were investigated. As a result, Korea Nuclear Equipment Qualification Association, an corporate juridical person, was established. Research on development of thermal and radiation aging test technology of nuclear materials was carried out by Hanyang University and SECO(Saehan Engineering and Qualification Co., Ltd.). Integrated Equipment Qualification Database was developed which contains material test data, equipment qualification data and other EQ related informations. Standard qualification procedures were developed in order for test laboratories and manufacturers to establish design requirements and to efficiently perform tests

  4. Equipment Qualification Data Base user manual

    International Nuclear Information System (INIS)

    Decker, Q.R.; Fackrell, L.J.; Fitch, L.R.; Meeky, O.B.

    1985-09-01

    This manual details the Equipment Qualification Data Base (EQDB), its usage, and contents. The EQDB consists of two files; the Plant Qualification File (PQF) and the Equipment Qualification File (EQF). The PQF contains plant specific environmental data and the EQF contains summaries of various test results. Two data management systems are used to manipulate the data and are discussed in this manual. SAS Institute System 2000 (S2K) is the management system for the PQF and Query Update (QU) is the operating system for the EQF. Each management system contains report writers. These writers and how to use them are discussed in detail in this manual

  5. Benefits of Digital Equipment Generic Qualification Activities

    International Nuclear Information System (INIS)

    Thomas, James E.; Steiman, Samuel C.

    2002-01-01

    As a result of nuclear power plant instrumentation and control obsolescence issues, there have been numerous activities during recent years relating to the qualification of digital equipment. Some of these activities have been 'generic' in nature in that the qualification was not limited to plant specific applications, but was intended to cover a broad base of potential applications of the digital equipment. These generic qualifications have been funded by equipment manufacturers and by utility groups and organizations. The generic activities sponsored by the Electric Power Research Institute (EPRI) have been pilot projects for an overall generic qualification approach. The primary benefit resulting from the generic qualification work to date is that a number of digital platforms and digital devices are now available for use in various nuclear safety-related applications. Many of the tests and evaluations necessary to support plant specific applications have been completed. The amount of data and documentation that each utility must develop on a case by case basis has been significantly reduced. There are also a number of additional benefits resulting from these industry efforts. The challenges and difficulties in qualifying digital equipment for safety-related applications are now more clearly understood. EPRI has published a lessons learned document (EPRI Report 1001452, Generic Qualification of Commercial Grade Digital Devices: Lessons Learned from Initial Pilots, which covers several different qualification areas, including device selection, project planning, vendor surveys and design reviews, and electromagnetic compatibility (EMC) qualification. Application of the experience and lessons learned from the EPRI pilot activities should help reduce the effort and cost required for future qualification work. Most generic qualification activities for commercial equipment have been conducted using the approach of EPRI TR-106439, Guideline on Evaluation and Acceptance

  6. Environmental qualification program for new designs

    International Nuclear Information System (INIS)

    Doerffer, K.

    2007-01-01

    Qualification of nuclear power plant equipment and components important to safety (ITS) is an integral part of the design process. The qualification methodology differs based on the severity of service conditions (operational and ambient), to which the ITS equipment is exposed. In Canada, the licensing requirements for environmental qualification for new designs are governed by the Canadian Standard Association (CSA) standard, N290.13-2005 titled 'Environmental Qualification of Equipment for CANDU Nuclear Power Plants' and the pre-consultation draft, 'Requirements for Design of Nuclear Power Plants'(DRD), issued for trial use by the Canadian Nuclear Safety Commission (CNSC) in March 2005. This paper will describe AECL's current Environmental Qualification program developed to comply with the above licensing requirements as applied to new designs. The focus will be given to qualification of ITS systems structures and components (SSC) to harsh conditions occurring due to the Design Basis Accidents (DBA). (author)

  7. Implications of NUREG-1150 for equipment qualification

    International Nuclear Information System (INIS)

    Siu, R.P.; Sarram, M.

    1988-01-01

    Current USNRC regulations in 10CFR50 requires that structures, systems and components important to safety in a nuclear power plant are to be designed to accommodate the effects of harsh environments associated with potential accidents. Detailed regulatory requirements are as discussed in Regulatory Guide 1.89. Some of these regulatory requirements have been based upon rather outdated understanding of the phenomenology of severe accidents -- e.g., the radiation source terms for equipment qualification can be traced to TID-14844 which was originally published in 1962. Furthermore, the definition of important-to-safety in these regulatory requirements is rather broad, usually resulting in a long Q-list of equipment to be qualified for the design-basis Large LOCA. In the past few years, extensive research/analysis on severe accidents have been conducted -- from the IREP/NREP activities, the IDCOR programs, to the NUREG-1150 efforts. This paper reports that as a result of all these PRA-related activities, a much-improved understanding of the phenomenology and environmental conditions associated with severe accidents has been gained

  8. Development of nuclear equipment qualification technology

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Heon O; Kim, Wu Hyun; Kim, Jin Wuk; Kim, Jeong Hyun; Lee, Jeong Kyu; Kim, Yong Han; Jeong, Hang Keun [Korea Institute of Machinery and Materials, Taejon (Korea)

    1999-03-01

    In order to enhance testing and evaluation technologies, which is one of the main works of the Chanwon branch of KIMM(Korea Institute of Machinery and Materials), in addition to the present work scope of the testing and evaluation in the industrial facilities such as petroleum and chemical, plants, the qualification technologies of the equipments important to safety used in the key industrial facilities such as nuclear power plants should be localized: Equipments for testing and evaluation is to be set up and the related technologies must be developed. In the first year of this study, of vibration aging qualification technologies of equipments important to safety used in nuclear power plants have been performed. (author). 27 refs., 81 figs., 17 tabs.

  9. Instrumentation qualification. Seismic qualification of C-E instrumentation equipment. Part One

    International Nuclear Information System (INIS)

    1977-05-01

    A summary of the C-E seismic qualification program utilized to demonstrate the seismic design adequacy of the instrumentation and control equipment used in C-E supplied Nuclear Steam Supply Systems (NSSS) is presented. The report is divided into two parts. Part One includes the equipment seismic requirements and a description of the qualification methods. Part Two lists the specific equipment by nuclear station in which it is used and the equipment test results are summarized in a standard data sheet format to facilitate review. The seismic requirements are based on individual contract commitments with C-E customers and the NRC Standard Review Plan, Section 3.10 ''Seismic Qualification of Category I Instrumentation and Electrical Equipment.'' Equipment is qualified for use in a seismic environment where damage potential to the equipment is less than or equal to that simulated seismic environment to which it has been qualified. The anticipated Safe Shutdown Earthquake (SSE) environment at the inservice location of equipment should be confirmed by each applicant as not exceeding that to which it is qualified

  10. Environmental qualification program for Wolsong project

    International Nuclear Information System (INIS)

    Duggal, A.; Johal, H.; Yee, F.; Suh, S.K.

    1995-01-01

    The Wolsong EQ Program is a process that begins at the design concept stage and continues throughout the operating life of the station. As all components may not have a 30 year service life without periodic maintenance, the EQ Program becomes an important management tool for the owner of the plant. First, the environmental conditions are predicted for the postulated events. Next, suitably qualified equipment is specified and procured. Then the equipment is installed according to specific instructions. Finally, by means of ongoing maintenance and replacement of parts, the qualification of the equipment is maintained during the operating life of the plant. Proper documentation and traceability is required at all stages of the program. As defined in the Wolsong Project Environmental Qualification Design Guide a comprehensive Environmental Qualification (EQ) Program ensures that safety related equipment located in an area in which a harsh environment could occur, can function when required for the life of the station . This program was implemented at the beginning of the Wolsong project. Using this program, components/equipment are qualified prior to installation and a maintenance program is established to keep equipment 'qualified' throughout the station life

  11. Qualification of electrical equipment. A United States nuclear system supplier perspective

    International Nuclear Information System (INIS)

    Jordan, W.G.

    1978-01-01

    At Westinghouse Pressurized Water Reactor Systems Division (PWR-SD) qualification. of safety related electrical equipment can be segregated into three distinct generations: (1) the initial seismic and environmental qualification programs for electrical equipment (1969-1972); (2) the supplemental sismic and environmental qualification programs (1975-1977); and (3) the seismic and environmental qualification programs to meet IEEE-323-1974, IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations''(1975). The latter two programs (in a licensing framework), as they are most current, with emphasis on electrical equipment (e.g. transmitters, rack mounted equipment) as opposed to electro-mechanical equipment (valve operators, pump motors) are reviewed. (author)

  12. Seismic qualification of non-safety class equipment whose failure would damage safety class equipment

    International Nuclear Information System (INIS)

    LaSalle, F.R.

    1991-01-01

    Both Code of Federal Regulations, Title 10, Part 50, and US Department of Energy Order 6340.1A have requirements to assess the interaction of non-safety and safety class structures and equipment during a seismic event to maintain the safety function. At the Hanford Site, a cost effective program has been developed to perform the evaluation of non-safety class equipment. Seismic qualification is performed by analysis, test, or upgrading of the equipment to ensure the integrity of safety class structures and equipment. This paper gives a brief overview and synopsis that address design analysis guidelines including applied loading, damping values, component anchorage, allowable loads, and stresses. Test qualification of equipment and walkdown acceptance criteria for heating ampersand ventilation (H ampersand V) ducting, conduit, cable tray, missile zone of influence, as well as energy criteria are presented

  13. Unresolved Safety Issue A-46 - seismic qualification of equipment in operating plants

    International Nuclear Information System (INIS)

    Anderson, N.

    1985-01-01

    Seismic Qualification of Equipment in Operating Plants was designated as an Unresolved Safety Issue (USI) in December, 1980. The USI A-46 program was developed in early 1981 to investigate the adequacy of mechanical and electrical equipment in operating plants to withstand a safe shutdown earthquake. The approach taken was to develop viable, cost effective alternatives to current seismic qualification licensing requirements which could be applied to operating nuclear power plants. The tasks investigated include: (1) identification of seismic sensitive systems and equipment; (2) assessment of adequacy of existing seismic qualification methods; (3) development and assessment of in-situ test procedures to assist in qualification of equipment; (4) seismic qualification of equipment using seismic experience data; and (5) development of methods to generate generic floor response spectra. Progress to date and plans for completion of resolution are reported

  14. IEEE standard for design qualification of safety systems equipment used in nuclear power generating stations

    International Nuclear Information System (INIS)

    Anon.

    1980-01-01

    This standard is written to serve as a general standard for qualification of all types of safety systems equipment, mechanical and instrumentation as well as electrical. It also establishes principles and procedures to be followed in preparing specific safety systems equipment standards. Guidance for qualifying specific safety systems equipment may be found in various specific equipment qualification standards that are now available or are being prepared. It is required that safety systems equipment in nuclear power generating stations meet or exceed its performance requirements throughout its installed life. This is accomplished by a disciplined program of design qualification and quality assurance of design, production, installation, maintenance and surveillance. This standard is for the design qualification section of the program only. Design qualification is intended to demonstrate the capability of the equipment design to perform its safety function(s) over the expected range of normal, abnormal, design basis event, post design basis event, and in-service test conditions. Inherent to design qualification is the requirement for demonstration, within limitations afforded by established technical state-of-the-art, that in-service aging throughout the qualified life established for the equipment will not degrade safety systems equipment from its original design condition to the point where it cannot perform its required safety function(s), upon demand. The above requirement reflects the primary role of design qualification to provide reasonable assurance that design- and age-related common failure modes will not occur during performance of safety function(s) under postulated service conditions

  15. Similarity principles for seismic qualification of equipment by experience data

    International Nuclear Information System (INIS)

    Kana, D.D.; Pomerening, D.J.

    1989-01-01

    A methodology is developed for seismic qualification of nuclear plant equipment by applying similarity principles to existing experience data. Experience data is that available from previous qualifications by analysis or testing, or from actual earthquake events. Similarity principles are defined in terms of excitation, equipment physical characteristics, and equipment response. Physical similarity is further defined in terms of a critical transfer function for response at a location on a primary structure, whose response can be assumed directly related to fragility of the item under elevated levels of excitation. Procedures are developed for combining experience data into composite specifications for qualification of equipment that can be shown to be physically similar to the reference equipment. Other procedures are developed for extending qualifications beyond the original specifications under certain conditions. Some examples for application and verification of the procedures are given for actual test data available from previous qualifications. The developments are intended to elaborate on the rather broad guidelines by the IEEE 344 Standards Committee for equipment qualification in new nuclear plants. The results also contribute to filling a gap that exists between the IEEE 344 methodology and that which was previously developed for equipment in existing plants by the Seismic Qualification Utilities Group. 10 refs., 9 figs., 1 tab

  16. Workshop on environmental qualification of electric equipment

    International Nuclear Information System (INIS)

    Lofaro, R.; Gunther, W.; Villaran, M.; Lee, B.S.; Taylor, J.

    1994-05-01

    Questions concerning the Environmental Qualification (EQ) of electrical equipment used in commercial nuclear power plants have recently become the subject of significant interest to the US Nuclear Regulatory Commission (NRC). Initial questions centered on whether compliance with the EQ requirements for older plants were adequate to support plant operation beyond 40 years. After subsequent investigation, the NRC Staff concluded that questions related to the differences in EQ requirements between older and newer plants constitute a potential generic issue which should be evaluated for backfit, independent of license renewal activities. EQ testing of electric cables was performed by Sandia National Laboratories (SNL) under contract to the NRC in support of license renewal activities. Results showed that some of the environmentally qualified cables either failed or exhibited marginal insulation resistance after a simulated plant life of 20 years during accident simulation. This indicated that the EQ process for some electric cables may be non-conservative. These results raised questions regarding the EQ process including the bases for conclusions about the qualified life of components based upon artificial aging prior to testing

  17. Workshop on environmental qualification of electric equipment

    Energy Technology Data Exchange (ETDEWEB)

    Lofaro, R.; Gunther, W.; Villaran, M.; Lee, B.S.; Taylor, J. [comps.] [Brookhaven National Lab., Upton, NY (United States)

    1994-05-01

    Questions concerning the Environmental Qualification (EQ) of electrical equipment used in commercial nuclear power plants have recently become the subject of significant interest to the US Nuclear Regulatory Commission (NRC). Initial questions centered on whether compliance with the EQ requirements for older plants were adequate to support plant operation beyond 40 years. After subsequent investigation, the NRC Staff concluded that questions related to the differences in EQ requirements between older and newer plants constitute a potential generic issue which should be evaluated for backfit, independent of license renewal activities. EQ testing of electric cables was performed by Sandia National Laboratories (SNL) under contract to the NRC in support of license renewal activities. Results showed that some of the environmentally qualified cables either failed or exhibited marginal insulation resistance after a simulated plant life of 20 years during accident simulation. This indicated that the EQ process for some electric cables may be non-conservative. These results raised questions regarding the EQ process including the bases for conclusions about the qualified life of components based upon artificial aging prior to testing.

  18. Impact of pre-conditioning on the qualification of safety-related equipment

    International Nuclear Information System (INIS)

    Isgro, J.R.

    1982-01-01

    This paper shares some recent experiences on the effects of preconditioning on the qualification of safety-related equipment not located in a harsh environment. Environmental and seismic qualification testing programs were conducted following the guidelines of IEEE 323-1974, IEEE 344-1975 and appropriate IEEE daughter standards, where available. The examples that follow will illustrate the degree of pre-conditioning of safety-related equipment qualified to the requirements of IEEE-323-1974, and its effect on the outcome of the qualification program

  19. Environmental Qualification Program for NPP Krsko

    International Nuclear Information System (INIS)

    Cerjak, J.; Klenovsek, P.; Pavsek, J.; Spalj, S.; Colovic, G.

    1998-01-01

    The functionality the equipment important to safety is deteriorated during its service due to ageing and harsh environment conditions. Since the environment is a potential for common cause failures, the purpose of Environmental Qualification (EQ) is to demonstrate the capability of safety-related equipment to perform its safety function in aged conditions and under extreme conditions after design bases event (DBE). EQ is one of the steps in licensing process according to US regulatory documents and standards (10CFR50.49, RG 1.89, NUREG-0588, IEEE-323). This paper presents the efforts in establishing the EQ program in the Krsko nuclear power plant. (author)

  20. On safety 1E qualification of electrical equipment for nuclear power stations

    International Nuclear Information System (INIS)

    Segarceanu, D.; Geambasu, C.; Avramescu, M.

    1995-01-01

    Electrical equipment and systems for the emergency shutdown of a nuclear reactor are qualified according to safety class 1E. Methods of qualification meeting the requirements should be used, either individually or in combination include, type-test qualification, qualification by operating experience, qualification by analysis, combined qualification. These methods qualification principles, procedures and documents are discussed. (N.T.). 1 fig

  1. Qualification of Electrical Equipment in Nuclear Power Plants - Management of ageing

    International Nuclear Information System (INIS)

    Spaang, Kjell; Staahl, Gunnar

    2013-02-01

    The purpose of this report is to describe programs and tools for assessment of accomplished and documented qualification with respect to ageing of electrical equipment and for development of complimentary ageing management programs. In addition to description of complete programs for management of ageing, tools for validation of the status with regard to ageing of installed ('old') equipment and, where needed, for complementation of their qualification are also included. The report is restricted to safety related equipment containing ageing sensitive parts, mainly organic materials. To this category belong cables and cable joints and a number of equipment containing oils, seals (o-rings), etc. For equipment located in the containment, the possibilities of continuous supervision are limited. The accessibility for regular inspections is also limited in many cases. The main part of this report deals with the qualification of such equipment. Some safety related equipment outside the containment can be located in areas where they are subjected to high temperature and other excessive environmental stresses during normal operation and in areas affected by an accident. Therefore, some material is given also on qualification of equipment located outside containment with better possibilities for frequent inspection and supervision. Part 1 of the report is an executive summary with a general review of the methodologies and their application. The more detailed description of the programs and underlying material, useful data, etc. is given in Part 2

  2. Recent developments in methodology for dynamic qualification of nuclear plant equipment

    International Nuclear Information System (INIS)

    Kana, D.D.; Pomerening, D.J.

    1984-01-01

    Dynamic qualification of nuclear plant electrical and mechanical equipment is performed basically under guidelines given in IEEE Standards 323 and 344, and a variety of NRC regulatory guides. Over the last fifteen years qualification methodology prescribed by these documents has changed significantly as interpretations, equipment capability, and imagination of the qualification engineers have progressed. This progress has been sparked by concurrent NRC and industry sponsored research programs that have identified anomalies and developed new methodologies for resolving them. Revisions of the standards have only resulted after a lengthy debate of all such new information and subsequent judgment of its validity. The purpose of this paper is to review a variety of procedural improvements and developments in qualification methodology that are under current consideration as revisions to the standards. Many of the improvements and developments have resulted from recent research programs. All are very likely to appear in one type of standard or another in the near future

  3. Re-qualification of switchgear equipment following field modification

    International Nuclear Information System (INIS)

    Tulk, J.D.; El Bestawi, M.A.

    1984-01-01

    A set of 4.16 kV switchgear was seismically qualified by shaker table test for use in a nuclear power plant. Later, the equipment was modified by the addition of two extra switches and enclosures. This paper describes the methods used to extend the qualification achieved in the original proof test to the new configuration. Qualification of the modified switchgear depended on demonstrating that the intensity of the shaking that would be experienced by equipment mounted in the extended enclosure during a design basis earthquake (DBE) would be no stronger than the shaking that occurred during the original qualification testing. This was accomplished by a combination of analysis and experiment. Natural frequencies and mode-shapes of the original and extended enclosure structures were determined through in-situ modal tests on the equipment. Mathematical models based on the experimental results were then used for dynamic analyses which generated two sets of in-equipment response spectra: one set representing the original qualification test; and one set representing the response of the modified equipment to a hypothetical DBE. Qualification was confirmed by demonstrating that the test-based response spectra for the original configuration exceeded the response spectra developed for the extended structure subjected to DBE level excitation

  4. Technology transfer equipment qualification methodology for shelf life determination

    International Nuclear Information System (INIS)

    Anderson, J.W.

    1995-01-01

    Discussions with a number of Nuclear Utilities revealed that equipment qualified for 10 to 40 years in the harsh environment of the plant was being assigned shelf lives of only 5 to 10 years in the benign environment of the warehouse, and then the materials were being trashed. One safety-related equipment supplier was assigning a 10-year qualified life, from date of shipment, with no recognition of the difference in the aging rate in the plant vs. that in the warehouse. Many suppliers assign shelf lives based on product warranty considerations rather than actual product degradation. An EPRI program was initiated to evaluate the methods used to assign shelf lives and to adapt the Arrhenius methodology, used in equipment qualification, to assign technically justifiable shelf lives. Temperature is the main factor controlling shelf life; however, atmospheric pressure, humidity, ultraviolet light, ozone and other atmospheric contaminants were also considered. A list of 70 representative materials was addressed in the program. All of these were found to have shelf lives of 14 years to greater than 60 years, except for 19 items. For 18 of these items, there was no data available except for the manufacturer's recommendation

  5. Technical evaluation of seismic qualification of safety-related equipment

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Yang Hui; Park, Heong Gee; Park, Yeong Seok [Univ. of Incheon, Incheon (Korea, Republic of)

    1994-04-15

    This study is purposed to evaluate the technical acceptability of the procedures and techniques of seismic qualifications which were performed for the YGN 3 and 4 safety-related equipment.This study is also targeted to suggest a systematized technical procedure guide for the effective performance and review of the seismic qualification, which reflects the most up-to-date licensing requirements and state-of the-art.

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

    International Nuclear Information System (INIS)

    2001-01-01

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

  7. Application of operating experience in environmental qualification program

    International Nuclear Information System (INIS)

    Lee, S.Y.; Wise, R.

    2000-01-01

    Environmental qualification (EQ) of equipment related to nuclear safety has been carried out in the nuclear community since the 70's. It started with electrical equipment and then expanded to include mechanical equipment. During this evolutionary process, the methods used for EQ have gone through a long period of refinement and clarification. Prior to 1971, qualification for equipment in licensed nuclear power plants was based on the use of electrical components of commonly accepted high industrial quality without the benefit of specific environmental qualification standards. Between 1971 and 1974, most plants used the criteria of IEEE Standard 323-1971 as the basis for demonstrating qualification. Also during this period related 'daughter' standards, mainly by IEEE, became available which addressed qualification for specific equipment items. After July 1974, plants were required to meet the more comprehensive guidelines specified in IEEE Standard 323-1974 and the related 'daughter' standards. IEEE Standard 323-1974 later evolved into IEEE Standard 323-1983. For nuclear power plants built in Ontario during the 70's, i.e. Pickering B and Bruce B, has included the environmental qualification requirements in their respective nuclear safety design guides. It is now recognized that they are not up to the current EQ standards. Darlington, constructed during the 80's, implemented the environmental qualification program in its project. An Environmental Qualification (EQ) Program is now under way in Ontario Power Generation (OPG) to formally implement the Environmental Qualification for Bruce B, Pickering B, and Pickering A and to preserve the Qualification for Darlington G.S. This paper makes a thorough a review of the standard methods used in the past by utilities for environmental qualification. These methods include type testing, analysis, and operating experience. Both type testing and analysis have been clearly defined in standards listed in References [2] to [6] and

  8. Seismic qualification of equipment by means of probabilistic risk assessment

    International Nuclear Information System (INIS)

    Azarm, M.A.; Farahzad, P.; Boccio, J.L.

    1982-01-01

    Upon the sponsorship of the Equipment Qualification Branch (EQB) of NRC, Brookhaven National Laboratory (BNL) has utilized a risk-based approach for identifying, in a generic fashion, seismically risk-sensitive equipment. It is anticipated that the conclusions drawn therefrom and the methodology employed will, in part, reconcile some of the concerns dealing with the seismic qualification of equipment in operating plants. The approach taken augments an existing sensitivity analysis, based upon the WASH-1400 Reactor Safety Study (RSS), by accounting for seismicity and component fragility with the Kennedy model and by essentially including the requisite seismic data presented in the Zion Probabilistic Safety Study (ZPSS). Parametrically adjusting the seismic-related variables and ascertaining their effects on overall plant risk, core-melt probability, accident sequence probability, etc., allows one to identify those seismically risk-sensitive systems and equipment. This paper describes the approach taken and highlights the results obtained thus far for a hypothetical pressurized water reactor

  9. Evolution of seismic shock test qualification of equipment

    International Nuclear Information System (INIS)

    Berriaud, C.

    1979-01-01

    From the first nuclear power plants a new industrial problem is appeared: the seismic test qualification of equipment. Nothing was existing in this range. Methods and test experiments were to be studied and perfected in order to obtain safe results. This paper presents the evolution of this question up to now [fr

  10. Seismic and environmental qualification of class IE equipment manufactured in Spain

    International Nuclear Information System (INIS)

    Gerini, P.; Lumbreras, A.; Naredo, F.

    1978-01-01

    Nuclear power plant instrumentation and control design is affected by several factors such as various plant operating conditions, transient response capability, safety requirements and changes in IEEE standards. Recent upgraded IEEE standards that call for Qualification of all Safety related I anc C equipment, namely IEEE 323 (Qualifying Class IE Electric Equipment for nuclear power generating stations) and its daughter Standard IEEE 344 (Recommended Practices for Seismic Qualification of Class IE Equipment for nuclear power generating stations) have been endorsed by the United States Nuclear Regulatory Commission through the issuance of corresponding Regulatory Guides. The author describes the Qualification requirements applicable to the Class IE I and C Components made in Spain for the different vintages of plants, and the programs implemented or plans established by Westinghouse to fulfill those requirements. (author)

  11. Technical basis for environmental qualification of microprocessor-based safety-related equipment in nuclear power plants

    International Nuclear Information System (INIS)

    Korsah, K.; Wood, R.T.; Hassan, M.; Tanaka, T.J.

    1998-01-01

    This document presents the results of studies sponsored by the Nuclear Regulatory Commission (NRC) to provide the technical basis for environmental qualification of computer-based safety equipment in nuclear power plants. The studies were conducted by Oak Ridge National Laboratory (ORNL), Sandia National Laboratories (SNL), and Brookhaven National Laboratory (BNL). The studies address the following: (1) adequacy of the present test methods for qualification of digital I and C systems; (2) preferred (i.e., Regulatory Guide-endorsed) standards; (3) recommended stressors to be included in the qualification process during type testing; (4) resolution of need for accelerated aging for equipment to be located in a benign environment; and (5) determination of an appropriate approach for addressing the impact of smoke in digital equipment qualification programs. Significant findings from the studies form the technical basis for a recommended approach to the environmental qualification of microprocessor-based safety-related equipment in nuclear power plants

  12. Technical basis for environmental qualification of microprocessor-based safety-related equipment in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Korsah, K.; Wood, R.T. [Oak Ridge National Lab., TN (United States); Hassan, M. [Brookhaven National Lab., Upton, NY (United States); Tanaka, T.J. [Sandia National Labs., Albuquerque, NM (United States)

    1998-01-01

    This document presents the results of studies sponsored by the Nuclear Regulatory Commission (NRC) to provide the technical basis for environmental qualification of computer-based safety equipment in nuclear power plants. The studies were conducted by Oak Ridge National Laboratory (ORNL), Sandia National Laboratories (SNL), and Brookhaven National Laboratory (BNL). The studies address the following: (1) adequacy of the present test methods for qualification of digital I and C systems; (2) preferred (i.e., Regulatory Guide-endorsed) standards; (3) recommended stressors to be included in the qualification process during type testing; (4) resolution of need for accelerated aging for equipment to be located in a benign environment; and (5) determination of an appropriate approach for addressing the impact of smoke in digital equipment qualification programs. Significant findings from the studies form the technical basis for a recommended approach to the environmental qualification of microprocessor-based safety-related equipment in nuclear power plants.

  13. Environmental qualification program for Krsko NPP

    International Nuclear Information System (INIS)

    Cerjak, J.; Klenovsek, P.; Pavsek, J.; Freeland, K.R.; Spalj, S.

    1998-01-01

    NEK plant components, including those critical to safe plant operation, deteriorate and wear over service life due to the effects of aging and harsh environmental conditions. Since the plant environment is a source of common-cause failures, an Environmental Qualification (EQ) program is required to ensure and demonstrate the ability of safety-related equipment to perform its design safety function during a design-basis (DBE), even after aging over its service life in the plant. EQ is a requirement for plants licensed by the US NRC, in accordance with 10 CFR 50.49, Regulatory Guide 1.89, NUREG-0588, and IEEE-323. This paper presents the current EQ Program status at Krsko NPP.(author)

  14. Application of Microprocessor-Based Equipment in Nuclear Power Plants - Technical Basis for a Qualification Methodology

    International Nuclear Information System (INIS)

    Korsah, K.

    2001-01-01

    This document (1) summarizes the most significant findings of the ''Qualification of Advanced Instrumentation and Control (I and C) Systems'' program initiated by the Nuclear Regulatory Commission (NRC); (2) documents a comparative analysis of U.S. and European qualification standards; and (3) provides recommendations for enhancing regulatory guidance for environmental qualification of microprocessor-based safety-related systems. Safety-related I and C system upgrades of present-day nuclear power plants, as well as I and C systems of Advanced Light-Water Reactors (ALWRs), are expected to make increasing use of microprocessor-based technology. The Nuclear Regulatory Commission (NRC) recognized that the use of such technology may pose environmental qualification challenges different from current, analog-based I and C systems. Hence, it initiated the ''Qualification of Advanced Instrumentation and Control Systems'' program. The objectives of this confirmatory research project are to (1) identify any unique environmental-stress-related failure modes posed by digital technologies and their potential impact on the safety systems and (2) develop the technical basis for regulatory guidance using these findings. Previous findings from this study have been documented in several technical reports. This final report in the series documents a comparative analysis of two environmental qualification standards--Institute of Electrical and Electronics Engineers (IEEE) Std 323-1983 and International Electrotechnical Commission (IEC) 60780 (1998)--and provides recommendations for environmental qualification of microprocessor-based systems based on this analysis as well as on the findings documented in the previous reports. The two standards were chosen for this analysis because IEEE 323 is the standard used in the U.S. for the qualification of safety-related equipment in nuclear power plants, and IEC 60780 is its European counterpart. In addition, the IEC document was published in

  15. Overview of nuclear power plant equipment qualification issues and practices

    International Nuclear Information System (INIS)

    Torr, K.G.

    1989-01-01

    This report presents a view of and commentary on the current status of equipment qualification (EQ) in nuclear industries of the major western nations. The introductory chapters discuss the concepts of EQ, the elements of EQ process and highlight some of the key issues in EQ. A brief review of industry practices and some of the prevalent industrial standards is presented, followed by an overview of current regulatory positions in the USA, France, Germany and Sweden. A summary and commentary on the latest research findings on issues relating to accident simulation, to aging simulation and some special topics related to EQ, has been contributed by Franklin Research Centre of Philadelphia. The last part of the report deals with equipment qualification in Canada and gives recommendations on EQ for new plants as well as currently operational CANDU nuclear power plants

  16. Seismic qualification method of equipment for nuclear power plant

    International Nuclear Information System (INIS)

    Kim, J.S.; Choi, T.H.; Sulaimana, R.A.

    1995-01-01

    Safety related equipment installed in Korean Nuclear Power Plants are required to perform a safety function during and after a seismic event. To accomplish this safety function, they must be seismically qualified in accordance with the intent and requirements of the USNRC Reg. Guide 1.100 Rev. 02 and IEEE Std. 344-1987. This paper defines and summarizes acceptable criteria and procedures, based on the Korean experience, for seismic qualification of purchased equipment to be installed in a nuclear power plant. As such the paper is intended to be a concise reference by equipment designers, architectural engineering company and plant owners in uniform implementation of commitments to nuclear regulatory agencies such as the USNRC or Korea Institute of Nuclear Safety (KINS) relating to adequacy of seismic Category 1 equipment. Thus, the paper provides the methodologies which can be used for qualifying equipment for safely related service in Nuclear Power Plants in a cost effective manner

  17. Nuclear Criticality Safety Department Qualification Program

    International Nuclear Information System (INIS)

    Carroll, K.J.; Taylor, R.G.; Worley, C.A.

    1996-01-01

    The Nuclear Criticality Safety Department (NCSD) is committed to developing and maintaining a staff of highly qualified personnel to meet the current and anticipated needs in Nuclear Criticality Safety (NCS) at the Oak Ridge Y-12 Plant. This document defines the Qualification Program to address the NCSD technical and managerial qualification as required by the Y-1 2 Training Implementation Matrix (TIM). This Qualification Program is in compliance with DOE Order 5480.20A and applicable Lockheed Martin Energy Systems, Inc. (LMES) and Y-1 2 Plant procedures. It is implemented through a combination of WES plant-wide training courses and professional nuclear criticality safety training provided within the department. This document supersedes Y/DD-694, Revision 2, 2/27/96, Qualification Program, Nuclear Criticality Safety Department There are no backfit requirements associated with revisions to this document

  18. Calibration and qualification of equipment in the pharmaceutical industry: emphasis on radiopharmaceuticals production

    International Nuclear Information System (INIS)

    Melero, Laura T.U.H.; Silva, Katia S. da S.; Zanette, Camila; Araujo, Elaine B. de; Mengatti, Jair

    2011-01-01

    The calibration and qualification of equipment are listed items in RDC number 17 of 2010 which refers about the Good Manufacturing Practice (GMP) of medicaments and RDC number 63 of 2009 which refers about GMP of Radiopharmaceuticals. Both are essential requirements since they are involved in process control to attend the regulatory criteria and are a key part of the validation process. The aim of this work is presenting the importance of calibration and qualification, and the routine use of equipment and facilities in industrial scale production of radiopharmaceuticals in the IPEN/CNEN. The radiopharmacy of IPEN is a pharmaceutical industry that produces radiopharmaceuticals for diagnosis and therapy. It was the pioneer institute in production of radioisotopes and radiopharmaceuticals in Brazil. Currently, 38 products are distributed to the nuclear medicine centers, including primary radioisotopes, labeled molecules and lyophilized reagents for labeling with technetium-99m. To fulfill the GMP requirements for quality assurance of products, several factors must be considered including infrastructure, equipment and raw materials beyond, obviously, the whole production process should be controlled until the release of the final product. Therefore, the calibration and verification of equipment, instruments and other appliances used in the production and quality control should be performed. A program of calibration, qualification and requalification of equipment used in production and quality control of radiopharmaceuticals is necessary for the validation of production processes and analytical methods, and should be established for quality assurance of produced radiopharmaceuticals. (author)

  19. Calibration and qualification of equipment in the pharmaceutical industry: emphasis on radiopharmaceuticals production

    Energy Technology Data Exchange (ETDEWEB)

    Melero, Laura T.U.H.; Silva, Katia S. da S.; Zanette, Camila; Araujo, Elaine B. de; Mengatti, Jair [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2011-07-01

    The calibration and qualification of equipment are listed items in RDC number 17 of 2010 which refers about the Good Manufacturing Practice (GMP) of medicaments and RDC number 63 of 2009 which refers about GMP of Radiopharmaceuticals. Both are essential requirements since they are involved in process control to attend the regulatory criteria and are a key part of the validation process. The aim of this work is presenting the importance of calibration and qualification, and the routine use of equipment and facilities in industrial scale production of radiopharmaceuticals in the IPEN/CNEN. The radiopharmacy of IPEN is a pharmaceutical industry that produces radiopharmaceuticals for diagnosis and therapy. It was the pioneer institute in production of radioisotopes and radiopharmaceuticals in Brazil. Currently, 38 products are distributed to the nuclear medicine centers, including primary radioisotopes, labeled molecules and lyophilized reagents for labeling with technetium-99m. To fulfill the GMP requirements for quality assurance of products, several factors must be considered including infrastructure, equipment and raw materials beyond, obviously, the whole production process should be controlled until the release of the final product. Therefore, the calibration and verification of equipment, instruments and other appliances used in the production and quality control should be performed. A program of calibration, qualification and requalification of equipment used in production and quality control of radiopharmaceuticals is necessary for the validation of production processes and analytical methods, and should be established for quality assurance of produced radiopharmaceuticals. (author)

  20. Design Modification of Kori Unit 1 for the Equipment Qualification

    International Nuclear Information System (INIS)

    Park, J. W.; Kim, M. Y.; Han, K. T.; Park, J. D.

    2007-01-01

    There has not been a strict regulatory requirements for the Equipment Qualification(EQ) in 1970's when Kori Unit 1 had begun the construction and the commercial operation. The Korean regulatory body requested the EQ on the various safety-related components, as a result of Periodic Safety Review. However, the EQ itself is impossible in some areas, due to the high pressure/temperature and flooding environment conditions from the pipe breaks. Design modification is being considered in the Auxiliary Building, the Intermediate Building, the Component Cooling Water Heat Exchanger Building and the Turbine Building, in order to mitigate the environmental conditions for the EQ

  1. IEEE Std 600: IEEE trial-use standard requirements for organizations that conduct qualification testing of safety systems equipment for use in nuclear power generating stations

    International Nuclear Information System (INIS)

    Anon.

    1992-01-01

    The purpose of this standard is to provide requirements for establishing a program for conducting qualification tests of safety systems equipment used in nuclear power generating stations. Compliance with the requirements of this standard does not assure the adequacy of the qualification tests performed. This standard applies to organizations that conduct qualification tests on equipment that has a definable safety function and is an identifiable part of a safety system for use in nuclear power generating stations. It requires a technical program, a quality assurance program, and a demonstrated ability to meet specified technical requirements. It does not apply to materials tests, production tests, normal performance testing, qualification by analysis, qualification by operating experience, or reliability tests such as diesel-generator multiple start tests. The intent of this standard is to achieve greater consistency, reliability, and reproducibility of test results and to provide adequate control of qualification testing of safety systems equipment

  2. A guide to qualification of electrical equipment for nuclear power plants. Final report, November 1983

    International Nuclear Information System (INIS)

    Marion, A.; Lamken, D.; Harrall, T.; Kasturi, S.; Holzman, P.; Carfagno, S.; Thompson, D.; Boyer, B.; Hanneman, H.; Rule, W.

    1983-09-01

    Equipment qualification demonstrates that nuclear power plant equipment can perform its safety function - that despite age or the adverse conditions of a design basis accident the equipment can work as needed. This report is a guide to the overall process of electrical equipment qualification. It should interest those who design such equipment, those who buy it, or test it, and even those who install and maintain it. (author)

  3. Use of GOTHIC Code for Assessment of Equipment Environmental Qualification

    International Nuclear Information System (INIS)

    Cavlina, N.; Feretic, D.; Grgic, D.; Spalj, S.; Spiler, J.

    1996-01-01

    Environmental qualification (EQ) of equipment important to safety in nuclear power plants ensures its capability to perform designated safety function on demand under postulated service conditions, including harsh accident environment (e. g. LOCA, HELB). The computer code GOTHIC was used to calculate pressure and temperature profiles inside NPP Krsko containment during limiting LOCA and MSLB accidents. The results of the new best-estimate containment code are compared to the older CONTEMPT code using the same input data and assumptions. The predictions obtained by both codes are very similar. As a result of the calculation the envelopes of the LOCA and MSLB pressures and temperatures, as used in FSAR/USAR Chapter 6, can be used in EQ project. (author)

  4. Towards a systematic format for (seismic) equipment qualification standards

    International Nuclear Information System (INIS)

    Smith, P.D.

    1982-01-01

    As part of technical assistance to the US Nuclear Regulatory Commission (NRC, 1), a systematic format for seismic equipment qualification (EQ) was initiated. This format consists of thirty issues associated with seismic EQ. Each issue was considered as a Category of Possible Seismic EQ Requirements and Criteria. That is, seismic EQ standards might be (but presently are not formulated in terms of requirements and criteria that address each of the thirty issues. Each of the thirty issues was ranked and a minimum set identified. The current requirements in existing NRC and national standards were also evaluated against this common set of issues, and they were estimated to score 60 out of 100 overall. It is believed that the systematic format exhibited in this paper can be of assistance in obtaining a broader and more complete perspective on seismic EQ issues. This format (but especially the technique) may also be of interest in non-seismic EQ since many of the issues are common

  5. Power/response spectrum transformations in equipment qualification

    International Nuclear Information System (INIS)

    Unruh, J.F.; Kana, D.D.

    1985-01-01

    Since its introduction a few years ago the use of the power/response spectrum transformation has gained considerable interest and acceptance, and a number of new applications of the transformation have been developed in the equipment qualification area. A brief review of the power/response spectrum transformation is given with a discussion of the input/output relationships for linear systems required for elevated power spectrum generation. Frequency content of earthquakelike signals is discussed with emphasis on the resolution given by the PSD. The problem of excessive ZPA due to inconsistent spectra enveloping and mechanical nonlinearities is also discussed. The PSD/RS transformation is applied to the problems of combining various dynamic load events, developing bounding spectra, and developing damping consistent test spectra. Development of elevated component spectra corrected for base overtest and generation from in-situ measurements is reviewed

  6. Safety review for seismic qualification on nuclear power plant equipment

    International Nuclear Information System (INIS)

    Fang Qingxian

    1995-01-01

    The standards and requirements for seismic qualification of nuclear power plant's component have been fully addressed, including the scope of seismic qualification, the approach and the method of common seismic qualification, the procedure of the seismic tests, and the criteria for the seismic qualification review. The problems discovered in the safety review and the solution for these problems and some other issues are also discussed

  7. Meeting the latest qualification requirements for Class 1E protection system equipment: a practical approach

    International Nuclear Information System (INIS)

    Daigle, R.P.; Breen, R.J.

    1977-01-01

    The requirements for qualifying Class 1E equipment for Nuclear Power Generating Stations were significantly revised in 1974 and 1975. These new requirements reflect the desire of the industry to provide improved methods of determining the qualification of this vital equipment. The revised standards do, in fact, meet these industry goals in a generally acceptable manner. The Nuclear Regulatory Commission is presently requiring utilities to comply with these revised standards and regulatory guides in order to obtain the necessary permits. Manufacturers are developing and implementing programs to comply with the new requirements. One of the more difficult new requirements of qualification is aging to achieve advanced life condition. The objectives and methods described for aging are difficult for much of the equipment within the Protection System. The use of thermal and vibrational techniques to simulate aging is valid for some components (i.e., capacitors, transistors, cable and/or motor insulation) but may be neither valid nor practical for many items (e.g., complete instrument systems, etc.). A seemingly obvious approach, although rarely followed, in regarding new or revised standards is to refrain from making any type of commitment until the standards are thoroughly understood. Often too hasty a decision is made by a utility (concerned about licensing) or a manufacturer (concerned about being competitive) to commit to new requirements. Consequently, the broad range of interpretations that usually develops for a given set of requirements may result in difficult relations between organizations. This paper deals with solutions for qualification in a practical sense, with emphasis on the aging issue and does not elaborate on seismic qualification

  8. 1E Qualification of Electrical Equipment - Requirement for Safety Nuclear Power Plants

    International Nuclear Information System (INIS)

    Geambasu, C.; Segarceanu, D.; Albu, J.

    2002-01-01

    The paper presents the qualification methods of the safety related equipment according to the safety class 1E. There are presented the qualification principles, procedure and documents, emphasis being laid on the qualification approach by type tests. This approach assumes the equipment test under both normal and accident conditions (design basis events) simulating the operational conditions and covers the largest part of electrical equipment from a nuclear power plant.The safety related equipment is to be qualified is subjected to a sequential test that will be detailed in the paper. (author)

  9. Co-operation Equipment Qualification for Safety grade I and C Equipment between Russia and Korea

    International Nuclear Information System (INIS)

    Ham, J. K.; Lee, D. H.; Park, J. W.; Jeong, M. H.; Choi, Y. H.; Suh, J. J.; Jang, T. H.

    2007-06-01

    Equipment Qualification technology for I and C system on nuclear grade have been approved with accurate and safe for verifying and validation. It contributes to acknowledge of reliability and to review of user approval. Also it did not completely satisfied the requirement of Russia, it can be satisfied by bit of modification on design. It is expected to support the export of safety PLC to nuclear power plant. Proven EQ technology is required on the further markets of nuclear. Therefore, comparison test with foreign country is necessary to support the mutual accreditation of EQ for export of domestic products

  10. Co-operation Equipment Qualification for Safety grade I and C Equipment between Russia and Korea

    Energy Technology Data Exchange (ETDEWEB)

    Ham, J. K.; Lee, D. H.; Park, J. W.; Jeong, M. H.; Choi, Y. H.; Suh, J. J.; Jang, T. H. [Korea Testing Laboratory, Seoul (Korea, Republic of)

    2007-06-15

    Equipment Qualification technology for I and C system on nuclear grade have been approved with accurate and safe for verifying and validation. It contributes to acknowledge of reliability and to review of user approval. Also it did not completely satisfied the requirement of Russia, it can be satisfied by bit of modification on design. It is expected to support the export of safety PLC to nuclear power plant. Proven EQ technology is required on the further markets of nuclear. Therefore, comparison test with foreign country is necessary to support the mutual accreditation of EQ for export of domestic products.

  11. Buried Waste Program (BWP) data qualification manual

    International Nuclear Information System (INIS)

    Casey, C.; Larson, R.A.; Harris, G.A.

    1989-06-01

    The Data Qualification Manual (DQM) has been developed to discuss the process required to qualify data generated for the Buried Waste Program (BWP). The data from the BWP tasks conducted at the Radioactive Waste Management Complex (RWMC) and elsewhere will lead to remedial decisions being made which are governed by federal regulations administered by the Environmental Protection Agency (EPA). Data qualification is the process of insuring that only data of planned and known qualities are used to make a decision or answer a question. Although it is the Data Integrity Review Committee's (DIRC) responsibility to insure that the quality of all BWP data is ultimately verified and validated, all personnel who participate in the data gathering process will affect the quality of the data and must be responsible for knowing what is required to produce data of the planned quality. Therefore this manual is addressed to all participants in a data-gathering task. This manual discusses requirements to support data qualification in several areas, including: the sampling and analysis plan; data quality objectives and PARCC goals; sample custody documentation; quality assurance; assembly of the data qualification package; and existing data. 23 refs., 4 figs., 6 tabs

  12. NFC based Equipment Qualification Management (NEQM) system preventing counterfeit and fraudulent item

    Energy Technology Data Exchange (ETDEWEB)

    Chang, C.K., E-mail: ckchang@kings.ac.kr [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of); Lee, K.J., E-mail: klee@khu.ac.kr [Kyung Hee Univ., Seoul (Korea, Republic of)

    2014-07-01

    Qualification of equipment essential to safety in nuclear power plants (NPPs) ensures its capability to perform designated safety functions on demand under postulated service conditions. However, a number of incidents identified by the NRC since 1980s catalysed the US nuclear industry to adopt standard precautions to guard against counterfeit items. The purpose of this paper is to suggest the NFC (Near Field Communication) based equipment qualification management system preventing counterfeit and fraudulent items. The NEQM (NFC based Equipment Qualification Management) system work with the support of legacy systems such as PMS (Procurement Management System) and FMS (Facility management System). (author)

  13. NFC based Equipment Qualification Management (NEQM) system preventing counterfeit and fraudulent item

    International Nuclear Information System (INIS)

    Chang, C.K.; Lee, K.J.

    2014-01-01

    Qualification of equipment essential to safety in nuclear power plants (NPPs) ensures its capability to perform designated safety functions on demand under postulated service conditions. However, a number of incidents identified by the NRC since 1980s catalysed the US nuclear industry to adopt standard precautions to guard against counterfeit items. The purpose of this paper is to suggest the NFC (Near Field Communication) based equipment qualification management system preventing counterfeit and fraudulent items. The NEQM (NFC based Equipment Qualification Management) system work with the support of legacy systems such as PMS (Procurement Management System) and FMS (Facility management System). (author)

  14. The DWPF waste form qualification program

    International Nuclear Information System (INIS)

    Marra, S.L.; Plodinec, M.J.

    1994-01-01

    Prior to the introduction of radioactive feed into the Defense Waste Processing Facility for immobilization in borosilicate glass an extensive waste qualification program must be completed. The DWPF must demonstrate its ability to comply with the Waste Acceptance Product Specifications. This ability is being demonstrated through laboratory and pilot scale work and will be completed after the full operation of the DWPF using various simulated feeds

  15. IEEE recommended practices for seismic qualification of Class 1E equipment for nuclear power generating stations

    International Nuclear Information System (INIS)

    Anon.

    1975-01-01

    The IEEE has developed this document to provide direction for developing programs to seismically qualify Class 1E equipment for nuclear power generating stations. It supplements IEEE Std 323-1974, IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations, which describes the basic requirements for equipment qualification. The Class 1E equipment to be qualified by produres or standards established by this document are of many forms, characteristics, and materials; therefore, the document presents many acceptable methods with the intent of permitting the user to make a judicious selection from among the various options. In making such a selection, the user should choose those that best meet a particular equipment's requirements. Further, in using this document as a specification for the purchase of equipment, the many options should also be recognized and the document invoked accordingly. It is recommended that the need for specific standards for the seismic qualifiction of particular kinds of equipment be evaluated by those responsible for such documents and that consideration be given to the application of particular methods from these documents which are most suitable

  16. A strategy for implementation of experience based seismic equipment qualification in IEEE and ASME industry standards

    International Nuclear Information System (INIS)

    Adams, T.M.

    1996-01-01

    In the past 20 years, extensive data on the performance of mechanical and electric equipment during actual strong motion earthquakes and seismic qualification tests has been accumulated. Recognizing that an experience based approach provides a technically sound and cost effective method for the seismic qualification of some or certain equipment, the IEEE Nuclear Power Engineering Committee and the ASME Committee on Qualification of Mechanical Equipment established a Special Working Group to investigate the incorporation of experienced based methods into the industry consensus codes and standards currently used in the seismic qualification of Seismic Category Nuclear Power Plant equipment. This paper presents the strategy (course of action) which was developed by the Special Working Group for meeting this objective of incorporation of experience based seismic qualification standards used in the design and seismic qualification of seismic category nuclear power plant equipment. This strategy was recommended to both chartering organizations, the IEEE Nuclear Power Engineering Committee and the ASME Committee on Qualification of Mechanical Equipment for their consideration and implementation. The status of the review and implementation of the Special Working Group's recommended strategy by the sponsoring organization is also discussed

  17. The qualification requirements for personnel carry out the testing for the pressure equipment materials

    International Nuclear Information System (INIS)

    Wojas, M.; Walczak, M.

    2006-01-01

    The article contains information about qualification requirements for personnel carry out the destructive and non-destructive testing for the pressure equipment materials based on the Directive 97/23/CE(PED). Competence laboratory carry out the testing. The responsibility lies with producer / employer. The producer / employer could elaborate the written practice procedure for qualification and certification testing personnel. (authors)

  18. Californium-252 Program Equipment Evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Chattin, Fred Rhea [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Wilson, Kenton [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Ezold, Julie G. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2017-12-01

    To successfully continue the 252Cf production and meet the needs of the customers, a comprehensive evaluation of the Building 7920 processing equipment was requested to identify equipment critical to the operational continuity of the program.

  19. Development of equipment qualification requirements for NPP instrumentation and control systems

    International Nuclear Information System (INIS)

    Siora, A. A.; Reshetitskij, S. V.; Harybin, A. V.

    2012-01-01

    The main stages of equipment qualification are presented. The aim of the work is to ensure compatibility between Ukrainian and international requirements. A comparison with US NRC requirements has been done. The approach in equipment qualification is presented for the resistance to: irradiation; dust; seismic motion, vibrations and mechanical impact; environmental impact (temperature, humidity, pressure); power supply parameters etc., as well as the technological testing

  20. Procedure for qualification of electric equipment installed in containments for pressurized water reactors subject to accident conditions

    International Nuclear Information System (INIS)

    1991-11-01

    This generic norm is usable for electrical equipment installed in containment building of PWR subject to accidental conditions. She defines the qualification methods and the general rules usable for the test specifications of qualification for these materials

  1. Qualification of Programmable Electronic System (PES) equipment based on international nuclear I and C standards

    International Nuclear Information System (INIS)

    De Grosbois, J.; Hepburn, G. A.; Olmstead, R.; Goble, W.; Kumar, V.

    2006-01-01

    Nuclear power plants (NPPs) are increasingly faced with the challenge of qualifying procured equipment, sub-components, and systems that contain digital programmed electronics for use in safety-related applications. Referred to as a 'programmable electronic system' (PES), such equipment typically contains both complex logic that is vulnerable to systematic design faults, and low voltage electronics hardware that is subject to random faults. Procured PES products or components are often only commercial grade, yet can offer reliable cost effective alternatives to custom-designed or nuclear qualified equipment, provided they can be shown to meet the quality assurance, functional safety, environmental, and reliability requirements of a particular application. The process of confirming this is referred to as application-specific product qualification (ASPQ) and can be challenging and costly. This paper provides an overview of an approach that has been developed at Atomic Energy Canada Limited (AECL) and successfully applied to PES equipment intended for use in domestic Candu R 6 nuclear power plants and special purpose reactors at Chalk River Laboratories. The approach has evolved over the past decade and has recently been adapted to be consistent with, and take advantage of new standards that are applicable to nuclear safety-related I and C systems. Also discussed are how recognized third-party safety-certifications of PES equipment to International Electrotechnical Commission (IEC) standards, and the assessment methods employed, may be used to reduce ASPQ effort. (authors)

  2. Qualification testing evaluation (QTE) program, FIN A-1051, Case 0686. Bimonthly status report, February-March 1986

    International Nuclear Information System (INIS)

    1986-01-01

    This report presents information on: accident methodologies assessments; accident environment effects; aging methodologies assessments; TMI-2 related activities; international programs coordination; research/facility definition; seismic methodologies; and related equipment qualification issues

  3. Use of commercial grade equipment and industrial standards for equipment qualification

    International Nuclear Information System (INIS)

    Gradin, L.P.; Muller, E.S.

    1984-01-01

    One of the most controversial issues is the proper application of Arrhenius aging methodology. Naturally and artificially aged equipment used in type test programs are often costly and burdensome tasks. Appropriate use of non-nuclear industrial standards and comparison to past history can demonstrate, with reasonable assurance, that equipment is qualified with proper consideration of aging. Specific review of the industrial standards available and application examples are provided

  4. Staff report on the environmental qualification of safety-related electrical equipment

    International Nuclear Information System (INIS)

    1977-12-01

    The current NRC safety review process for nuclear power plants includes criteria related to the qualification of certain electrical equipment. These criteria require that electrical equipment important to safety must be qualified to function in the environment that might result from various accident conditions. Although such criteria have been applied since the early days of commercial nuclear power, the details of these criteria have been changed over the years. The evolution of environmental qualification of safety-related electrical equipment is described in Appendix A

  5. Equipment Obsolescence Management Program

    Energy Technology Data Exchange (ETDEWEB)

    Redmond, J.

    2014-07-01

    Nuclear Power Plant (NPP) Operators are challenged with securing reliable supply channels for safety related equipment due to equipment obsolescence. Many Original Equipment Manufacturers (OEMs) have terminated production of spare parts and product life-cycle support. The average component life cycles are much shorter than the NPP design life, which means that replacement components and parts for the original NPP systems are not available for the complete design life of the NPPs. The lack or scarcity of replacement parts adversely affects plant reliability and ultimately the profitability of the affected NPPs. This problem is further compounded when NPPs pursue license renewal and approval for plant-life extension. A reliable and predictable supply of replacement co components is necessary for NPPs to remain economically competitive and meet regulatory requirements and guidelines. Electrical and I and C components, in particular, have short product life cycles and obsolescence issues must be managed pro actively and not reactively in order to mitigate the risk to the NPP to ensure reliable and economic NPP operation. (Author)

  6. Lessons learned in the environmental qualification of class IE equipment at Tennessee Valley Authority

    International Nuclear Information System (INIS)

    Bell, R.N.; Akos, T.

    1985-01-01

    Tennessee Valley Authority has been engaged in an extensive program for the environmental qualification of Class 1E components. This program has been conducted in accordance with the requirements set forth in various industry standards and federal regulations, including IEEE 323-1971, IEEE 323-1974, Nuclear Regulatory Commission (NRC) IE Bulletin 7901B, NRC NUREG-0588, and the Code of Federal Regulations 10CFR50.49. Valuable lessons have been learned as a result of this program, particularly in the area of environmental qualification testing. This paper describes some unique experiences in the qualification testing of main steam isolation valve control manifold assemblies, control relays, and motor control centers

  7. Seismic qualification of nuclear equipment under multiple support excitations

    International Nuclear Information System (INIS)

    Neelwarne, A.; Kushwaha, H.S.; Kakodkar, A.

    1991-01-01

    ERS (Envelop Response Spectrum) is a conservative method for seismic analysis of equipment without overhang whereas it may severely underestimate the response, as compared to the time history response, for the case of overhanging equipment. However, MSRS (Multi Support Response Spectrum) method appears to give conservative results for both class of equipment. Inability to account a) magnification of response and b) contribution of antisymmetric modes resulting from relative support motion are found to be the reasons for unconservatism of ERS method. A simple criterion for selection of proper method, between ERS and MSRS, for the analysis of overhanging equipment is developed. The criterion is based on correlation of modal mass with the modal normal coordinate and is applicable to generalised equipment of non uniform mass and stiffness distribution. It is shown that; 1) MSRS method must be adopted if equipment first mode corresponds to vibration of overhanging masses. 2) MSRS method should be adopted if the modal mass for the first mode is less than 15 % of equipment mass. 3) Algebraic support group combination appears to give realistic results for the analysis of equipment. This is due to the dominant cantilever beam like behaviour of primary structure resulting in near in-phase motion at equipment supports. (author)

  8. Seismic qualification of equipment in operating nuclear power plants: Unresolved Safety Issue A-46

    International Nuclear Information System (INIS)

    Chang, T.Y.

    1987-02-01

    The margin of safety provided in existing nuclear power plant equipment to resist seismically induced loads and perform their intended safety functions may vary considerably, because of significant changes in design criteria and methods for the seismic qualification of equipment over the years. Therefore, the seismic qualification of equipment in operating plants must be reassessed to determine whether requalification is necessary. The objective of technical studies performed under the Task Action Plan A-46 was to establish an explicit set of guidelines and acceptance criteria to judge the adequacy of equipment under seismic loading at all operating plants, in lieu of requiring qualification to the current criteria that are applied to new plants. This report summarizes the work accomplished on USI A-46. In addition, the collection and review of seismic experience data and existing seismic test data are presented. Staff assessment of work accomplished under USI A-46 leads to the conclusion that the use of seismic experience data provides the most reasonable alternative to current qualification criteria. Consideration of seismic qualification by use of experience data was a specific task in USI A-46. Several other A-46 tasks serve to support the use of an experienced data base. The principal technical finding of USI A-46 is that seismic experience data, supplemented by existing seismic test data, applied in accordance with the guidelines developed, can be used to verify the seismic adequacy of mechanical and electrical equipment in operating nuclear plants. Explicit seismic qualification should be required only if seismic experience data or existing test data on similar components cannot be shown to apply

  9. Qualification of electric equipments for nuclear power plants

    International Nuclear Information System (INIS)

    Chauvin, G.; Raimondo, E.

    1983-03-01

    Description of the testing equipment, testing methods and standards of the resistance to seisms of electrical equipments (switches, pump motors, electrovalves, ...) for electronuclear power plants in France. Presentation of the French design and construction rules for electrical devices in the domestic and export nuclear market (resistance to thermodynamical and chemical stresses, to seisms, etc...) [fr

  10. Romanian-Canadian joint program for qualification of FCN as a CANDU fuel supplier

    International Nuclear Information System (INIS)

    Galeriu, C.A.; Andrei, G.; Bailescu, A.

    1995-01-01

    RENEL (Romania Power Authority), the co-ordinator of Romanian Nuclear Program, have decided to improve, starting 1990 the existing capability to produce CANDU nuclear fuel at FCN Pitesti. The objective of the program was defined with AAC (AECL - ANSALDO Consortium) for the qualification of FCN fuel plant according to Canadian Z299.2 standard. The Qualification Program was performed under AAC Work Order C-003. The co-ordination was assumed by AECL, as overall Design Authority. ZPI (Zircatec Precision Industries Inc., Canada), were designated to supply technical assistance, equipments and know how where necessary. After a preliminary verification of the FCN fuel plant, including the processes and system investigation, performed under AECL and ZPI assistance, the Qualification Program was defined in all details. The upgrading of documentation on all aspects required by Z299.2 was performed. Few processes needed to be reconsidered and equipment was delivered by ZPI or other suppliers. This includes mainly welding equipments and special inspection equipments. Health Physics was practically fully reconsidered. New equipment and practice were adapted to provide adequate control on health conditions. Every manufacturing and inspection process was checked to determine their performance during a Qualification Run based on acceptance criteria which have been established in the Qualification Plan. Manufacturing Demonstration Run was an important step to prove that all plant functions have been accomplished during the fabrication of 200 fuel bundles. These bundles have been fully accepted and 66 of them have been loaded in the first charge of Unit 1 Cemavoda NPS. The surveillance and audit actions made by AECL and ZPI during this period confirmed the FCN capability to operate an adequate system meeting the to required quality assurance standard. The very open attitude of AECL, Zircatec and FCN staff have stimulated the progress of the project and a successful achievement of the

  11. SRNL PHASE 1 Assessment Of The WTP Waste Qualification Program

    International Nuclear Information System (INIS)

    Peeler, D.; Hansen, E.; Herman, C.; Marra, S.; Wilmarth, B.

    2012-01-01

    The Hanford Tank Waste Treatment and Immobilization Plant (WTP) Project is currently transitioning its emphasis from an engineering design and construction phase toward facility completion, start-up and commissioning. With this transition, the WTP Project has initiated more detailed assessments of the requirements that must be met during the actual processing of the Hanford Site tank waste. One particular area of interest is the waste qualification program. In general, the waste qualification program involves testing and analysis to demonstrate compliance with waste acceptance criteria, determine waste processability, and demonstrate laboratory-scale unit operations to support WTP operations. The testing and analysis are driven by data quality objectives (DQO) requirements necessary for meeting waste acceptance criteria for transfer of high-level wastes from the tank farms to the WTP, and for ensuring waste processability including proper glass formulations during processing within the WTP complex. Given the successful implementation of similar waste qualification efforts at the Savannah River Site (SRS) which were based on critical technical support and guidance from the Savannah River National Laboratory (SRNL), WTP requested subject matter experts (SMEs) from SRNL to support a technology exchange with respect to waste qualification programs in which a critical review of the WTP program could be initiated and lessons learned could be shared. The technology exchange was held on July 18-20, 2011 in Richland, Washington, and was the initial step in a multi-phased approach to support development and implementation of a successful waste qualification program at the WTP. The 3-day workshop was hosted by WTP with representatives from the Tank Operations Contractor (TOC) and SRNL in attendance as well as representatives from the US DOE Office of River Protection (ORP) and the Defense Nuclear Facility Safety Board (DNFSB) Site Representative office. The purpose of the

  12. Impact of the draft DOE Training and Qualification Standard on an established training and qualification program

    International Nuclear Information System (INIS)

    Taylor, R.G.; Worley, C.A.

    1999-01-01

    One of the provisions of Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 97-2 was that the US Department of Energy (DOE) hor e llipsis Develop and institute ahor e llipsiscourse in criticality and criticality safety hor e llipsis to serve as the foundation for a program of formal qualification of criticality engineers. In response, a draft DOE standard establishing requirements for a formal qualification program for nuclear criticality safety (NCS) engineers has been prepared and is currently in review. The Oak Ridge Y-12 plant implemented a formal training and qualification program for NCS engineers in 1995. The program complies with existing DOE requirements. The program was developed using a performance-based systematic approach to training and is accomplished through structured mentoring where experienced personnel interact with candidates through various learning exercises. Self-study, exercises, and work under instruction are all utilized. The candidate's performance is evaluated by mentors and oral boards. Competency gained through experience at other sites can also be credited. Technical portions of the program are primarily contained in an initial Engineer-in-Training segment and in subsequent task-specific qualifications. The Engineer-in-Training segment exposes the candidate to fundamental NCS concepts through example problems; ensures the initial compliance training requirements are met; and includes readings from applicable procedures, technical documents, and standards. Upon completion of this initial training, candidates proceed to task qualifications. Tasks are defined NCS activities such as operational reviews, criticality safety evaluations, criticality safety computations, criticality accident alarm system (CAAS) evaluations, support for emergency management, etc. Qualification on a task basis serves to break up training into manageable pieces and expedites qualification of candidates to perform specific production activities. The

  13. Nuclear EQ sourcebook: A compilation of documents for nuclear equipment qualification

    International Nuclear Information System (INIS)

    Anon.

    1992-01-01

    In the nuclear power industry, environmental and seismic qualification of safety-related electrical and instrumentation equipment is collectively known as Equipment Qualification (EQ). Related technology, as well as regulatory requirements, have evolved rapidly during the last 15 years. For environmental qualification, what began in 1971 with one trial-use guide (IEEE Std 323-1971), now stands as a full complement of Nuclear Regulatory Commission (NRC) rules, guides and industry standards. In addition to the Institute of Electrical and Electronics Engineers (IEEE), the American Society of Mechanical Engineers (ASME) has also undertaken development of its own set of standards for use in qualifying safety-related mechanical equipment. To ensure that the original design and qualification is preserved, engineers need to select and use the correct set of NRC regulations, regulatory guides, industry standards, and generic correspondence. Given that the total number of these documents exceed 200, this task becomes resource intensive. This compilation is the first known publication available to serve the user-community need for a complete and exhaustive single source. Approximately 180 items (Bulletins, Federal Rules, Generic Letters, Notices, Regulatory Guides, IEEE Standards, IEEE Recommended Practices, and IEEE Guides) have been processed separately for inclusion on the data base

  14. Seismic qualification of equipment for the TA-55 Plutonium Processing Facility

    International Nuclear Information System (INIS)

    Pellette, P.R.; Endebrock, E.G.; Giles, P.M.; Shaw, R.H.

    1977-04-01

    The techniques employed by the Los Alamos Scientific Laboratory (LASL) for the seismic qualification of internal equipment for the TA-55 Plutonium Facility are discussed. The structural analysis of the plutonium building and critical associated structures was performed by the Architect-Engineer (A-E), and the calculations were checked by LASL. The specifications and procedures used by LASL produced dramatic improvement in the responses by qualified vendors to the seismic requirements. There was an increase from about a 20% bid ratio to greater than 90% because prospective vendors could be competitive without having had previous seismic experience with their equipment. The equipment seismic qualification for TA-55 is in compliance with the Code of Federal Regulations, Nuclear Regulatory Commission (NRC) Guides, Energy Research and Development Administration (ERDA) Manual Chapters and Appendices, and Institute of Electrical and Electronic Engineers (IEEE) Standard 344

  15. Qualification of class 1e equipment: regulation, technological margins and test experience

    International Nuclear Information System (INIS)

    Pasco, Y.; Le Meur, M.; Henry, J.Y.; Droger, J.P.; Morange, E.; Roubault, J.

    1986-10-01

    French regulation requires licensee to qualify electrical equipment important to safety for service in nuclear power plants to ensure that the equipment can perform its safety function under the set of plausible operating conditions. The French regulatory texts entitled Fundamental safety rules have classified safety related electrical equipment in three main categories: k1, k2, k3, according to their location and operating conditions. The definition of a design basis accident test profile must account for margins applied to thermal hydraulic code outputs. Specific safety margins was added to cover uncertainties in qualification test representativity. Up to now, accidental sequence studies have shown the validity of such a qualification test profile. On the other hand, the results from post accident simulation tests have shown that it is useful not only to validate post accident operating life but also to reveal failures initiated during previous tests [fr

  16. Nuclear power generating station equipment qualification method and apparatus

    International Nuclear Information System (INIS)

    Fero, A.H.; Potochnik, L.M.; Riling, R.W.; Semethy, K.F.

    1990-01-01

    This patent describes a method of monitoring an object piece of qualified equipment in a nuclear power plant. It comprises providing a first passive mimic means for mimicking the effect of radiation received by the object piece on the object piece; providing a second mimic means for mimicking the effect of a thermal history of the object piece on the object piece and mounting the first passive mimic means and the second mimic means in close proximity to the object piece

  17. Containment Response Analysis for Equipment Qualification of Kori Nuclear Power Plant Unit 3 and 4

    Energy Technology Data Exchange (ETDEWEB)

    Byun, Choong Sup; Song, Dong Soo; Hwang, Yong Jun [Korea Electric Power Research Institute, Taejon (Korea, Republic of); Seo, Kwi Hyun; Song, Wan Jung [ENERGEO Inc., Sungnam (Korea, Republic of)

    2006-07-01

    Equipment that is used to perform a necessary safety function must be capable of maintaining functional operability under all service condition postulated to occur during the installed life for the time it is required. The pressure and temperature analyses for loss of coolant accident and main steam line break accident provide the bounding test envelope inside containment for the operability evaluation of safety equipment in harsh environmental. This paper describes the results of the containment pressure and temperature analysis for the equipment qualification (EQ) envelopes of Kori unit 3 and 4.

  18. Qualification of a digital radiographic equipment for thin weld inspection

    International Nuclear Information System (INIS)

    Boulanger, G.; Furlan, J.

    1988-04-01

    The level of quality asked for welding plugs to fuel pins requires to test all the welds, that is to say about 200 000 welds of the fuel assemblies of the fast reactor Super-Phenix. X-ray radiography is one of the tests. Before the operation was done on a film by the personnel automatic selection of tested material and image processing are substituted to the film in the digital radiographic equipment IRENE. Main advantages are: elimination of human factor in defect appreciation, reliability of image processing and instant availability. On 1000 welds a good correlation is obtained between results on films and those of image processing [fr

  19. Qualification and training of personnel for nuclear equipment programmes

    International Nuclear Information System (INIS)

    Montagnier, S.

    1980-01-01

    The Equipment Department of Electricite de France has the task of designing, co-ordinating the construction of and commissioning the power stations required to feed the grid as part of the country's energy policity. The French nuclear programme may seem ambitious - 35.000 to 40.000 MW in service by 1985 - but it should be remembered that the first nuclear power plant construction in France goes back more than 20 years and that, as a result of this, the Equipment Department already has qualified staff at its disposal. Hence the proposed training activities take into account the educational background of such personnel and the number of persons concerned. These activities can be divided into (1) the professional orientation phase, intended for recently recruited staff members and consisting of discussion and instruction seminars aimed at facilitating the induction of the young recruit into EDF's departments, and (2) the training and retraining phase, intended for all staff in accordance with each person's particular job and made up, as the case may be, of courses in new theoretical knowledge, updating of previous knowledge, often accompanied by extensive practical work in the field, discussion of working methods, study of new operational techniques, and so forth. The teaching methods adopted naturally take into account the professional level of the trainees and are therefore usually 'active' or 'semi-active', entailing groups of the order of 12 persons, with effective participation by their supervisors. (author)

  20. Process and equipment qualification of the ceramic and metal waste forms for spent fuel treatment

    International Nuclear Information System (INIS)

    Marsden, Ken; Knight, Collin; Bateman, Kenneth; Westphal, Brian; Lind, Paul

    2005-01-01

    The electrometallurgical process for treating sodium-bonded spent metallic fuel at the Materials and Fuels Complex of the Idaho National Laboratory separates actinides and partitions fission products into two waste forms. The first is the metal waste form, which is primarily composed of stainless steel from the fuel cladding. This stainless steel is alloyed with 15w% zirconium to produce a very corrosion-resistant metal which binds noble metal fission products and residual actinides. The second is the ceramic waste form which stabilizes fission product-loaded chloride salts in a sodalite and glass composite. These two waste forms will be packaged together for disposal at the Yucca Mountain repository. Two production-scale metal waste furnaces have been constructed. The first is in a large argon-atmosphere glovebox and has been used for equipment qualification, process development, and process qualification - the demonstration of process reliability for production of the DOE-qualified metal waste form. The second furnace will be transferred into a hot cell for production of metal waste. Prototype production-scale ceramic waste equipment has been constructed or procured; some equipment has been qualified with fission product-loaded salt in the hot cell. Qualification of the remaining equipment with surrogate materials is underway. (author)

  1. Qualification test of Class 1E equipment based on IEEE323 Std 2003

    International Nuclear Information System (INIS)

    Kim, J. S.; Jung, S. C.; Kim, T. R.

    2004-01-01

    IEEE Standard for Qualifying Class 1E Equipment has been updated to 2003 edition since the issue of IEEE Std 323-1971, 1974, 1983. NRC approved the IEEE Std 323-1974 as Qualification standard of Class 1E Equipment in domestic nuclear power plant. IEEE Std 323-2003 was issued in September of 2003 and utility is waiting the approval of NRC. IEEE Std 323-2003 suggest a new qualification technique which adopts the condition monitoring. Performance of two transient during DBA test is no longer recommended in IEEE Std 323-2003. IEEE323 Std 2003 included a chapter of ''extension of Qualified life'' to make available the life extension of components during plant life extension. For the efficient control of preserving EQ in domestic nuclear power plant, IEEE323 Std 2003 is strongly recommended

  2. Environmental qualification - walkdowns: The documentation of configuration information for safety related components, equipment and systems

    International Nuclear Information System (INIS)

    Melmer, J.; Waters, M.

    1995-01-01

    Environmental Qualification walkdowns are conducted to collect field data to verify/validate/document configurations of safety related equipment and systems. This paper describes the process for conducting walkdowns and the justification for using an electronic format. The following are described: a) Background; b) Preparing, executing and processing walkdowns; c) Hardware/software; d) Impact of a paperless system on walkdown execution, maintenance and work planning; e) Other applications for the technology

  3. A new approach to determine the environmental qualification requirements for the safety related equipment

    International Nuclear Information System (INIS)

    Hasnaoui, C.; Parent, G.

    2000-01-01

    The objective of the environmental qualification of safety related equipment is to ensure that the plant defense-in-depth is not compromised by common mode failures following design basis accidents with a harsh environment. A new approach based on safety functions has been developed to determine what safety-related equipment is required to function during and after a design basis accident, as well as their environmental qualification requirements. The main feature of this approach is to use auxiliary safety functions established from safety requirements as credited in the safety analyses. This approach is undertaken in three steps: identification of the auxiliary safety functions of each main safety function; determination of the main equipment groups required for each auxiliary safety function; and review of the safety analyses for design basis accidents in order to determine the credited auxiliary safety functions and their mission times for each accident scenario. Some of the benefits of the proposed approach for the determination of the safety environmental qualification requirements are: a systematic approach for the review of safety analyses based on a safety function check list, and the insurance, with the availability of the safety functions, that Gentilly-2 defense-in-depth would not be compromised by design basis accidents with a harsh environment. (author)

  4. Nuclear Criticality Safety Organization qualification program. Revision 4

    International Nuclear Information System (INIS)

    Carroll, K.J.; Taylor, R.G.; Worley, C.A.

    1997-01-01

    The Nuclear Criticality Safety Organization (NCSO) is committed to developing and maintaining a staff of highly qualified personnel to meet the current and anticipated needs in Nuclear Criticality Safety (NCS) at the Oak Ridge Y-12 Plant. This document defines the Qualification Program to address the NCSO technical and managerial qualification as required by the Y-12 Training Implementation Matrix (TIM). It is implemented through a combination of LMES plant-wide training courses and professional nuclear criticality safety training provided within the organization. This Qualification Program is applicable to technical and managerial NCSO personnel, including temporary personnel, sub-contractors and/or LMES employees on loan to the NCSO, who perform the NCS tasks or serve NCS-related positions as defined in sections 5 and 6 of this program

  5. Nuclear criticality safety specialist training and qualification programs

    International Nuclear Information System (INIS)

    Hopper, C.M.

    1993-01-01

    Since the beginning of the Nuclear Criticality Safety Division of the American Nuclear Society (ANS) in 1967, the nuclear criticality safety (NCS) community has sought to provide an exchange of information at a national level to facilitate the education and development of NCS specialists. In addition, individual criticality safety organizations within government contractor and licensed commercial nonreactor facilities have developed training and qualification programs for their NCS specialists. However, there has been substantial variability in the content and quality of these program requirements and personnel qualifications, at least as measured within the government contractor community. The purpose of this paper is to provide a brief, general history of staff training and to describe the current direction and focus of US DOE guidance for the content of training and qualification programs designed to develop NCS specialists

  6. Interim staff position on environmental qualification of safety-related electrical equipment: including staff responses to public comments. Regulatory report

    International Nuclear Information System (INIS)

    Szukiewicz, A.J.

    1981-07-01

    This document provides the NRC staff positions regarding selected areas of environmental qualification of safety-related electrical equipment, in the resolution of Unresolved Safety Issue A-24, 'Qualification of Class IE Safety-Related Equipment.' The positions herein are applicable to plants that are or will be in the construction permit (CP) or operating license (OL) review process and that are required to satisfy the requirements set forth in either the 1971 or the 1974 version of IEEE-323 standard

  7. Hanford Waste Vitrification Plant Project Waste Form Qualification Program Plan

    International Nuclear Information System (INIS)

    Randklev, E.H.

    1993-06-01

    The US Department of Energy has created a waste acceptance process to help guide the overall program for the disposal of high-level nuclear waste in a federal repository. This Waste Form Qualification Program Plan describes the hierarchy of strategies used by the Hanford Waste Vitrification Plant Project to satisfy the waste form qualification obligations of that waste acceptance process. A description of the functional relationship of the participants contributing to completing this objective is provided. The major activities, products, providers, and associated scheduling for implementing the strategies also are presented

  8. Application of quality assurance program to safety related aging equipment or components

    International Nuclear Information System (INIS)

    Papaiya, N.C.

    1990-01-01

    This paper addresses how quality assurance programs and their criteria are applied to safety related and aging equipment or components used in commercial nuclear plant applications. The QA Programs referred to are 10CFR50 Appendix B and EPRI NP-5652. The QA programs as applicable are applied to equipment/component aging qualification, preventive maintenance, surveillance testing and procurement engineering. The intent of this paper is not the technical issues, methods and research of aging. The paper addresses QA program's application to age-related equipment or components in safety related applications. Quality Assurance Program 10CFR50 Appendix B applies to all safety related aging components or equipment related to the qualification program and associated preventive maintenance and surveillance testing programs. Quality Assurance involvement with procurement engineering for age-related commercial grade items supports EPRI NP-5652 and assures that the dedicated OGI is equal to the item purchased as a basic component to 10CFR50 Appendix B requirements

  9. Impact of power uprate on environmental qualification of equipment in nuclear power plants

    International Nuclear Information System (INIS)

    Raheja, R.D.; Mohiuddin, A.; Alsammarae, A.

    1996-01-01

    Many nuclear power facilities are finding it economically beneficial to increase reactor output, from operating plants, by resorting to power uprates. A power uprate implies that a utility can increase the reactor output, or the megawatts generated, by increasing steam pressure without adding or changing any plant systems. This is perhaps one of the least expensive options for increasing the generating capacity of a power plant. However, a nuclear plant requires a comprehensive review of the plant systems, structures and components to assure their capability to withstand the resulting increased normal and accident plant conditions. A power uprate will typically result in a plant operating at higher than the originally designed environmental conditions. Safety related equipment in nuclear plants is presently qualified to the UFSAR Chapter 15 accident events and the resulting temperatures, pressures, radiation levels etc. These values will increase when the reactor is producing a higher MWe output. Components that are sensitive to the environment must be re-evaluated and assessed to determine their acceptability and operability under the revised environmental conditions. Most safety-related mechanical and electrical equipment will require an assessment from an environmental qualification standpoint. Utilities must perform this task in a systematic, auditable and cost effective manner to optimize their resources and minimize plant costs associated with modifications, replacements or equipment testing. This paper discusses various approaches and provides recommendations to achieve equipment qualification while satisfying the plant's objective of a power uprate

  10. The process control and management on equipment qualification of nuclear power plant

    International Nuclear Information System (INIS)

    Liu Dong; Wang Hongyin; Zhang Yong

    2013-01-01

    The equipment qualification (EQ) to the safety class equipment is an important safety measure for the nuclear power plants (NPP), and also reflects the nuclear safety culture. Along with the continuous constructions of NPP in China, it has become an important issue for NPP engineering company and equipment suppliers how to effectively establish standard EQ process control and management, and provide sufficient technical arrangements to maintain this EQ management system. This paper summarizes three process of EQ including Design Input, EQ Establishment and EQ Maintenance, proposes the measures and key points for EQ process control and management in phase of NPP construction, and introduces the documents management during the whole process of EQ. (authors)

  11. Development of generic floor response spectra for equipment qualification for seismic loads

    International Nuclear Information System (INIS)

    Curren, J.R.; Costantino, C.J.

    1984-01-01

    A generic floor response spectra has been developed for use in the qualification of electrical and mechanical equipment in operating nuclear power plants. Actual PWR and BWR - Mark I structural models were used as representative of a class of structures. For each model, the stiffness properties were varied, with the same mass, so as to extend the fundamental base structure natural frequency from 2 cps to 36 cps. This resulted in fundamental mode coupled natural frequencies as low as 0.86 cps and as high as 30 cps. The characteristics of 1000 floor response spectra were studied to determine the generic spectra. A procedure for its application to any operating plant has been established. The procedure uses as much or as little information that currently exists at the plant relating to the question of equipment qualification. A generic floor response spectra is proposed for the top level of a generic structure. Reduction factors are applied to the peak acceleration for equipment at lower levels

  12. Development of generic floor response spectra for equipment qualification for seismic loads

    International Nuclear Information System (INIS)

    Curreri, J.R.; Costantino, C.J.

    1984-10-01

    A generic floor response spectra has been developed for use in the qualification of electrical and mechanical equipment in operating nuclear power plants. Actual PWR and BWR - Mark I structural models were used as representative of a class of structures. For each model, the stiffness properties were varied, with the same mass, so as to extend the fundamental base structure natural frequency from 2 cps to 36 cps. This resulted in fundamental mode coupled natural frequencies as low as 0.86 cps and as high as 30 cps. The characteristics of 1000 floor response spectra were studied to determine the generic spectra. A procedure for its application to any operating plant has been established. The procedure uses as much or as little information that currently exists at the plant relating to the question of equipment qualification. A generic floor response spectra is proposed for the top level of a generic structure. Reduction factors are applied to the peak acceleration for equipment at lower levels

  13. Supplement to nuclear EQ sourcebook: A compilation of documents for nuclear equipment qualification

    International Nuclear Information System (INIS)

    Anon.

    1993-01-01

    In the nuclear power industry, environmental and seismic qualification of safety-related electrical and instrumentation equipment is collectively known as Equipment Qualification (EQ). Related technology, as well as regulatory requirements, have evolved rapidly during the last 15 years. For environmental qualification, what began in 1971 with one trial-use guide (IEEE Std 323-1971), now stands as a full complement of Nuclear Regulatory Commission (NRC) rules, guides, and industry standards. As the original 1992 version of the Nuclear EQ Sourcebook was compiled to serve the user-community need for a complete and exhaustive single source of nuclear EQ documentation, this Supplement is published to provide the user community with nuclear EQ documentation revisions and updates that have been published since the publication of the original volume in May of 1992. The first volume of this publication included documents issued before December, 1991. That first volume was well received and also prompted positive response from industry on its usefulness and on recommendations to improve the completeness and enhance the ease of use. This Supplement, therefore, includes new documents, revisions, and updates issued and published since December 1991 and up to and including March 1993. It incorporates various enhancements in order to better serve the user community. One such enhancement included in this Supplement is the new Equipment Classification Index that is described in the User Guide section of this publication. 37 papers, including Bulletins, Federal rules, Generic Letters, Notices, Regulatory Guides, IEEE Standards, IEEE Recommended Practices, and IEEE Guides, have been processed separately for inclusion on the data base

  14. Seismic qualification of equipment in operating nuclear power plants. Unresolved safety issue A-46, draft report for comment

    International Nuclear Information System (INIS)

    Chang, T.Y.

    1985-08-01

    The margin of safety provided in existing nuclear power plant equipment to resist seismically induced loads and perform their intended safety functions may vary considerably, because of significant changes in design criteria and methods for the seismic qualification of equipment over the years. Therefore, the seismic qualification of equipment in operating plants should be reassessed to determine whether requalification is necessary. The objective of technical studies performed under the Task Action Plan A-46 was to establish an explicit set of guidelines and acceptance criteria to judge the adequacy of equipment under seismic loading at all operating plants, in lieu of requiring qualification to the current criteria that are applied to new plants. This report summarizes the work accomplished on USI A-46 by the Nuclear Regulatory Commission staff and its contractors, Idaho National Engineering Laboratory, Southwest Research Institute, Brookhaven National Laboratory, and Lawrence Livermore National Laboratory. In addition, the collection and review of seismic experience data by the Seismic Qualification Utility Group and the review and recommendations of a group of seismic consultants, the Senior Seismic Review Advisory Panel, are presented. Staff assessment of work accomplished under USI A-46 leads to the conclusion that the use of seismic experience data provides the most reasonable alternative to current qualification criteria. Consideration of seismic qualification by use of experience data was a specific task in USI A-46. Several other A-46 tasks serve to support the use of an experience data base

  15. U-Mo fuel qualification program in HANARO

    International Nuclear Information System (INIS)

    Lee, K.H.; Lee, C.S.; Kim, H.R.; Kuk, I.H.; Kim, C.K.

    2000-01-01

    Atomized U-Mo fuel has shown good performance from the results of previous out-of-pile tests and post-irradiation examinations. A qualification program of rod type U-Mo fuel is in progress and the fuel will be irradiated in HANARO. 6 gU/cm 3 U-7Mo, U-8Mo and U-9Mo are considered in this program. The laboratory test results of porosity, mechanical property, thermal conductivity, and thermal compatibility test are discussed in this paper. In parallel with this qualification program, the feasibility study on the core conversion from the present U 3 Si fuel to U-Mo in HANARO will be initiated to provide technical bases for the policy making. Several options of core conversion for HANARO are proposed and each option will be addressed briefly in terms of the operation policy, fuel management, and licensing of HANARO. (author)

  16. Maintenance program guidelines for programmatic equipment

    International Nuclear Information System (INIS)

    1994-11-01

    The Division Directors at Lawrence Berkeley Laboratory are responsible for implementing a maintenance program for research equipment (also referred to as programmatic equipment) assigned to them. The program must allow maintenance to be accomplished in a manner that promotes operational safety, environmental protection and compliance, and cost effectiveness; that preserves the intended functions of the facilities and equipment; and that supports the programmatic mission of the Laboratory. Programmatic equipment -- such as accelerators, lasers, radiation detection equipment, and glove boxes -- is dedicated specifically to research. Installed equipment, by contrast, includes the mechanical and electrical systems installed as part of basic building construction, equipment essential to the normal functioning of the facility and its intended use. Examples of installed equipment are heating, ventilating, and air conditioning systems; elevators; and communications systems. The LBL Operating and Assurance Program Plan (PUB-3111, Revision 4) requires that a maintenance program be prepared for programmatic equipment and defines the basic maintenance program elements. Such a program of regular, documented maintenance is vital to the safety and quality of research activities. As a part of that support, this document offers guidance to Laboratory organizations for developing their maintenance programs. It clarifies the maintenance requirements of the Operating and Assurance Program (OAP) and presents an approach that, while not the only possibility, can be expected to produce an effective maintenance program for research equipment belonging to the Laboratory's organizations

  17. IEEE 693 seismic qualification of composites for substation high-voltage equipment

    Energy Technology Data Exchange (ETDEWEB)

    Schiff, A.J. [Precision Measurement Instruments, Los Altos Hills, CA (United States); Kempner, L.Jr. [Bonneville Power Administration, Vancouver, BC (Canada)

    2004-07-01

    Standard 693-1997 of the Institute of Electrical and Electronic Engineers (IEEE) is the recommended practice for seismic design of substations. It represents a significant improvement in the way the power industry seismically qualifies substation high-voltage equipment. This paper described the use of IEEE Standard 693 for hollow-core composite insulators that are used on high-voltage transformers and demonstrated that changes are warranted. The following four failure modes associated with the composite insulator were discussed: bond degradation, bond failure, tube degradation and tube layer delamination. The authors evaluated the IEEE 693 qualification procedure of time history shake-table and static-pull tests and were concerned about acceptance criteria. It was shown that acceptance criteria are not valid for qualifying hollow-core composites and that static-pull tests are needed after the vibration qualification tests are completed. It was suggested that more research is warranted to determine if bonding at the top part of the flange can be eliminated, thereby eliminating bond degradation. The resulting increase in system damping would improve the dynamic response of the unit. 1 ref., 10 figs.

  18. ITER tungsten divertor design development and qualification program

    Energy Technology Data Exchange (ETDEWEB)

    Hirai, T., E-mail: takeshi.hirai@iter.org [ITER Organization, Route de Vinon sur Verdon, F-13115 Saint Paul lez Durance (France); Escourbiac, F.; Carpentier-Chouchana, S.; Fedosov, A.; Ferrand, L.; Jokinen, T.; Komarov, V.; Kukushkin, A.; Merola, M.; Mitteau, R.; Pitts, R.A.; Shu, W.; Sugihara, M. [ITER Organization, Route de Vinon sur Verdon, F-13115 Saint Paul lez Durance (France); Riccardi, B. [F4E, c/ Josep Pla, n.2, Torres Diagonal Litoral, Edificio B3, E-08019 Barcelona (Spain); Suzuki, S. [JAEA, Fusion Research and Development Directorate JAEA, 801-1 Mukouyama, Naka, Ibaragi 311-0193 (Japan); Villari, R. [Associazione EURATOM-ENEA sulla Fusione, Via Enrico Fermi 45, I-00044 Frascati, Rome (Italy)

    2013-10-15

    Highlights: • Detailed design development plan for the ITER tungsten divertor. • Latest status of the ITER tungsten divertor design. • Brief overview of qualification program for the ITER tungsten divertor and status of R and D activity. -- Abstract: In November 2011, the ITER Council has endorsed the recommendation that a period of up to 2 years be set to develop a full-tungsten divertor design and accelerate technology qualification in view of a possible decision to start operation with a divertor having a full-tungsten plasma-facing surface. To ensure a solid foundation for such a decision, a full tungsten divertor design, together with a demonstration of the necessary high performance tungsten monoblock technology should be completed within the required timescale. The status of both the design and technology R and D activity is summarized in this paper.

  19. Generation of floor spectra compatible time histories for equipment seismic qualification in nuclear power plants

    International Nuclear Information System (INIS)

    Shyu, Y.-S.; Luh, Gary G.; Blum, Arie

    2004-01-01

    This paper proposes a procedure for generating floor response spectra compatible time histories used for equipment seismic qualification in nuclear power plants. From the 84th percentile power spectrum density function of an earthquake ensemble of four randomly generated time history motions, a statistically equivalent time history can be obtained by converting the power spectrum density function from the frequency domain into the time domain. With minor modification, if needed, the converted time history will satisfy both the spectral and the power spectrum density enveloping criteria, as required by the USNRC per Revision 2 of the Standard Review Plan, Section 3.7.1. Step-by-step generating procedures and two numerical examples are presented to illustrate the applications of the methodology. (author)

  20. The effect of plant aging on equipment qualification and human performance issues related to license renewal

    International Nuclear Information System (INIS)

    Gunther, W.E.; Higgins, J.C.; Aggarwal, S.K.

    1991-01-01

    The aging of nuclear power plants is one of the most important issues facing the nuclear industry worldwide. Aging encompasses as forms of degradation to nuclear power plant components, systems, and structures that result from exposure to environmental conditions or from operational stresses. Both the degradation from aging and actions taken to address the aging, such as increased maintenance and testing, can significantly impact human performance in the plant. Research into the causes and effects of aging as obtained through the assessment of operating experience and testing have raised questions regarding the adequacy of existing industry standards for addressing the concerns raised by this research. This paper discusses these issues, with particular emphasis in the area of equipment qualification and human performance

  1. The effect of plant aging on equipment qualification and human performance issues related to license renewal

    Energy Technology Data Exchange (ETDEWEB)

    Gunther, W.E.; Higgins, J.C. [Brookhaven National Lab., Upton, NY (United States); Aggarwal, S.K. [Nuclear Regulatory Commission, Washington, DC (United States)

    1991-12-31

    The aging of nuclear power plants is one of the most important issues facing the nuclear industry worldwide. Aging encompasses as forms of degradation to nuclear power plant components, systems, and structures that result from exposure to environmental conditions or from operational stresses. Both the degradation from aging and actions taken to address the aging, such as increased maintenance and testing, can significantly impact human performance in the plant. Research into the causes and effects of aging as obtained through the assessment of operating experience and testing have raised questions regarding the adequacy of existing industry standards for addressing the concerns raised by this research. This paper discusses these issues, with particular emphasis in the area of equipment qualification and human performance.

  2. The effect of plant aging on equipment qualification and human performance issues related to license renewal

    Energy Technology Data Exchange (ETDEWEB)

    Gunther, W.E.; Higgins, J.C. (Brookhaven National Lab., Upton, NY (United States)); Aggarwal, S.K. (Nuclear Regulatory Commission, Washington, DC (United States))

    1991-01-01

    The aging of nuclear power plants is one of the most important issues facing the nuclear industry worldwide. Aging encompasses as forms of degradation to nuclear power plant components, systems, and structures that result from exposure to environmental conditions or from operational stresses. Both the degradation from aging and actions taken to address the aging, such as increased maintenance and testing, can significantly impact human performance in the plant. Research into the causes and effects of aging as obtained through the assessment of operating experience and testing have raised questions regarding the adequacy of existing industry standards for addressing the concerns raised by this research. This paper discusses these issues, with particular emphasis in the area of equipment qualification and human performance.

  3. On the evolution of the regulatory guidance for seismic qualification of electric and active mechanical equipment for nuclear power plants

    International Nuclear Information System (INIS)

    Ng, Ching Hang; Chen, Pei-Ying

    2009-01-01

    All electric and active mechanical equipment important to safety for nuclear power plants must be seismically qualified by testing, analysis, or combined analysis and testing. The general requirements for seismic qualification of electric and active mechanical equipment in nuclear power plants are delineated in Appendix S, 'Earthquake Engineering Criteria for Nuclear Power Plants,' to Title 10, Part 50, 'Domestic Licensing of Production and Utilization Facilities,' of the Code of Federal Regulations (10 CFR Part 50), item 52.47(20) of 10 CFR 52.47, 'Contents of Applications; Technical Information,' and Appendix A, 'Seismic and Geologic Siting Criteria for Nuclear Power Plants,' to 10 CFR Part 100, 'Reactor Site Criteria.' The United States Nuclear Regulatory Commission (NRC) issued Revision 2 of Regulatory Guide (RG) 1.100, 'Seismic Qualification of Electric and Mechanical for Nuclear Power Plants' in 1988, which endorsed, with restrictions, exceptions, and clarifications, Institute of Electrical and Electronics Engineers (IEEE) Standard 344-1987 'IEEE Recommended Practice for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations,' for use in seismic qualification of both electric and mechanical equipment. In 2008, the staff at the NRC drafted Revision 3 of RG 1.100 to endorse, with restrictions, exceptions, and clarifications, the IEEE Std 344-2004 and the American Society of Mechanical Engineers (ASME) QME-1-2007 'Qualification of Active Mechanical Equipment Used in Nuclear Power Plants.' IEEE Std 344-2004 was an update of Std 344-1987 and ASME QME-1-2007 was an update of QME-1-2002. The major changes in IEEE Std 344-2004 and ASME QME-1-2007 include the update and expansion of criteria and procedures describing the use of experience data as a method for seismic qualification of Class 1E electric equipment (including I and C components) as well as active mechanical equipment. In this paper, the staff will compare the draft Revision 3 to

  4. Typical design/qualification acceptance criteria for newly installed pipelines and equipment components of VVER-type NPPs

    International Nuclear Information System (INIS)

    Masopust, R.

    2003-01-01

    This paper describes in general the typical design/qualification acceptance criteria and seismic acceptance criteria in particular that are applicable for important to safety newly installed pipelines and equipment components of VVER-type already existing NPPs, specifically during the design verification phase of this newly installed equipment. These criteria are currently used for VVER 440-213 and VVER 1000 NPPs in Czech Republic and in Slovakia. The similar criteria are also used in Hungary. (author)

  5. Computer code qualification program for the Advanced CANDU Reactor

    International Nuclear Information System (INIS)

    Popov, N.K.; Wren, D.J.; Snell, V.G.; White, A.J.; Boczar, P.G.

    2003-01-01

    Atomic Energy of Canada Ltd (AECL) has developed and implemented a Software Quality Assurance program (SQA) to ensure that its analytical, scientific and design computer codes meet the required standards for software used in safety analyses. This paper provides an overview of the computer programs used in Advanced CANDU Reactor (ACR) safety analysis, and assessment of their applicability in the safety analyses of the ACR design. An outline of the incremental validation program, and an overview of the experimental program in support of the code validation are also presented. An outline of the SQA program used to qualify these computer codes is also briefly presented. To provide context to the differences in the SQA with respect to current CANDUs, the paper also provides an overview of the ACR design features that have an impact on the computer code qualification. (author)

  6. IE Bulletin No. 79-01: Environmental qualification of Class IE equipment

    International Nuclear Information System (INIS)

    Anon.

    1993-01-01

    The intent of IE Circular 78-08 was to highlight to all licensees important lessons learned from environmental qualification deficiencies reported by individual licensees. In this regard, licensees were requested to examine installed safety-related electrical equipment and determine that proper documentation existed which provided assurance that this equipment would function under postulated accident conditions. The intent of this Bulletin is to raise the threshold of IE Circular 78-08 to the level of a Bulletin; i.e., action requiring a licensee response. Inspections conducted to date by the NRC of licensees' activities in response to IE Circular 78-08 have identified one component which licensees have found to be unqualified for service within the LOCA environment. Specifically, unqualified stem mounted limit switches (SMLS), other than those identified in previously issued IE Bulletin 78-04, were found to be installed on safety-related valves inside containment at both Duane Arnold and Quad Cities 1 and 2 Nuclear Generating Stations. According to the manufacturer, these switches are designed only for general purpose applications and are not considered suitable devices for service in the LOCA environment. Consequently, switches are being replaced at the above power plants with qualified components

  7. Training and qualification program for nuclear criticality safety technical staff

    International Nuclear Information System (INIS)

    Taylor, R.G.; Worley, C.A.

    1996-01-01

    A training and qualification program for nuclear criticality safety technical staff personnel has been developed and implemented. The program is compliant with requirements and provides evidence that a systematic approach has been taken to indoctrinate new technical staff. Development involved task analysis to determine activities where training was necessary and the standard which must be attained to qualify. Structured mentoring is used where experienced personnel interact with candidates using checksheets to guide candidates through various steps and to provide evidence that steps have been accomplished. Credit can be taken for the previous experience of personnel by means of evaluation boards which can credit or modify checksheet steps. Considering just the wealth of business practice and site specific information a new person at a facility needs to assimilate, the program has been effective in indoctrinating new technical staff personnel and integrating them into a productive role. The program includes continuing training

  8. Equipment Reliability Program in NPP Krsko

    International Nuclear Information System (INIS)

    Skaler, F.; Djetelic, N.

    2006-01-01

    Operation that is safe, reliable, effective and acceptable to public is the common message in a mission statement of commercial nuclear power plants (NPPs). To fulfill these goals, nuclear industry, among other areas, has to focus on: 1 Human Performance (HU) and 2 Equipment Reliability (EQ). The performance objective of HU is as follows: The behaviors of all personnel result in safe and reliable station operation. While unwanted human behaviors in operations mostly result directly in the event, the behavior flaws either in the area of maintenance or engineering usually cause decreased equipment reliability. Unsatisfied Human performance leads even the best designed power plants into significant operating events, which can be found as well-known examples in nuclear industry. Equipment reliability is today recognized as the key to success. While the human performance at most NPPs has been improving since the start of WANO / INPO / IAEA evaluations, the open energy market has forced the nuclear plants to reduce production costs and operate more reliably and effectively. The balance between these two (opposite) goals has made equipment reliability even more important for safe, reliable and efficient production. Insisting on on-line operation by ignoring some principles of safety could nowadays in a well-developed safety culture and human performance environment exceed the cost of electricity losses. In last decade the leading USA nuclear companies put a lot of effort to improve equipment reliability primarily based on INPO Equipment Reliability Program AP-913 at their NPP stations. The Equipment Reliability Program is the key program not only for safe and reliable operation, but also for the Life Cycle Management and Aging Management on the way to the nuclear power plant life extension. The purpose of Equipment Reliability process is to identify, organize, integrate and coordinate equipment reliability activities (preventive and predictive maintenance, maintenance

  9. Equipment Qualification and Environment Establishment for COTS Dedication of Safety Grade PC

    International Nuclear Information System (INIS)

    Ahn, Kwang Chul; Bin, Chang Sun; Kwon, Yoon Kwang; Kang, Shin Woo; Koh, Sung Won; Shon, Eui Chan; Jang, Hyun Doo; Song, Il Sup; Lee, Hyun Noh

    2010-08-01

    Safety grade PCs are required for protection systems of SKN 3 and 4 nuclear power plant and subsequent plants. Commercial grade item (CGI) dedication should be carried out to utilize a commercial PC as a safety grade PC of nuclear power plants. This project is aimed to perform the equipment qualification of the commercial PC, and review and improve the quality system of the PC supplier. As a result of the EQ for the CGI dedication, selected military PCs have passed the environment test, the seismic test, and the EMI test required for the digital controllers of nuclear plants. In addition, a walk-through of the quality system of the PC supplier, ISO 9001, was carried out and the quality system was improved. History data for the PC was gathered. As the analysis of the history data showed that operating experience time of the PC is longer than the plant life time, the history data could be used as an evidence of acceptance. After dedicated according to the CGI dedication process, military rugged PCs could be used for safety grade PCs

  10. 76 FR 9376 - Proposed Extension of Existing Information Collection on Qualification/Certification Program and...

    Science.gov (United States)

    2011-02-17

    ... Extension of Existing Information Collection on Qualification/Certification Program and Man Hoist Operators... 77.107-1 on Qualification/Certification Program and Man Hoist Operators Physical Fitness. DATES: All... Labor or Secretary of Health and Human Services must make frequent inspections and investigations in...

  11. SRNL Phase 1 Assessment Of The WAC/DQO And Unit Operations For The WTP Waste Qualification Program

    International Nuclear Information System (INIS)

    Peeler, D.; Adamson, D.; Bannochie, C.; Cozzi, A.; Eibling, R.; Hay, M.; Hansen, E.; Herman, D.; Martino, C.; Nash, C.; Pennebaker, F.; Poirier, M.; Reboul, S.; Stone, M.; Taylor-Pashow, K.; White, T.; Wilmarth, B.

    2012-01-01

    The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is currently transitioning its emphasis from a design and construction phase toward start-up and commissioning. With this transition, the WTP Project has initiated more detailed assessments of the requirements related to actual processing of the Hanford Site tank waste. One particular area of interest is the waste qualification program to be implemented to support the WTP. Given the successful implementation of similar waste qualification efforts at the Savannah River Site (SRS), based on critical technical support and guidance from the Savannah River National Laboratory (SRNL), WTP requested the utilization of subject matter experts from SRNL to support a technology exchange to perform a review of the WTP waste qualification program, discuss the general qualification approach at SRS, and to identify critical lessons learned through the support of DWPF's sludge batch qualification efforts. As part of Phase 1, SRNL subject matter experts in critical technical and/or process areas reviewed specific WTP waste qualification information. The Phase 1 review was a collaborative, interactive, and iterative process between the two organizations. WTP provided specific analytical procedures, descriptions of equipment, and general documentation as baseline review material. SRNL subject matter experts reviewed the information and, as appropriate, requested follow-up information or clarification to specific areas of interest. This process resulted in multiple teleconferences with key technical contacts from both organizations resolving technical issues that lead to the results presented in this report. This report provides the results of SRNL's Phase 1 review of the WAC-DQO waste acceptance criteria and processability parameters, and the specific unit operations which are required to support WTP waste qualification efforts. The review resulted in SRNL providing concurrence, alternative methods, or gap identification

  12. SRNL PHASE 1 ASSESSMENT OF THE WAC/DQO AND UNIT OPERATIONS FOR THE WTP WASTE QUALIFICATION PROGRAM

    Energy Technology Data Exchange (ETDEWEB)

    Peeler, D.; Adamson, D.; Bannochie, C.; Cozzi, A.; Eibling, R.; Hay, M.; Hansen, E.; Herman, D.; Martino, C.; Nash, C.; Pennebaker, F.; Poirier, M.; Reboul, S.; Stone, M.; Taylor-Pashow, K.; White, T.; Wilmarth, B.

    2012-05-16

    The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is currently transitioning its emphasis from a design and construction phase toward start-up and commissioning. With this transition, the WTP Project has initiated more detailed assessments of the requirements related to actual processing of the Hanford Site tank waste. One particular area of interest is the waste qualification program to be implemented to support the WTP. Given the successful implementation of similar waste qualification efforts at the Savannah River Site (SRS), based on critical technical support and guidance from the Savannah River National Laboratory (SRNL), WTP requested the utilization of subject matter experts from SRNL to support a technology exchange to perform a review of the WTP waste qualification program, discuss the general qualification approach at SRS, and to identify critical lessons learned through the support of DWPF's sludge batch qualification efforts. As part of Phase 1, SRNL subject matter experts in critical technical and/or process areas reviewed specific WTP waste qualification information. The Phase 1 review was a collaborative, interactive, and iterative process between the two organizations. WTP provided specific analytical procedures, descriptions of equipment, and general documentation as baseline review material. SRNL subject matter experts reviewed the information and, as appropriate, requested follow-up information or clarification to specific areas of interest. This process resulted in multiple teleconferences with key technical contacts from both organizations resolving technical issues that lead to the results presented in this report. This report provides the results of SRNL's Phase 1 review of the WAC-DQO waste acceptance criteria and processability parameters, and the specific unit operations which are required to support WTP waste qualification efforts. The review resulted in SRNL providing concurrence, alternative methods, or gap

  13. Isotope Brayton ground demonstration testing and flight qualification. Volume 1. Technical program

    Energy Technology Data Exchange (ETDEWEB)

    1974-12-09

    A program is proposed for the ground demonstration, development, and flight qualification of a radioisotope nuclear heated dynamic power system for use on space missions beginning in the 1980's. This type of electrical power system is based upon and combines two aerospace technologies currently under intense development; namely, the MHW isotope heat source and the closed Brayton cycle gas turbine. This power system represents the next generation of reliable, efficient economic electrical power equipment for space, and will be capable of providing 0.5 to 2.0 kW of electric power to a wide variety of spacecraft for earth orbital and interplanetary missions. The immediate design will be based upon the requirements for the Air Force SURVSATCOM mission. The proposal is presented in three volumes plus an Executive Summary. This volume describes the tasks in the technical program.

  14. Used energy-related laboratory equipment grant program for institutions of higher learning. Eligible equipment catalog

    Energy Technology Data Exchange (ETDEWEB)

    1994-07-01

    This is a listing of energy related equipment available through the Energy-Related Laboratory Equipment Grant Program which grants used equipment to institutions of higher education for energy-related research. Information included is an overview of the program, how to apply for a grant of equipment, eligibility requirements, types of equipment available, and the costs for the institution.

  15. Comparison and Analysis of IEEE 344 and IEC 60980 standards for harmonization of seismic qualification of safety-related equipment

    International Nuclear Information System (INIS)

    Lee, Young Ok; Kim, Jong Seog; Seo, Jeong Ho; Kim, Myung Jun

    2011-01-01

    The seismic qualification of safety related equipment in nuclear power plants should demonstrate an equipment's ability to perform its safety function during/or after the time it is subjected to the forces resulting from one SSE. In addition, the equipment must withstand the effects of a number of OBEs, preceding the SSE. IEEE 344 and IEC 60980 present the criteria for establishing procedures demonstrating that the Class 1E equipment can meet its performance requirement during seismic events. Currently, IEEE 344 is used for regulation of nuclear power plant in the United State whereas IEC 60980 is mainly used in Europe. In particular, NPPs of France and China apply with RCC-E and GB that are domestic standards, respectively. Equipment supplier and Utility have difficulties because of different applicable standards. Equipment supplier to export S/R components/equipment to other standard area performs additional seismic qualification. For example, equipment are qualifies according to IEC 60980, RCC-E, GB although they have been qualified in accordance with IEEE 344. Also, utility to attempt power up-rate, life extension of NPP constructed under rules of RCC-E such as Ulchin NPP 1 and 2 has similar difficulties. RCC-E endorses IEC 60980 and GB is almost same as IEC 60980 except minor difference of earthquake environment definition. Therefore this paper surveys the similarities and differences between IEEE 344 and IEC 60980. In addition, this paper considers how the two sets of standards may be used in a complementary fashion to be possible using one or the other standard area

  16. Regulatory analysis for resolution of Unresolved Safety Issue A-46, seismic qualification of equipment in operating plants

    International Nuclear Information System (INIS)

    Chang, T.Y.; Anderson, N.R.

    1987-02-01

    The margin of safety provided in existing nuclear power plant equipment to resist seismically induced loads and perform required safety functions may vary considerably, because of significant changes in design criteria and methods for the seismic qualification of equipment over the years. Therefore, the seismic qualification of equipment in operating plants must be reassessed to determine whether requalification is necessary. The objective of technical studies performed under Task Action Plan A-46 was to establish an explicit set of guidelines and acceptance criteria to judge the adequacy of equipment under seismic loading at all operating plants, in lieu of requiring these plants to meet the criteria that are applied to new plants. This report presents the regulatory analysis for Unresolved Safety Issue (USI) A-46. It includes: Statement of the Problem; the Objective of USI A-46; a Summary of A-46 Tasks; a Proposed Implementation Procedure; a Value-Impact Analysis; Application of the Backfit Rule; 10 CFR 50.109; Implementation; and Operating Plants To Be Reviewed to USI A-46 Requirements

  17. 14 CFR 121.909 - Approval of Advanced Qualification Program.

    Science.gov (United States)

    2010-01-01

    ... criteria. Each AQP must have separate curriculums for indoctrination, qualification, and continuing... the training and evaluation of CRM and technical skills and knowledge. An application for approval of... must meet all the requirements of this subpart. (2) Each indoctrination, qualification, and continuing...

  18. Commercial Spacewalking: Designing an EVA Qualification Program for Space Tourism

    Science.gov (United States)

    Gast, Matthew A.

    2010-01-01

    In the near future, accessibility to space will be opened to anyone with the means and the desire to experience the weightlessness of microgravity, and to look out upon both the curvature of the Earth and the blackness of space, from the protected, shirt-sleeved environment of a commercial spacecraft. Initial forays will be short-duration, suborbital flights, but the experience and expertise of half a century of spaceflight will soon produce commercial vehicles capable of achieving low Earth orbit. Even with the commercial space industry still in its infancy, and manned orbital flight a number of years away, there is little doubt that there will one day be a feasible and viable market for those courageous enough to venture outside the vehicle and into the void, wearing nothing but a spacesuit, armed with nothing but preflight training. What that Extravehicular Activity (EVA) preflight training entails, however, is something that has yet to be defined. A number of significant factors will influence the composition of a commercial EVA training program, but a fundamental question remains: 'what minimum training guidelines must be met to ensure a safe and successful commercial spacewalk?' Utilizing the experience gained through the development of NASA's Skills program - designed to qualify NASA and International Partner astronauts for EVA aboard the International Space Station - this paper identifies the attributes and training objectives essential to the safe conduct of an EVA, and attempts to conceptually design a comprehensive training methodology meant to represent an acceptable qualification standard.

  19. Establishment of an unrelated umbilical cord blood bank qualification program: ensuring quality while meeting Food and Drug Administration vendor qualification requirements.

    Science.gov (United States)

    Rabe, Fran; Kadidlo, Diane; Van Orsow, Lisa; McKenna, David

    2013-10-01

    Qualification of a cord blood bank (CBB) is a complex process that includes evaluation of multiple aspects of donor screening and testing, processing, accreditation and approval by professional cell therapy groups, and results of received cord blood units. The University of Minnesota Medical Center Cell Therapy Laboratory has established a CBB vendor qualification process to ensure the CBB meets established regulatory and quality requirements. The deployed qualification of CBBs is based on retrospective and prospective review of the CBB. Forty-one CBBs were evaluated retrospectively: seven CBBs were disqualified based on failed quality control (QC) results. Eight CBBs did not meet the criteria for retrospective qualification because fewer than 3 cord blood units were received and the CBB was not accredited. As of March 2012, three US and one non-US CBBs have been qualified prospectively. One CBB withdrew from the qualification process after successful completion of the comprehensive survey and subsequent failure of the provided QC unit to pass the minimum criteria. One CBB failed the prospective qualification process based on processing methods that were revealed during the paper portion of the evaluation. A CBB qualification process is necessary for a transplant center to manage the qualification of the large number of CBBs needed to support a umbilical cord blood transplantation program. A transplant center that has utilized cord blood for a number of years before implementation of a qualification process should use a retrospective qualification process along with a prospective process. © 2013 American Association of Blood Banks.

  20. Economies of using seismic experience data qualification methods at Department of Energy facilities

    International Nuclear Information System (INIS)

    Loceff, F.; Antaki, G.; Goen, L.

    1995-01-01

    This paper summarizes the implementation of the seismic qualification of existing equipment using experience data techniques. The emphasis is on the economies of this approach compared with standard qualification methods of analysis and testing or replacement with qualified equipment. Seismic qualification of existing equipment using experience data is a technical necessity and is the most economically attractive of the options. Representative costs for seismic qualification at two facilities show costs are substantially lower than the costs for qualification using conventional methods. Because of the experience to date, the authors recommend that the Department of Energy continue to sponsor the Existing Facilities Program for applying qualification using experience data techniques at DOE facilities

  1. Hanford Tank Waste Treatment and Immobilization Plant (WTP) Waste Feed Qualification Program Development Approach - 13114

    Energy Technology Data Exchange (ETDEWEB)

    Markillie, Jeffrey R.; Arakali, Aruna V.; Benson, Peter A.; Halverson, Thomas G. [Hanford Tank Waste Treatment and Immobilization Plant Project, Richland, WA 99354 (United States); Adamson, Duane J.; Herman, Connie C.; Peeler, David K. [Savannah River National Laboratory, Aiken, SC 29808 (United States)

    2013-07-01

    The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is a nuclear waste treatment facility being designed and constructed for the U.S. Department of Energy by Bechtel National, Inc. and subcontractor URS Corporation (under contract DE-AC27-01RV14136 [1]) to process and vitrify radioactive waste that is currently stored in underground tanks at the Hanford Site. A wide range of planning is in progress to prepare for safe start-up, commissioning, and operation. The waste feed qualification program is being developed to protect the WTP design, safety basis, and technical basis by assuring acceptance requirements can be met before the transfer of waste. The WTP Project has partnered with Savannah River National Laboratory to develop the waste feed qualification program. The results of waste feed qualification activities will be implemented using a batch processing methodology, and will establish an acceptable range of operator controllable parameters needed to treat the staged waste. Waste feed qualification program development is being implemented in three separate phases. Phase 1 required identification of analytical methods and gaps. This activity has been completed, and provides the foundation for a technically defensible approach for waste feed qualification. Phase 2 of the program development is in progress. The activities in this phase include the closure of analytical methodology gaps identified during Phase 1, design and fabrication of laboratory-scale test apparatus, and determination of the waste feed qualification sample volume. Phase 3 will demonstrate waste feed qualification testing in support of Cold Commissioning. (authors)

  2. Sample results from the interim salt disposition program macrobatch 9 tank 21H qualification samples

    Energy Technology Data Exchange (ETDEWEB)

    Peters, T. B. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2015-11-01

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 9 for the Interim Salt Disposition Program (ISDP). This document reports characterization data on the samples of Tank 21H.

  3. IE Supplement No. 2 to Bulletin No. 79-01B: Environmental qualification of Class 1E equipment

    International Nuclear Information System (INIS)

    Anon.

    1993-01-01

    Enclosed are the generic questions and answers which resulted from NRC/Licensee meetings in NRC Regional Offices during the week of July 14, 1980 regarding environmental qualification of Class 1E equipment in use at power reactor facilities. These answers address specific questions asked during the meetings. Due to the generic nature of some of these questions, the staff is issuing them as a bulletin supplement. Some answers given in Supplement No. 1 to IEB-79-01B are superseded by these answers

  4. Nuclear energy electricity technical regulation on the qualification

    International Nuclear Information System (INIS)

    1995-01-01

    It tells the range of application purpose and of the qualification. It describes how to qualify of the class 1 E equipment, which are type test, operating experience, analysis and combined method. Next it deals with qualification procedure, which are specification requirement, requirement of qualification program, type testing, operating experience, analysis and combined qualification, acceptance criteria modification and extension with qualified life, simulated test profiles and document about type test data, operating experience data and extrapolation.

  5. Development of Simulator Maintenance Engineer Qualification Program Draft

    International Nuclear Information System (INIS)

    Chung, Kyung Hun

    2010-01-01

    As of 2009, KHNP has currently seven full scope simulators that are used for training of Nuclear Power Plant (NPP) Operators. Well-trained Simulator Maintenance Engineers (SME) are required to support these simulators. These SMEs will maintain and address any issues identified or any changes required for keep up the simulator with their respective plant sites. These issues will be identified as Simulator Discrepancy Reports (DR) or Work Order (WO) by the simulator operation personnel in KHNP. The simulator maintenance is a very complex. The simulator consists of many areas of process and requires experts in software modeling for different processes such as Neutronics, thermohydraulics, Logics, control, Electrical systems and computer systems as well as hardware subjects such as I and C, I/O, computers, etc. All these areas need experts the subject expertise need to be divided among SME's. In other word the SME's need to be trained for different expertise as well as having different level of SME's. KHNP has seen the need to outsource the maintenance work for these complex simulators. To have one company concentrating on this work will have many benefits such as: · Provides proper and well trained experts · Maintains consistent support personnel · Maintains the maintenance history for the simulator · Coordinates and Maintains the knowledge in house · The simulator maintenance will be consistent In order to accomplish the goals, KEPCO RI has recognized that there is a need for a program to adequately train and qualify the SME's. KEPCO RI and GSE, which has provided 6 simulators among 7 NPP simulators in Korea, have jointly developed this Simulator Maintenance Engineer Qualification Program (SMEQP). After issue of this plan, KEPCO RI will maintain and modify as needed periodically to meet the goals and purpose of the plan

  6. DATA QUALIFICATION REPORT: WATER-LEVEL DATA FROM THE NYE COUNTY EARLY WARNING DRILLING PROGRAM

    Energy Technology Data Exchange (ETDEWEB)

    F. H. Dove, P. Sanchez, and L. Saraka

    2000-04-21

    The objective of this work is to evaluate unqualified, water-level data gathered under the Nye County Early Warning Drilling Program (EWDP) and to determine whether the status of the data should be changed to ''qualified'' data in accordance with AP-SIII.2Q (Qualification of Unqualified Data and the Documentation of Rationale for Accepted Data). The corroboration method (as defined in Attachment 2 of AP-SIII.2Q) was implemented to qualify water-level data from Nye County measurements obtained directly from the Nye County Nuclear Waste Repository Program Office (NWRPO). Comparison of United States Geological Survey (USGS) measurements contained in DTN GS990608312312.003 with the Nye County water-level data has shown that the differences in water-level altitudes for the same wells are significantly less than 1 meter. This is an acceptable finding. Evaluation and recommendation criteria have been strictly applied to qualify Nye County measurements of water levels in selected wells measured by the USGS. However, the process of qualifying measured results by corroboration also builds confidence that the Nye County method for measurement of water levels is adequate for the intended use of the data (which is regional modeling). Therefore, it is reasonable to extend the term of ''qualified'' to water-level measurements in the remaining Nye County Phase I wells on the basis that the method has been shown to produce adequate results for the intended purpose of supporting large-scale modeling activities for the Yucca Mountain Project (YMP). The Data Qualification Team recommends the Nye County, water-level data contained in Appendix D of this report be designated as ''qualified''. These data document manual measurements of water-levels in eight (8) EWDP Phase I drillholes that were obtained prior to the field installation of continuous monitoring equipment.

  7. DATA QUALIFICATION REPORT: WATER-LEVEL DATA FROM THE NYE COUNTY EARLY WARNING DRILLING PROGRAM

    International Nuclear Information System (INIS)

    F. H. Dove, P. Sanchez, and L. Saraka

    2000-01-01

    The objective of this work is to evaluate unqualified, water-level data gathered under the Nye County Early Warning Drilling Program (EWDP) and to determine whether the status of the data should be changed to ''qualified'' data in accordance with AP-SIII.2Q (Qualification of Unqualified Data and the Documentation of Rationale for Accepted Data). The corroboration method (as defined in Attachment 2 of AP-SIII.2Q) was implemented to qualify water-level data from Nye County measurements obtained directly from the Nye County Nuclear Waste Repository Program Office (NWRPO). Comparison of United States Geological Survey (USGS) measurements contained in DTN GS990608312312.003 with the Nye County water-level data has shown that the differences in water-level altitudes for the same wells are significantly less than 1 meter. This is an acceptable finding. Evaluation and recommendation criteria have been strictly applied to qualify Nye County measurements of water levels in selected wells measured by the USGS. However, the process of qualifying measured results by corroboration also builds confidence that the Nye County method for measurement of water levels is adequate for the intended use of the data (which is regional modeling). Therefore, it is reasonable to extend the term of ''qualified'' to water-level measurements in the remaining Nye County Phase I wells on the basis that the method has been shown to produce adequate results for the intended purpose of supporting large-scale modeling activities for the Yucca Mountain Project (YMP). The Data Qualification Team recommends the Nye County, water-level data contained in Appendix D of this report be designated as ''qualified''. These data document manual measurements of water-levels in eight (8) EWDP Phase I drillholes that were obtained prior to the field installation of continuous monitoring equipment

  8. The design and qualification of radiation tolerant equipment for the nuclear power industry

    International Nuclear Information System (INIS)

    Sharp, R.; Pater, L.

    1995-01-01

    The nuclear power industry has many demands for equipment tolerant to the damaging effects of radiation. The wide variety of applications, including components handling, tooling, monitoring and communications, means that a systematic evaluation of the effects of radiation on materials and components used for equipment in radioactive facilities is often required. This paper describes the various effects of radiation on equipment, and discusses how to manage them when using and designing equipment. (Author)

  9. 24 CFR 200.935 - Administrator qualifications and procedures for HUD building products certification programs.

    Science.gov (United States)

    2010-04-01

    ... procedures for HUD building products certification programs. 200.935 Section 200.935 Housing and Urban... for HUD building products certification programs. (a) General. This section establishes administrator qualifications and procedures for the HUD Building Products Certification Programs under section 521 of the...

  10. Training and qualification program for nuclear criticality safety technical staff. Revision 1

    International Nuclear Information System (INIS)

    Taylor, R.G.; Worley, C.A.

    1997-01-01

    A training and qualification program for nuclear criticality safety technical staff personnel has been developed and implemented. All personnel who are to perform nuclear criticality safety technical work are required to participate in the program. The program includes both general nuclear criticality safety and plant specific knowledge components. Advantage can be taken of previous experience for that knowledge which is portable such as performance of computer calculations. Candidates step through a structured process which exposes them to basic background information, general plant information, and plant specific information which they need to safely and competently perform their jobs. Extensive documentation is generated to demonstrate that candidates have met the standards established for qualification

  11. Equipment line-up developed for structuring programmed digital systems important to safety

    International Nuclear Information System (INIS)

    Remus, L.; Colling, J.M.; Buisson, J.

    1986-01-01

    The use of the programmed digital techniques in systems important to safety led to developing equipment line-ups which allow to procedure, through using a restricted number of sub-assemblies, a variety of facilities capable of performing diversified functions. Upon remembering the requirements that such equipment are required to meet (quality assurance both at the design and production stages, qualification, testing opportunities, etc.) the equipments produced by MERLIN GERIN are described in this paper. Such equipments include a whole set of printed circuit boards, plug-in units with self-engaging connectors and the related cabinets to accomodate them. The following systems are made up of such equipments: Digital integrated protection system; Rod control and monitoring system; Reactor power distribution monitoring equipment. This equipment line-up has been gradually complemented and is still further expanding both as a result of the component further development or for the purpose of meeting new requirements or applications (new digital neutron instrumentation, local area networks). Experience gained thus far provides us with the capability of working out in a short time programmed systems for further applications in the nuclear power field

  12. Practical approaches to implementing facility wide equipment strengthening programs

    International Nuclear Information System (INIS)

    Kincaid, R.H.; Smietana, E.A.

    1989-01-01

    Equipment strengthening programs typically focus on components required to ensure operability of safety related equipment or to prevent the release of toxic substances. Survival of non-safety related equipment may also be crucial to ensure rapid recovery and minimize business interruption losses. Implementing a strengthening program for non-safety related equipment can be difficult due to the large amounts of equipment involved and limited budget availability. EQE has successfully implemented comprehensive equipment strengthening programs for a number of California corporations. Many of the lessons learned from these projects are applicable to DOE facilities. These include techniques for prioritizing equipment and three general methodologies for anchoring equipment. Pros and cons of each anchorage approach are presented along with typical equipment strengthening costs

  13. NRC sponsored rotating equipment vibration research: a program description and progress report

    International Nuclear Information System (INIS)

    Nitzel, M.E.

    1986-01-01

    The Idaho National Engineering Laboratory (INEL) is currently involved in a research project sponsored by the United States Nuclear Regulatory Commission (NRC) regarding operational vibration in rotating equipment. The object of this program is to assess the nature of vibrational failures and the effect that improved qualification standards may have in reducing the incidence of failure. In order to limit the scope of the initial effort, safety injection (SI) pumps were chosen as the component group for concentrated study. The task has been oriented to addressing the issues of whether certain SI pumps experience more failures than others, examining the dynamic environments in operation, examining the adequacy of current qualification standards, and examining what performance parameters could be used more efficiently to predict degradation or failure. Results of a literature search performed to survey SI pump failures indicate that failures are due to a diversity of causes, many of which may not be influenced by qualification criteria. Cooperative efforts have been undertaken with a limited number of nuclear utilities to describe the variety of possible operating environments and to analyze available data. The results of this analysis as they apply to the research issues are presented and possibilities for the future direction of the program are discussed

  14. Investgation concerning the structure, critical analysis and improvement of the organization of quality assurance in the qualification of electrical equipment for nuclear power plants with new parts and in-service inspections

    International Nuclear Information System (INIS)

    1985-01-01

    The study gives a survey of methods for the qualification of electrical equipment for nuclear power plants presently applied in the Federal Republic of Germany full consideration being given to the organization of quality assurance on the premises of the organizations involved (operators, plant suppliers, manufacturers). The organization of the qualification is to be kept distinct from the technical execution of the qualification. The qualification procedures are compared to those applied in France and in the USA. Aspects of future developments are shown with are promising with respect to: an increase in safety of electrical equipment for nuclear power plants, a simplification of the licencing procedure under Atomic Law. (orig./HP) [de

  15. Analysis of the extension and reduction method of qualified life used in equipment with ambiental qualification

    International Nuclear Information System (INIS)

    Serrano R, M.L. .e -mail: mlserrano@cnsns.gob.mx

    2005-01-01

    With the purpose of reducing costs of acquisition, maintenance, design, hour-man, dose, production, etc. or by changes in the temperature of service, diverse Nuclear Plants (NP) in the world have been carried out extensions and reductions of life of equipment and/or components related with the safety. The used methods are mainly tests type on equipment or component aged quickly, tests type on equipment or component aged naturally and use of the Arrhenius model with monitoring of temperatures in place. The present article carries out an analysis of the Arrhenius model with monitoring of temperatures in place, which is presented in two variants, equation (1) and (2), since it is the but used by the NP with extension purposes and reduction of qualified life. As back information, it was made one search of investigations, applied to diverse fields of the science that try about the reliability of the results provided by Arrhenius for the aging case. The results of the analysis indicate: I) that this method make uncertainties in some intervals of temperature and 2) which of the two variants it provides data more reliable. (Author)

  16. Preliminary Assessment of the Hanford Tank Waste Feed Acceptance and Product Qualification Programs

    Energy Technology Data Exchange (ETDEWEB)

    Herman, C. C.; Adamson, Duane J.; Herman, D. T.; Peeler, David K.; Poirier, Micheal R.; Reboul, S. H.; Stone, M. E.; Peterson, Reid A.; Chun, Jaehun; Fort, James A.; Vienna, John D.; Wells, Beric E.

    2013-04-01

    The U.S. Department of Energy Office of Environmental Management (EM) is engaging the national laboratories to provide the scientific and technological rigor to support EM program and project planning, technology development and deployment, project execution, and assessment of program outcomes. As an early demonstration of this new responsibility, Savannah River National Laboratory (SRNL) and Pacific Northwest National Laboratory (PNNL) have been chartered to implement a science and technology program addressing Hanford Tank waste feed acceptance and product qualification. As a first step, the laboratories examined the technical risks and uncertainties associated with the planned waste feed acceptance and qualification testing for Hanford tank wastes. Science and technology gaps were identified for work associated with 1) feed criteria development with emphasis on identifying the feed properties and the process requirements, 2) the Tank Waste Treatment and Immobilization Plant (WTP) process qualification program, and 3) the WTP HLW glass product qualification program. Opportunities for streamlining the accetpance and qualification programs were also considered in the gap assessment. Technical approaches to address the science and technology gaps and/or implement the opportunities were identified. These approaches will be further refined and developed as strong integrated teams of researchers from national laboratories, contractors, industry, and academia are brought together to provide the best science and technology solutions. Pursuing the identified approaches will have immediate and long-term benefits to DOE in reducing risks and uncertainties associated with tank waste removal and preparation, transfers from the tank farm to the WTP, processing within the WTP Pretreatment Facility, and in producing qualified HLW glass products. Additionally, implementation of the identified opportunities provides the potential for long-term cost savings given the anticipated

  17. The training program self-correcting and developing leadership qualities of sportsmen of high qualification.

    Directory of Open Access Journals (Sweden)

    Vysochina Nadezhda Leonidovna

    2011-09-01

    Full Text Available The influence of level of self-esteem on the effectiveness of game of skilled chess players. It is shown the program of correction of self-appraisal of sportsmen of high qualification. Introduced correction technology developed self-esteem in the process of training of sportsmen chess players of high qualification as a set of training exercises aimed at improving the efficiency of sports activity. It is shown that high self-esteem has a positive effect on sports results chess players.

  18. Significance of non-classical damping in seismic qualification of equipment and piping

    Energy Technology Data Exchange (ETDEWEB)

    Gupta, Abhinav, E-mail: agupta1@ncsu.edu; Bose, Mrinal K.

    2017-06-15

    Highlights: • Damping in coupled building-piping or building-equipment systems is nonlclassical. • Significance of nonclassical damping is illustrated. • Classical damping assumption can over predict or under predict response. • Significance of nonclassical damping increases for very light secondary systems. • Composite modal damping is another form of classical damping. - Abstract: This paper presents a discussion on the significance of non-classical damping in coupled primary-secondary systems such as building-equipment or building-piping. Closed-form expressions are used to illustrate that the effect of non-classical damping is significant in systems with tuned or nearly tuned uncoupled modes when the mass-interaction is sufficiently small. Further, simple primary-secondary systems are used to illustrate that composite modal damping is another form of classical damping for which the transformed damping matrix, obtained after pre- and post-multiplication of the damping matrix with the modal matrix, contains only diagonal terms. Both the composite and the classical damping give almost identical results that can be much different from the corresponding results for non-classical damping. Finally, it is shown that consideration of classical damping (ignoring the off-diagonal terms) can give excessively conservative results in nearly tuned primary-secondary systems. For perfectly tuned primary-secondary systems, however, classical damping can give responses that are much lower than what they should be.

  19. Qualification program of the ASTRID SFR project: definition, methodology and associated risk evaluation and management - 15093

    International Nuclear Information System (INIS)

    Rodriguez, G.; Dirat, J.F.; Traina, A.; Christofari, M.

    2015-01-01

    The Preconceptual Design phase of the ASTRID French Sodium Fast Reactor project had the objective to integrate innovative options to meet the requirements of the 4. generation reactors and to comply with the related specifications. It was followed by the conceptual phase studies (AVP2 phase 2013-2015) where some technical options are left opened with an advanced option and a backup alternative. In the same time of the AVP2 phase studies, the qualification program related to ASTRID project was initiated. It consists in collecting the exhaustive list of research/development (R/D) needs and technological demonstration tests to be fulfilled on representative mockup prior to component implementation in the prototype. The ASTRID Qualification Program (AQP) objectives are to collect needs expressed by all engineering companies involved in ASTRID, and then to organize the answer to this expression of needs. This significant work of needs compilation has been divided in several tasks, according to the ASTRID project decomposition in the Product Breakdown Structure (PBS). Compilation of needs was jointly performed by engineering company, R/D responsible and coordinated by the ASTRID Qualification project responsible. It was associated with an evaluation of the maturity level of the technical options thanks to a Technological Readiness Level grid (TRL ranking table), an identification of major risks, and an evaluation of the R/D potentiality and associated facility platform. The methodology applied for the ASTRID Qualification Program (AQP) is presented. It is explained what methodology was used associated to the TRL process, and how is managed the associated risk analysis evaluation: evaluation of major risks, definition of a risk portfolio and a corresponding Action Plan for risk reduction (synthesized under the REM acronym: Risk Evaluation and Management). This methodology is a mean used to facilitate ASTRID risk-informed decision making, technology qualification and

  20. Seismic test qualification of electrical equipment - testing methods in use to EDF

    International Nuclear Information System (INIS)

    Fabries, R.

    1981-01-01

    At the beginning, for the 900 MW Power Plant level, the testing method in application used the single axis test by sine beat of 10 cycles according to the specifications of the guide IEEE 344-71. When the french guide UTEC 20-420 came into force we have had to define another testing method (EDF standard: HN20 E52) which utilize the single-axis test either by a sine beat of 5-cycles or by a synthetized time history. We present here the mains criterions allowing to justify: -The single-axis test. The single frequency wave (when the Initial Response Spectrum (IRS) present a narrow band). The use of one sine beat of 5-cycles or one synthetized time history. The need of taking into account the high stress level. This oligocyclic stress fatigue explains why one beat of 5-cycles may be as severe as one time history of 20 seconds (with the same level of strong response spectrum). Then, we conclude that the durating of the testing wave applied to the equipment shall be considered as a relative parameter only. The weight of the SSE tests by respect to the OBE tests. The precautions to take in order to: generate and check accurately the synthetized time history, choice the test frequencies when the sine beat is used. (orig./HP)

  1. A compliance testing program for diagnostic X-ray equipment

    International Nuclear Information System (INIS)

    Hutchinson, D.E.; Cobb, B.J.; Jacob, C.S.

    1999-01-01

    Compliance testing is nominally that part of a quality assurance program dealing with those aspects of X-ray equipment performance that are subject to radiation control legislation. Quality assurance programs for medical X-ray equipment should be an integral part of the quality culture in health care. However while major hospitals and individual medical centers may implement such programs with some diligence, much X-ray equipment can remain unappraised unless there is a comprehensive regulatory inspection program or some form of compulsion on the equipment owner to implement a testing program. Since the late 1950s all X-ray equipment in the State of Western Australia has been inspected by authorized officers acting on behalf of the Radiological Council, the regulatory authority responsible for administration of the State's Radiation Safety Act. However, economic constraints, coupled with increasing X-ray equipment numbers and a geographically large State have significantly affected the inspection rate. Data available from inspections demonstrate that regular compliance and performance checks are essential in order to ensure proper performance and to minimize unnecessary patient and operator dose. To ensure that diagnostic X-ray equipment complies with accepted standards and performance criteria, the regulatory authority introduced a compulsory compliance testing program for all medical, dental and chiropractic diagnostic X-ray equipment effective from 1 January 1997

  2. An evaluation of methodology for seismic qualification of equipment, cable trays, and ducts in ALWR plants by use of experience data

    International Nuclear Information System (INIS)

    Bandyopadhyay, K.K.; Kana, D.D.; Kennedy, R.P.; Schiff, A.J.

    1997-07-01

    Advanced Reactor Corporation (ARC) has developed a methodology for seismic qualification of equipment, cable trays and ducts in Advanced Light Water Reactor plants. A Panel (members of which acted as individuals) supported by the Office of Nuclear Regulatory Research of the Nuclear Regulatory Commission has evaluated this methodology. The review approach and observations are included in this report. In general, the Panel supports the ARC methodology with some exceptions and provides recommendations for further improvements. 26 refs., 10 figs., 1 tab

  3. An evaluation of methodology for seismic qualification of equipment, cable trays, and ducts in ALWR plants by use of experience data

    Energy Technology Data Exchange (ETDEWEB)

    Bandyopadhyay, K.K.; Kana, D.D.; Kennedy, R.P.; Schiff, A.J.

    1997-07-01

    Advanced Reactor Corporation (ARC) has developed a methodology for seismic qualification of equipment, cable trays and ducts in Advanced Light Water Reactor plants. A Panel (members of which acted as individuals) supported by the Office of Nuclear Regulatory Research of the Nuclear Regulatory Commission has evaluated this methodology. The review approach and observations are included in this report. In general, the Panel supports the ARC methodology with some exceptions and provides recommendations for further improvements. 26 refs., 10 figs., 1 tab.

  4. IEEE Std 323-1983: IEEE standard for qualifying Class 1E equipment for nuclear power generating stations

    International Nuclear Information System (INIS)

    Anon.

    1992-01-01

    This standard describes the basic requirements for qualifying Class 1E equipment with interfaces that are to be used in nuclear power generating stations. The requirements presented include the principles, procedures, and methods of qualification. These qualification requirements, when met, will confirm the adequacy of the equipment design under normal, abnormal, design basis event, post design basis event, and in-service test conditions for the performance of safety function(s). The purpose of this standard is to identify requirements for the qualification of Class 1E equipment, including those interfaces whose failure could adversely affect the performance of Class 1E equipment and systems. The methods described shall be used for qualifying equipment, extending qualification, and updating qualification if the equipment is modified. Other issued IEEE standards which present qualification methods for specific equipment or components, or both, and those that deal with parts of the qualification program, may be used to supplement this standard, as applicable

  5. Tilt stability in nonlinear programming under Mangasarian-Fromovitz constraint qualification

    Czech Academy of Sciences Publication Activity Database

    Mordukhovich, B. S.; Outrata, Jiří

    2013-01-01

    Roč. 49, č. 3 (2013), s. 446-464 ISSN 0023-5954 R&D Projects: GA ČR(CZ) GAP201/12/0671 Institutional support: RVO:67985556 Keywords : variational analysis * second-order theory * generalized differentiation * tilt stability Subject RIV: BA - General Mathematics Impact factor: 0.563, year: 2013 http://library.utia.cas.cz/separaty/2013/MTR/outrata-tilt stability in nonlinear programming under mangasarian-fromovitz constraint qualification.pdf

  6. Nuclear security personnel for power plants. Content and review procedures for a security training and qualification program

    International Nuclear Information System (INIS)

    1978-06-01

    The applicant and licensee training and qualification plans will outline the process by which guard, watchman, armed response persons and other members of the security organization will be selected, trained, equipped and qualified. This plan should contain: (1) job descriptions for all security positions; (2) duties defined for all positions; (3) critical tasks defined for all duties; (4) skills, knowledge and abilities defined for all critical tasks; (5) performance objectives stated for all critical tasks; and (6) training and qualification plans to train and test to appropriate performance objectives. The document gives guidance on the preparation of this training and qualification plan and contains three parts: (1) an introduction to and brief explanation of job analysis and performance objectives; (2) a statement of the information that should be submitted in response to the requirements and the NRR review procedures; and (3) a sample qualification submittal

  7. Qualification plan for the Genmod-PC computer program

    International Nuclear Information System (INIS)

    Richardson, R.B.; Wright, G.M.; Dunford, D.W.; Linauskas, S.H.

    2002-07-01

    Genmod-PC is an internal dosimetry code that uses Microsoft Windows operating system, and that currently calculates radionuclide doses and intakes for an adult male. This report provides a plan for specifying the quality assurance measures that conform to the recommendations of the Canadian Standards Association, as well as AECL procedural requirements for a legacy computer program developed at AECL. (author)

  8. Perry Nuclear Power Plant Area/Equipment Temperature Monitoring Program

    International Nuclear Information System (INIS)

    McGuire, L.L.

    1991-01-01

    The Perry Nuclear Power Plant Area/Equipment Temperature Monitoring Program serves two purposes. The first is to track temperature trends during normal plant operation in areas where suspected deviations from established environmental profiles exist. This includes the use of Resistance Temperature Detectors, Recorders, and Temperature Dots for evaluation of equipment qualified life for comparison with tested parameters and the established Environmental Design Profile. It also may be used to determine the location and duration of steam leaks for effect on equipment qualified life. The second purpose of this program is to aid HVAC design engineers in determining the source of heat outside anticipated design parameters. Resistance Temperature Detectors, Recorders, and Temperature Dots are also used for this application but the results may include design changes to eliminate the excess heat or provide qualified equipment (cable) to withstand the elevated temperature, splitting of environmental zones to capture accurate temperature parameters, or continued environmental monitoring for evaluation of equipment located in hot spots

  9. Quality Assurance Program Plan for SFR Metallic Fuel Data Qualification

    Energy Technology Data Exchange (ETDEWEB)

    Benoit, Timothy [Argonne National Lab. (ANL), Argonne, IL (United States). Nuclear Engineering Division; Hlotke, John Daniel [Argonne National Lab. (ANL), Argonne, IL (United States). Nuclear Engineering Division; Yacout, Abdellatif [Argonne National Lab. (ANL), Argonne, IL (United States). Nuclear Engineering Division

    2017-07-05

    This document contains an evaluation of the applicability of the current Quality Assurance Standards from the American Society of Mechanical Engineers Standard NQA-1 (NQA-1) criteria and identifies and describes the quality assurance process(es) by which attributes of historical, analytical, and other data associated with sodium-cooled fast reactor [SFR] metallic fuel and/or related reactor fuel designs and constituency will be evaluated. This process is being instituted to facilitate validation of data to the extent that such data may be used to support future licensing efforts associated with advanced reactor designs. The initial data to be evaluated under this program were generated during the US Integral Fast Reactor program between 1984-1994, where the data includes, but is not limited to, research and development data and associated documents, test plans and associated protocols, operations and test data, technical reports, and information associated with past United States Nuclear Regulatory Commission reviews of SFR designs.

  10. Safety design guides for environmental qualification for CANDU 9

    International Nuclear Information System (INIS)

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

    1996-03-01

    This safety design guide describes the safety philosophy and requirements for the environmental qualification of safety related systems and components for CANDU 9. The environmental qualification program identifies the equipments to be qualified and conditions to be used for qualification and provides comprehensive set of documentation to ensure that the qualification is complete and can be maintained for the life of the plant. A summary of the system, components and structures requiring environmental qualification is provided in the table for the guidance of the system design, and this table will be subject to change or confirmation by the environmental qualification program. Also, plant ares subject to harsh environment is provided in the figure. The change status of the regulatory requirements, code and standards should be traced and this safety design guide shall be updated accordingly. 1 tab., 5 figs. (Author) .new

  11. Qualification of quality assurance program audit personnel for nuclear power plants - August 1980

    International Nuclear Information System (INIS)

    Anon.

    1981-01-01

    Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants, to 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities, establishes overall quality assurance requirements for the design, construction, and operation of safety-related structures, and components of nuclear power plants. Criterion XVIII, Audits, of Appendix B establishes requirements for conducting audits of the quality assurance program. This guide describes a method acceptable to the NRC staff for complying with the Commission's regulations with regard to qualification of quality assurance program audit personnel for nuclear power plants

  12. Seismic qualification program plan for continued operation at DOE-SRS nuclear material processing facilities

    International Nuclear Information System (INIS)

    Talukdar, B.K.; Kennedy, W.N.

    1991-01-01

    The Savannah River Facilities for the most part were constructed and maintained to standards that were developed by Du Pont and are not rigorously in compliance with the current General Design Criteria (GDC); DOE Order 6430.IA requirements. In addition, many of the facilities were built more than 30 years ago, well before DOE standards for design were issued. The Westinghouse Savannah River Company (WSRC) his developed a program to address the evaluation of the Nuclear Material Processing (NMP) facilities to GDC requirements. The program includes a facility base-line review, assessment of areas that are not in compliance with the GDC requirements, planned corrective actions or exemptions to address the requirements, and a safety assessment. The authors from their direct involvement with the Program, describe the program plan for seismic qualification including other natural phenomena hazards,for existing NMP facility structures to continue operation Professionals involved in similar effort at other DOE facilities may find the program useful

  13. Human performance for the success of equipment reliability programs

    International Nuclear Information System (INIS)

    Woodcock, J.

    2007-01-01

    Human performance is a critical element of programs directed at equipment reliability. Reliable equipment performance requires broad support from all levels of plant management and throughout all plant departments. Experience at both nuclear power plants and fuel manufacturing plants shows that human performance must be addressed during all phases of program implementation from the beginning through the establishment of a living, on-going process. At the beginning, certain organizational and management actions during the initiation of the program set the stage for successful adoption by station personnel, leading to more rapid benefits. For the long term, equipment reliability is a living process needed throughout the lifetime of a station, a program which must be motivated and measured. Sustained acceptance and participation by the plant personnel is a requirement, and culture is a key ingredient. This paper will provide an overview of key human performance issues to be considered, using the application of the INPO AP-913 Equipment Reliability Guideline as a basis and gives some best practices for training, communicating and implementing programs. The very last part includes ways to tell if the program is effective

  14. An overview of fiber-to-the-premises (FTTP) product requirements and qualification programs

    Science.gov (United States)

    Gebizlioglu, Osman S.; Gallo, Ernest J.

    2006-04-01

    North American deployments of FTTP architectures have been rapidly increasing. While the FTTP market is being driven by major telecommunications service providers, equipment suppliers have been scrambling to bring products to market that will ensure them a piece of this high-stakes market. In this invited presentation/paper, we propose to examine the technical requirements that are needed to support the new FTTP network with a host of new products that have been in development. To enable service providers select the best new products for FTTP deployment, product selection needs to be based on the analysis and testing of new products for performance and reliability, Telcordia, in its traditional role of telecommunications standards development, has been publishing generic requirements (GR) documents that have been used by suppliers, service providers and the industry at large. Product qualification programs based on the established performance and reliability requirements/standards have been designed to evaluate products to determine if they can 1) withstand the rigors of the outside plant deployment environment and perform for extended periods of time, 2) be upgradeable, and 3) craft friendly. The outside plant is a tough environment to live in. A product must perform under the extreme conditions of cold down -40°C (-40°F) and hot up to 46°C (115°F) with high humidity of 95%, rain, snow, sleet, vibration due to traffic, lightning, heating due to solar loads, high winds, ice, sand storms, and products are even tested to demonstrate if they can continue to operate in an earthquake, a wild fire and a shotgun blast. All FTTP products are not only expected to perform, but they must meet stringent optical performance criteria of low insertion loss and reflectance / return loss at a broad range of wavelengths from 1310, 1490, 1550 and 1625 nm. While the upstream (from the customer to the CO) voice and data transmission is currently planned over 1310-nm wavelength, the

  15. From Harassment to Helping with Antisocial Youth: The EQUIP Program.

    Science.gov (United States)

    Gibbs, John C.; Potter, Granville Bud; Goldstein, Arnold P.; Brendtro, Larry K.

    1996-01-01

    Describes a new psychoeducational treatment model for antisocial youth. Discusses the principles and methods for cultivating a positive caring culture in the schools and how the program equips youth for effective peer helping by integrating positive peer culture with training in moral development, anger management, social skills, and correcting…

  16. Seismic and dynamic qualification of safety-related electrical and mechanical equipment in operating nuclear power plants: development of a method to generate generic floor-response spectra

    International Nuclear Information System (INIS)

    Curreri, J.; Costantino, C.; Subudhi, M.; Reich, M.

    1983-09-01

    Generic floor response spectra were developed for use in the qualification of electrical and mechanical equipment in operating nuclear power plants. The characteristics of 1000 floor response spectra were studied to determine the generic spectra. The procedure developed uses as much or as little information that currently exists at the plant relating to the question of equipment qualification. The general approach was to study the effects on the dynamic characteristics of each of the elements in the chain of events that goes between the loads and the responses. This includes the loads, the soils and the structures. A free-field earthquake response spectra was used to generate horizontal earthquake time histories. The excitation was applied through the soil and into the various structures to produce responses in equipment. An entire range of soil conditions was used with each structure. Actual PWR and BWR - Mark I structural models were used. For each model, the stiffness properties were varied, with the same mass, so as to extend the fundamental base structure natural frequency from 2 cps to 36 cps. The natural frequencies of the structures were varied to obtain maximum response conditions. The actual properties were first used to locate the natural frequencies. The stiffness properties were than varied, with the same mass, to extend the range of the fundamental base structure natural frequency. The intention was to have the coupled structural material frequencies in the vicinity of the peak amplitude frequency content of the excitation spectrum. Particular attention was therefore given to the frequency band between 2 Hz and 4 Hz. A horizontal generic floor response spectra is proposed for the top level of a generic structure. Reduction factors are applied to the peak acceleration for equipment at lower levels

  17. Expansion of the acceptance program: nitrous oxide scavenging equipment and nitrous oxide trace gas monitoring equipment

    Energy Technology Data Exchange (ETDEWEB)

    1977-10-01

    The Acceptance Program for dental materials and devices and the general guidelines for submission of products have been reported in the Journal (88:615 March 1974). At its April 1977 meeting, the Council included equipment for scavenging and monitoring trace nitrous oxide gas in its Acceptance Program. The Council has established the effective date for classification of products under these two sets of guidelines as one year from the date of publication of this announcement. After that date, classification of a product will be required before promotion or exhibition in Association media.

  18. Advances and highlights of the CNEA qualification program as high density fuel manufacturer for research reactors

    Energy Technology Data Exchange (ETDEWEB)

    Adelfang, P.; Alvarez, L.; Boero, N.; Calabrese, R.; Echenique, P.; Markiewicz, M.; Pasqualini, E.; Ruggirello, G.; Taboada, H. [Unidad de Actividad Combustibles Nucleares Comision Nacional de Energia Atomica (CNE4), Avda. del Libertador, 8250 C1429BNO Buenos Aires (Argentina)

    2002-07-01

    One of the main objectives of CNEA regarding the fuel for research reactors is the development and qualification of the manufacturing of LEU high-density fuels. The qualification programs for both types of fuels, Silicide fuel and U- x Mo fuel, are similar. They include the following activities: development and set up of the fissile compound manufacturing technology, set up of fuel plate manufacturing, fabrication and irradiation of mini plates and plates, design and fabrication of fuel assembly prototypes for irradiation, post-irradiation examination and feedback for manufacturing improvements. This paper describes the different activities performed within each program during the last year and the main advances and achievements of the programs within this period. The main achievements may be summarized in the following activities: Continuation of the irradiation of the first silicide fuel element in the R A3. Completion of the manufacturing of the second silicide fuel element, licensing and beginning of its irradiation in the R A3. Development of the HMD Process to manufacture U-Mo powder (pUMA project). Set up of fuel plates manufacturing at industrial level using U-Mo powder. Preliminary studies and the design for the irradiation of mini plates, plates and full scale fuel elements with U-Mo and 7 g U/cm{sup 3}. PIE destructive studies for the P-04 silicide fuel prototype (accurate burnup determination through chemical analysis, metallography and SEM of samples from the irradiated fuel plates). Improvement and development of new characterization techniques for high density fuel plates quality control including US testing and densitometric analysis of X-ray examinations. The results obtained in this period are encouraging and also allow to foresee a wider participation of CNEA in the international effort to qualify U-Mo as a new material for the manufacturing of research reactor fuels. (author)

  19. Advances and highlights of the CNEA qualification program as high density fuel manufacturer for research reactors

    International Nuclear Information System (INIS)

    Adelfang, P.; Alvarez, L.; Boero, N.; Calabrese, R.; Echenique, P.; Markiewicz, M.; Pasqualini, E.; Ruggirello, G.; Taboada, H.

    2002-01-01

    One of the main objectives of CNEA regarding the fuel for research reactors is the development and qualification of the manufacturing of LEU high-density fuels. The qualification programs for both types of fuels, Silicide fuel and U- x Mo fuel, are similar. They include the following activities: development and set up of the fissile compound manufacturing technology, set up of fuel plate manufacturing, fabrication and irradiation of mini plates and plates, design and fabrication of fuel assembly prototypes for irradiation, post-irradiation examination and feedback for manufacturing improvements. This paper describes the different activities performed within each program during the last year and the main advances and achievements of the programs within this period. The main achievements may be summarized in the following activities: Continuation of the irradiation of the first silicide fuel element in the R A3. Completion of the manufacturing of the second silicide fuel element, licensing and beginning of its irradiation in the R A3. Development of the HMD Process to manufacture U-Mo powder (pUMA project). Set up of fuel plates manufacturing at industrial level using U-Mo powder. Preliminary studies and the design for the irradiation of mini plates, plates and full scale fuel elements with U-Mo and 7 g U/cm 3 . PIE destructive studies for the P-04 silicide fuel prototype (accurate burnup determination through chemical analysis, metallography and SEM of samples from the irradiated fuel plates). Improvement and development of new characterization techniques for high density fuel plates quality control including US testing and densitometric analysis of X-ray examinations. The results obtained in this period are encouraging and also allow to foresee a wider participation of CNEA in the international effort to qualify U-Mo as a new material for the manufacturing of research reactor fuels. (author)

  20. Program description for the qualification of CNEA - Argentina as a supplier of LEU silicide fuel and post-irradiation examinations plan for the first prototype irradiated in Argentina

    International Nuclear Information System (INIS)

    Rugirello, Gabriel; Adelfang, Pablo; Denis, Alicia; Zawerucha, Andres; Marco, Agustin di; Guillaume, Eduardo; Sbaffoni, Monica; Lacoste, Pablo

    1998-01-01

    In this report we present a description of the ongoing and future stages of the program for the qualification of CNEA, Argentina, as a supplier of low enriched uranium silicide fuel elements for research reactor. Particularly we will focus on the characteristics of the future irradiation experiment on a new detachable prototype, the post-irradiation examinations (PIE) plan for the already irradiated prototype PO4 and an overview of the recently implemented PIE facilities and equipment. The program is divided in several steps, some of which have been already completed. It concludes: development of the uranium silicide fissile material, irradiation and PIE of several full-scale prototypes. Important investments have been already carried out in the facilities for the FE production and PIE. (author)

  1. 15 CFR 9.3 - Appliances and equipment included in program.

    Science.gov (United States)

    2010-01-01

    ... 15 Commerce and Foreign Trade 1 2010-01-01 2010-01-01 false Appliances and equipment included in... VOLUNTARY LABELING PROGRAM FOR HOUSEHOLD APPLIANCES AND EQUIPMENT TO EFFECT ENERGY CONSERVATION § 9.3 Appliances and equipment included in program. The appliances and equipment included in this program are room...

  2. Modified enforcement policy relating to 10 CFR 50.49, ''Environmental qualification of electrical equipment important to safety for nuclear power plants'' (Generic Letter 88-07)

    International Nuclear Information System (INIS)

    Miraglia, F.J.

    1992-01-01

    Generic Letters, Bulletins, and Information Notices have been issued to provide guidance regarding the application and enforcement of 10 CFR 50.49, ''Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants.'' Generic Letter 85-15, issued August 6, 1985, and Generic Letter 86-15, issued September 22, 1986, provided information related to the deadlines for compliance with 10 CFR 50.49 and possible civil penalties applicable to licensees who were not in compliance with the rule as of the November 30, 1985 deadline. Upon review, the Commission found that the EQ Enforcement Policy promulgated in Generic Letter 86-15, could result in imposition of civil penalties that did not properly reflect the safety significance of EQ violations with respect to civil penalties imposed in the past. In the interest of continuing a tough but fair enforcement policy, the Commission determined that the EQ Enforcement Policy should be revised. The purpose of this letter is to provide a modification to the NRC's enforcement policy, as approved by the Commission, for environmental qualification (EQ) violations. This letter replaces the guidance provided in Generic Letters 85-15 and 86-15

  3. Hanford Waste Vitrification Plant Quality Assurance Program description for defense high-level waste form development and qualification

    International Nuclear Information System (INIS)

    Hand, R.L.

    1992-01-01

    This document describes the quality assurance (QA) program of the Hanford Waste Vitrification Plant (HWVP) Project. The purpose of the QA program is to control project activities in such a manner as to achieve the mission of the HWVP Project in a safe and reliable manner. A major aspect of the HWVP Project QA program is the control of activities that relate to high-level waste (HLW) form development and qualification. This document describes the program and planned actions the Westinghouse Hanford Company (Westinghouse Hanford) will implement to demonstrate and ensure that the HWVP Project meets the US Department of Energy (DOE) and ASME regulations. The actions for meeting the requirements of the Waste Acceptance Preliminary Specifications (WAPS) will be implemented under the HWVP product qualification program with the objective of ensuring that the HWVP and its processes comply with the WAPS established by the federal repository

  4. Opportunities for the LWR ATF materials development program to contribute to the LBE-cooled ADS materials qualification program

    Energy Technology Data Exchange (ETDEWEB)

    Gong, Xing, E-mail: gongxingzfl@hotmail.com [Department of ATF R& D, Nuclear Fuel Research and Development Center, China Nuclear Power Technology Research Institute Co., Ltd., China General Nuclear Power Corporation (CGN), Shenzhen, 518026 (China); Li, Rui, E-mail: li-rui@cgnpc.com.cn [Department of ATF R& D, Nuclear Fuel Research and Development Center, China Nuclear Power Technology Research Institute Co., Ltd., China General Nuclear Power Corporation (CGN), Shenzhen, 518026 (China); Sun, Maozhou; Ren, Qisen [Department of ATF R& D, Nuclear Fuel Research and Development Center, China Nuclear Power Technology Research Institute Co., Ltd., China General Nuclear Power Corporation (CGN), Shenzhen, 518026 (China); Liu, Tong, E-mail: liutong@cgnpc.com.cn [Department of ATF R& D, Nuclear Fuel Research and Development Center, China Nuclear Power Technology Research Institute Co., Ltd., China General Nuclear Power Corporation (CGN), Shenzhen, 518026 (China); Short, Michael P., E-mail: hereiam@mit.edu [Department of Nuclear Science and Engineering, Massachusetts Institute of Technology (MIT), Cambridge, MA, 02139 (United States)

    2016-12-15

    Accelerator-driven systems (ADS) are a promising approach for nuclear waste disposal. Nevertheless, the principal candidate materials proposed for ADS construction, such as the ferritic/martensitic steel, T91, and austenitic stainless steels, 316L and 15-15Ti, are not fully compatible with the liquid lead-bismuth eutectic (LBE) coolant. Under some operating conditions, liquid metal embrittlement (LME) or liquid metal corrosion (LMC) may occur in these steels when exposed to LBE. These environmentally-induced material degradation effects pose a threat to ADS reactor safety, as failure of the materials could initiate a severe accident, in which fission products are released into the coolant. Meanwhile, parallel efforts to develop accident-tolerant fuels (ATF) in light water reactors (LWRs) could provide both general materials design philosophies and specific material solutions to the ADS program. In this paper, the potential contributions of the ATF materials development program to the ADS materials qualification program are evaluated and discussed in terms of service conditions and materials performance requirements. Several specific areas where coordinated development may benefit both programs, including composite materials and selected coatings, are discussed. - Highlights: • ATF materials developed for LWRs could be candidate materials for the LBE-cooled ADS program. • Similar material design and protection philosophies are utilized in both programs. • Unique challenges of LBE-cooled ADS systems could possibly be addressed by LWR ATF materials. • More coordinated testing should be performed between the ATF and ADS programs.

  5. Sensor equipment of the German earth scientific airplane program

    Science.gov (United States)

    Seige, P.

    1975-01-01

    The German airplane program for earth scientific research supports the work of a vast staff of earth scientists from universities and federal agencies. Due to their fields of interest, which are in oceanography, hydrology, geology, ecology, and forestry, five test areas were selected which are spread all over Germany. The sensor package, which was designed in accordance with the requirements of this group of scientists, will be installed in a DO 28 D2 type airplane. The sensor equipment consists of a series of 70-mm cameras having different film/filter combinations, a photogrammetric camera, an infrared radiometer, an 11-channel multispectral line scanner, a LANDSAT-compatible radiometer, and a complex avionic system. Along with the airplane, a truck will be equipped with a set of radiometers and other sensor devices for extensive ground-truth measurement; this also includes a cherry picker.

  6. Recovery Act: Training Program Development for Commercial Building Equipment Technicians

    Energy Technology Data Exchange (ETDEWEB)

    Leah Glameyer

    2012-07-12

    The overall goal of this project has been to develop curricula, certification requirements, and accreditation standards for training on energy efficient practices and technologies for commercial building technicians. These training products will advance industry expertise towards net-zero energy commercial building goals and will result in a substantial reduction in energy use. The ultimate objective is to develop a workforce that can bring existing commercial buildings up to their energy performance potential and ensure that new commercial buildings do not fall below their expected optimal level of performance. Commercial building equipment technicians participating in this training program will learn how to best operate commercial buildings to ensure they reach their expected energy performance level. The training is a combination of classroom, online and on-site lessons. The Texas Engineering Extension Service (TEEX) developed curricula using subject matter and adult learning experts to ensure the training meets certification requirements and accreditation standards for training these technicians. The training targets a specific climate zone to meets the needs, specialized expertise, and perspectives of the commercial building equipment technicians in that zone. The combination of efficient operations and advanced design will improve the internal built environment of a commercial building by increasing comfort and safety, while reducing energy use and environmental impact. Properly trained technicians will ensure equipment operates at design specifications. A second impact is a more highly trained workforce that is better equipped to obtain employment. Organizations that contributed to the development of the training program include TEEX and the Texas Engineering Experiment Station (TEES) (both members of The Texas A&M University System). TEES is also a member of the Building Commissioning Association. This report includes a description of the project

  7. The IHS diagnostic X-ray equipment radiation protection program

    International Nuclear Information System (INIS)

    Knapp, A.; Byrns, G.; Suleiman, O.

    1994-01-01

    The Indian Health Service (IHS) operates or contracts with Tribal groups to operate 50 hospitals and approximately 165 primary ambulatory care centers. These facilities contain approximately 275 medical and 800 dental diagnostic x-ray machines. IHS environmental health personnel in collaboration with the Food and Drug Administration's (FDA) Center for Devices and Radiological Health (CDRH) developed a diagnostic x-ray protection program including standard survey procedures and menu-driven calculations software. Important features of the program include the evaluation of equipment performance collection of average patient entrance skin exposure (ESE) measurements for selected procedures, and quality assurance. The ESE data, collected using the National Evaluation of X-ray Trends (NEXT) protocol, will be presented. The IHS Diagnostic X-ray Radiation Protection Program is dynamic and is adapting to changes in technology and workload

  8. Qualification issues: the rest of the iceberg

    International Nuclear Information System (INIS)

    Bonzon, L.L.; Luna, R.E.

    1978-01-01

    Reactor safety has been a primary concern since the beginning of commercial power reactor development. But only since the IEEE became actively involved (circa-1970), through IEEE-323-1971 and its predecessor drafts, has the qualification of selected Class 1 equipment been formalized and intensified. Currently EPRI and the USNRC are funding significant qualification research programs. However, these current research topics address only a few of the issues and there are more to come. A review of recent achievements and a discussion of some issues still to be encountered are presented

  9. US DOE Radiological Assistance Program: personnel, equipment and resources

    International Nuclear Information System (INIS)

    Hull, A.P.; Kuehner, A.V.; Phillips, L.F.

    1982-01-01

    The Radiological Assistance Program (RAP) of the US Department of Energy (DOE) is intended to provide emergency advice and assistance in the event of radiological incidents. Each of DOE's eight Regional Coordinating Offices in the US provide a 24-hour reporting and response capability. Specifically, the Brookhaven Area Office (BHO) is responsible for DOE's Region I, which includes the 11 northeastern states of the US. Although an inventory of dedicated equipment is assigned to BHO-RAP, it draws upon the resources of Brookhaven National Laboratory (BNL) for trained personnel in health physics and for other specialized personnel in both the day to day operation of the program and in the on-the-scene response to an incident. The organization of the BHO-RAP program and its response procedures are described in detail. An inventory and brief description of the contents of a variety of emergency equipment kits and of additional state-of-the-art instruments is included. The BHO-RAP guidelines and requirements for field operations are also indicated, as are other DOE resources upon which it can draw

  10. Experience on environmental qualification of safety-related components for Darlington Nuclear Generating Station

    International Nuclear Information System (INIS)

    Yu, A.S.; Kukreti, B.M.

    1987-01-01

    The proliferation of Nuclear Power Plant safety concerns has lead to increasing attention over the Environmental Qualification (EQ) of Nuclear Power Plant Safety-Related Components to provide the assurance that the safety related equipment will meet their intended functions during normal operation and postulated accident conditions. The environmental qualification of these components is also a Licensing requirement for Darlington Nuclear Generating Station. This paper provides an overview of EQ and the experience of a pilot project, in the qualification of the Main Moderator System safety-related functions for the Darlington Nuclear Generating Station currently under construction. It addresses the various phases of qualification from the identification of the EQ Safety-Related Components List, definition of location specific service conditions (normal, adbnormal and accident), safety-related functions, Environmental Qualification Assessments and finally, an EQ system summary report for the Main Moderator System. The results of the pilot project are discussed and the methodology reviewed. The paper concludes that the EQ Program developed for Darlington Nuclear Generating Station, as applied to the qualification of the Main Moderator System, contained all the elements necessary in the qualification of safety-related equipment. The approach taken in the qualification of the Moderator safety-related equipment proves to provide a sound framework for the qualification of other safety-related components in the station

  11. SAMPLE RESULTS FROM THE INTEGRATED SALT DISPOSITION PROGRAM MACROBATCH 4 TANK 21H QUALIFICATION SAMPLES

    Energy Technology Data Exchange (ETDEWEB)

    Peters, T.; Fink, S.

    2011-06-22

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H to qualify them for use in the Integrated Salt Disposition Program (ISDP) Batch 4 processing. All sample results agree with expectations based on prior analyses where available. No issues with the projected Salt Batch 4 strategy are identified. This revision includes additional data points that were not available in the original issue of the document, such as additional plutonium results, the results of the monosodium titanate (MST) sorption test and the extraction, scrub strip (ESS) test. This report covers the revision to the Tank 21H qualification sample results for Macrobatch (Salt Batch) 4 of the Integrated Salt Disposition Program (ISDP). A previous document covers initial characterization which includes results for a number of non-radiological analytes. These results were used to perform aluminum solubility modeling to determine the hydroxide needs for Salt Batch 4 to prevent the precipitation of solids. Sodium hydroxide was then added to Tank 21 and additional samples were pulled for the analyses discussed in this report. This work was specified by Task Technical Request and by Task Technical and Quality Assurance Plan (TTQAP).

  12. Experience with the implementation of a risk-based ISI program and inspection qualification

    International Nuclear Information System (INIS)

    Chapman, O.J.V.

    1996-01-01

    Rolls Royce and Associates (RRA) are the Design Authority (DA) for Nuclear Steam Raising Plant (NSRP) used for the Royal Naval Nuclear Fleet. Over the past seven years RRA, with support from the Ministry of Defense, has developed and implemented a risk based in-service inspection (RBISI) strategy for the NSRP. Having used risk as a means of optimizing where to inspect, an inspection qualification (IQ) process has now been put in place to ensure that proposed inspections deliver the expected gains assumed. This qualification process follows very closely that currently being put forward by the European Network on Inspection Qualification (ENIQ)

  13. SAMPLE RESULTS FROM THE INTEGRATED SALT DISPOSITION PROGRAM MACROBATCH 5 TANK 21H QUALIFICATION MST, ESS AND PODD SAMPLES

    Energy Technology Data Exchange (ETDEWEB)

    Peters, T.; Fink, S.

    2012-04-24

    Savannah River National Laboratory (SRNL) performed experiments on qualification material for use in the Integrated Salt Disposition Program (ISDP) Batch 5 processing. This qualification material was a composite created from recent samples from Tank 21H and archived samples from Tank 49H to match the projected blend from these two tanks. Additionally, samples of the composite were used in the Actinide Removal Process (ARP) and extraction-scrub-strip (ESS) tests. ARP and ESS test results met expectations. A sample from Tank 21H was also analyzed for the Performance Objectives Demonstration Document (PODD) requirements. SRNL was able to meet all of the requirements, including the desired detection limits for all the PODD analytes. This report details the results of the Actinide Removal Process (ARP), Extraction-Scrub-Strip (ESS) and Performance Objectives Demonstration Document (PODD) samples of Macrobatch (Salt Batch) 5 of the Integrated Salt Disposition Program (ISDP).

  14. Initial results of strand produced in Phase 2 of the SSCL Vendor Qualification Program

    International Nuclear Information System (INIS)

    Erdmann, M.; Capone, D. II; Coleman, S.; Jones, B.; Seuntjens, J.

    1993-05-01

    In 1991, the Superconducting Super Collider Laboratory (SSCL) instituted a program to qualify specific superconductor manufacturers for production of cable acceptable for use in both Collider Dipole (CDM) and Quadrupole (CQM) magnets. The SSCL Vendor Qualification Program (VQP) was designed with two Phases. Phase 1 was divided into two additional phases, 1A and 1B, which ran concurrently. In Phase 1B, each vendor was directed to manufacture roughly 3000 kg of cable using a ''baseline'' process. The baseline process was agreed to by both the SSCL and the vendor at the beginning of the VQP. In this phase, process control was closely monitored with the use of statistical methods and each vendor was graded based on these results. Phase 1A, known as the R ampersand D phase, was developed to allow each vendor an opportunity to optimize and improve on their baseline process in terms of both cost and manufacturability. In this phase, multifilament billets were designed to explore several key variables such as alternate alloy sources, process modifications and improved billet designs. At the end of Phase 1, the results from both 1A and 1B were evaluated at a review between the SSCL and each vendor, and a final Phase 2 process was generated and fixed using the best results. In Phase 2, each vendor is required to manufacture roughly 6000 kg of superconducting cable under a firm fixed price contract which can then be used to create an accurate price estimate for competitive bidding on the full rate production CDM and CQM contracts. At the end of Phase 2, each vendor must meet the minimum requirements outlined in the contract to become a qualified superconducting cable supplier. For one requirement, critical process variables identified by the SSCL Conductor Department at the beginning of the VQP will be evaluated to determine the quality and uniformity of the material produced during Phase 2 of the program

  15. Sample Results from the Interim Salt Disposition Program Macrobatch 8 Tank 21H Qualification Samples

    Energy Technology Data Exchange (ETDEWEB)

    Peters, T. B. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Washington, A. L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2015-01-01

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 8 for the Interim Salt Disposition Program (ISDP). An Actinide Removal Process (ARP) and several Extraction-Scrub- Strip (ESS) tests were also performed. This document reports characterization data on the samples of Tank 21H as well as simulated performance of ARP and the Modular Caustic Side Solvent Extraction (CSSX) Unit (MCU). No issues with the projected Salt Batch 8 strategy are identified. A demonstration of the monosodium titanate (MST) (0.2 g/L) removal of strontium and actinides provided acceptable average decontamination factors for plutonium of 2.62 (4 hour) and 2.90 (8 hour); and average strontium decontamination factors of 21.7 (4 hour) and 21.3 (8 hour). These values are consistent with results from previous salt batch ARP tests. The two ESS tests also showed acceptable performance with extraction distribution ratios (D(Cs)) values of 52.5 and 50.4 for the Next Generation Solvent (NGS) blend (from MCU) and NGS (lab prepared), respectively. These values are consistent with results from previous salt batch ESS tests. Even though the performance is acceptable, SRNL recommends that a model for predicting extraction behavior for cesium removal for the blended solvent and NGS be developed in order to improve our predictive capabilities for the ESS tests.

  16. Sample results from the Interim Salt Disposition Program Macrobatch 8 Tank 21H qualification samples

    Energy Technology Data Exchange (ETDEWEB)

    Peters, T. B. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Washington, II, A. L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2015-01-13

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 8 for the Interim Salt Disposition Program (ISDP). An Actinide Removal Process (ARP) and several Extraction-Scrub-Strip (ESS) tests were also performed. This document reports characterization data on the samples of Tank 21H as well as simulated performance of ARP and the Modular Caustic Side Solvent Extraction (CSSX) Unit (MCU). No issues with the projected Salt Batch 8 strategy are identified. A demonstration of the monosodium titanate (MST) (0.2 g/L) removal of strontium and actinides provided acceptable average decontamination factors for plutonium of 2.62 (4 hour) and 2.90 (8 hour); and average strontium decontamination factors of 21.7 (4 hour) and 21.3 (8 hour). These values are consistent with results from previous salt batch ARP tests. The two ESS tests also showed acceptable performance with extraction distribution ratios (D(Cs)) values of 52.5 and 50.4 for the Next Generation Solvent (NGS) blend (from MCU) and NGS (lab prepared), respectively. These values are consistent with results from previous salt batch ESS tests. Even though the performance is acceptable, SRNL recommends that a model for predicting extraction behavior for cesium removal for the blended solvent and NGS be developed in order to improve our predictive capabilities for the ESS tests.

  17. Qualification Status of Non-Asbestos Internal Insulation in the Reusable Solid Rocket Motor Program

    Science.gov (United States)

    Clayton, Louie

    2011-01-01

    This paper provides a status of the qualification efforts associated with NASA's RSRMV non-asbestos internal insulation program. For many years, NASA has been actively engaged in removal of asbestos from the shuttle RSRM motors due to occupation health concerns where technicians are working with an EPA banned material. Careful laboratory and subscale testing has lead to the downselect of a organic fiber known as Polybenzimidazol to replace the asbestos fiber filler in the existing synthetic rubber copolymer Nitrile Butadiene - now named PBI/NBR. Manufacturing, processing, and layup of the new material has been a challenge due to the differences in the baseline shuttle RSRM internal insulator properties and PBI/NBR material properties. For this study, data gathering and reduction procedures for thermal and chemical property characterization for the new candidate material are discussed. Difficulties with test procedures, implementation of properties into the Charring Material Ablator (CMA) codes, and results correlation with static motor fire data are provided. After two successful five segment motor firings using the PBI/NBR insulator, performance results for the new material look good and the material should eventually be qualified for man rated use in large solid rocket motor applications.

  18. Qualification testing program plan for SIMMER. A computer code for LMFBR disrupted core analysis

    International Nuclear Information System (INIS)

    Basdekas, D.L.; Silberberg, M.; Curtis, R.T.; Kelber, C.N.

    1978-07-01

    The objective of SIMMER qualification testing program is to assure that the mathematical models and input parameters are derived from experimental data, which, on the basis of criteria still to be established, are representative of the phenomena and processes governing the progression of a CDA in an LMFBR. At the present time, the work to meet this objective can be classified into three general task areas as they relate to the use of SIMMER in CDA analysis: (1) The whole-core energetic disassembly accident, or the ''vessel problem'': The objective here is to predict the partition of the total energy release, by a postulated severe power excursion, between the primary containment and the energy absorbed through nondestructive dissipative processes. (2) Single subassembly accident: The objective here is to determine the pertinent phenomena and to develop the capability to assess the significance and likelihood that such accidents might propagate to involvement of larger fraction of the core. (3) The whole-core transition phase accident: The objective here is to advance the understanding of the phenomena and processes involved, so that reliable predictions can be made of the possible consequences of a CDA and the potential for further nuclear excursions through recriticality

  19. Qualification requirements and training programs for nonreactor nuclear facility personnel in the Operations Division of the Oak Ridge National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Preston, E.L.; Culbert, W.H.; Baldwin, M.E.; McCormack, K.E.; Rivera, A.L.; Setaro, J.A.

    1985-11-01

    This document describes the program for training, retraining, and qualification of nonreactor nuclear operators in the Operations Division of the Oak Ridge National Laboratory. The objective of the program is to provide the Operators and Supervisors of nuclear facilities the knowledge and skills needed to perform assigned duties in a safe and efficient manner and to comply with US Department of Energy Order 5480.1A Chapter V. This order requires DOE nuclear facilities to maintain formal training programs for their operating staff and documentation of that training.

  20. Qualification requirements and training programs for nonreactor nuclear facility personnel in the Operations Division of the Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Preston, E.L.; Culbert, W.H.; Baldwin, M.E.; McCormack, K.E.; Rivera, A.L.; Setaro, J.A.

    1985-11-01

    This document describes the program for training, retraining, and qualification of nonreactor nuclear operators in the Operations Division of the Oak Ridge National Laboratory. The objective of the program is to provide the Operators and Supervisors of nuclear facilities the knowledge and skills needed to perform assigned duties in a safe and efficient manner and to comply with US Department of Energy Order 5480.1A Chapter V. This order requires DOE nuclear facilities to maintain formal training programs for their operating staff and documentation of that training

  1. Constellation Program Electrical Ground Support Equipment Research and Development

    Science.gov (United States)

    McCoy, Keegan S.

    2010-01-01

    At the Kennedy Space Center, I engaged in the research and development of electrical ground support equipment for NASA's Constellation Program. Timing characteristics playa crucial role in ground support communications. Latency and jitter are two problems that must be understood so that communications are timely and consistent within the Kennedy Ground Control System (KGCS). I conducted latency and jitter tests using Alien-Bradley programmable logic controllers (PLCs) so that these two intrinsic network properties can be reduced. Time stamping and clock synchronization also play significant roles in launch processing and operations. Using RSLogix 5000 project files and Wireshark network protocol analyzing software, I verified master/slave PLC Ethernet module clock synchronization, master/slave IEEE 1588 communications, and time stamping capabilities. All of the timing and synchronization test results are useful in assessing the current KGCS operational level and determining improvements for the future.

  2. Boosting program integrity and effectiveness of the cognitive behavioral program EQUIP for incarcerated youth in The Netherlands

    NARCIS (Netherlands)

    Helmond, P.; Overbeek, G.; Brugman, D.

    2014-01-01

    This study examined whether a "program integrity booster" could improve the low to moderate program integrity and effectiveness of the EQUIP program for incarcerated youth as practiced in The Netherlands. Program integrity was assessed in EQUIP groups before and after the booster. Youth residing in

  3. Sample Results From The Interim Salt Disposition Program Macrobatch 7 Tank 21H Qualification Samples

    Energy Technology Data Exchange (ETDEWEB)

    Peters, T. B.; Washington, A. L. II

    2013-08-08

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 7 for the Interim Salt Disposition Program (ISDP). An ARP and several ESS tests were also performed. This document reports characterization data on the samples of Tank 21H as well as simulated performance of ARP/MCU. No issues with the projected Salt Batch 7 strategy are identified, other than the presence of visible quantities of dark colored solids. A demonstration of the monosodium titanate (0.2 g/L) removal of strontium and actinides provided acceptable 4 hour average decontamination factors for Pu and Sr of 3.22 and 18.4, respectively. The Four ESS tests also showed acceptable behavior with distribution ratios (D(Cs)) values of 15.96, 57.1, 58.6, and 65.6 for the MCU, cold blend, hot blend, and Next Generation Solvent (NGS), respectively. The predicted value for the MCU solvent was 13.2. Currently, there are no models that would allow a prediction of extraction behavior for the other three solvents. SRNL recommends that a model for predicting extraction behavior for cesium removal for the blended solvent and NGS be developed. While no outstanding issues were noted, the presence of solids in the samples should be investigated in future work. It is possible that the solids may represent a potential reservoir of material (such as potassium) that could have an impact on MCU performance if they were to dissolve back into the feed solution. This salt batch is intended to be the first batch to be processed through MCU entirely using the new NGS-MCU solvent.

  4. Apollo experience report: Development flight instrumentation. [telemetry equipment for space flight test program

    Science.gov (United States)

    Farmer, N. B.

    1974-01-01

    Development flight instrumentation was delivered for 25 Apollo vehicles as Government-furnished equipment. The problems and philosophies of an activity that was concerned with supplying telemetry equipment to a space-flight test program are discussed. Equipment delivery dates, system-design details, and flight-performance information for each mission also are included.

  5. Results from the interim salt disposition program macrobatch 10 tank 21H qualification samples

    Energy Technology Data Exchange (ETDEWEB)

    Peters, T. B. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Bannochie, C. J. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2017-02-23

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 10 for the Interim Salt Disposition Program (ISDP). This document reports characterization data on the samples of Tank 21H and fulfills the requirements of Deliverable 3 of the Technical Task Request (TTR). Further work will report the results of the Extraction-Scrub-Strip (ESS) testing (Task 5 of the TTR) using the Tank 21H material. Task 4 of the TTR (MST Strike) will not be completed for Salt Batch 10.

  6. Results from the DOE Advanced Gas Reactor Fuel Development and Qualification Program

    Energy Technology Data Exchange (ETDEWEB)

    David Petti

    2014-06-01

    Modular HTGR designs were developed to provide natural safety, which prevents core damage under all design basis accidents and presently envisioned severe accidents. The principle that guides their design concepts is to passively maintain core temperatures below fission product release thresholds under all accident scenarios. This level of fuel performance and fission product retention reduces the radioactive source term by many orders of magnitude and allows potential elimination of the need for evacuation and sheltering beyond a small exclusion area. This level, however, is predicated on exceptionally high fuel fabrication quality and performance under normal operation and accident conditions. Germany produced and demonstrated high quality fuel for their pebble bed HTGRs in the 1980s, but no U.S. manufactured fuel had exhibited equivalent performance prior to the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program. The design goal of the modular HTGRs is to allow elimination of an exclusion zone and an emergency planning zone outside the plant boundary fence, typically interpreted as being about 400 meters from the reactor. To achieve this, the reactor design concepts require a level of fuel integrity that is better than that claimed for all prior US manufactured TRISO fuel, by a few orders of magnitude. The improved performance level is about a factor of three better than qualified for German TRISO fuel in the 1980’s. At the start of the AGR program, without a reactor design concept selected, the AGR fuel program selected to qualify fuel to an operating envelope that would bound both pebble bed and prismatic options. This resulted in needing a fuel form that could survive at peak fuel temperatures of 1250°C on a time-averaged basis and high burnups in the range of 150 to 200 GWd/MTHM (metric tons of heavy metal) or 16.4 to 21.8% fissions per initial metal atom (FIMA). Although Germany has demonstrated excellent performance of TRISO-coated UO

  7. Recommendations for the elaboration of a training program and personnel qualification of the regulatory body

    International Nuclear Information System (INIS)

    Medina Gironzini, E.; Bonacossa de Almeida, C.; Jimenez Rojas, M.; Pacheco Jimenez, R.; Prendes Alonso, M.; Tomas Zerquera, J.

    2013-01-01

    In this work are defined training methods and provides details on the qualifications of staff and the use of the method of the four quadrants where competencies are established: legal framework and regulatory responsibilities, technical disciplines, regulatory procedures and personal attributes. It is the first time that will make these recommendations in the region and is expected to be very useful for the regulator institutions

  8. Qualification of quality assurance program audit personnel for nuclear power plants

    International Nuclear Information System (INIS)

    Anon.

    1979-01-01

    Requirements and guidance are provided for the qualification of Auditors and Lead Auditors who perform audits for plant owners, contractors or others participating in activities affecting the quality of structures, systems and components of nuclear power plants. The Lead Auditor is the audit team leader, who organizes and directs audits, reports, audit findings, and evaluates corrective action. Auditors include technical specialists, management representatives and auditors-in-training. This standard is to be used in conjunction with ANSI N45.2.12

  9. The comparison of System 1000 analysis and type testing for neoprene gasket environmental qualification

    International Nuclear Information System (INIS)

    Park, Kyung Heum; Kim, Jong Seok; Jeong, Sun Chul; Jang, Kyung Nam; Hwang, Sung Phil

    2010-01-01

    The typical environmental qualification is to ensure that equipment will operate on demand to meet system performance requirements during normal and abnormal service conditions. There are four environmental qualification methods, type testing, operating experience, analysis and combined method. Generally, the American EQ do not contain the mechanical equipment like pumps and valves in their EQ equipment list because their EQ standard 10CFR50.49 limits EQ equipment as electrical equipment. On the other hand, Canadian EQ contain the mechanical equipment like pumps and valves in their EQ components list, Canadians usually call American 'equipment' as 'components', because their EQ standard CSA N290.13-05 do not limits EQ equipment as electrical equipment. System 1000 program is typical Canadian EQ analysis method using mathematical modeling and comparison with established engineering information and manufacturers' data. Most of Canadian nuclear power utilities like NB Power, Hydro Quebec and OPG use the System 1000 program to evaluate the design life for their EQ components. To qualify a pump, I had to list all the non-metallic parts in the pump and found there are lots of gaskets made by neoprene material. I tried to qualify these neoprene gaskets by analysis using System 1000 program and by type testing. In this paper, I'd like to introduce the qualification results of neoprene gasket both type testing and analysis using System 1000 program

  10. 'Outside the box thinking': An overview of an environmental qualification test from a test lab perspective

    International Nuclear Information System (INIS)

    Mitton, T.

    2004-01-01

    Most people in the nuclear Environmental Qualification (EQ) business know that the basis for qualification ultimately lies with an equipment's successful operation during and after exposure to a simulated harsh environment. As opposed to focusing specifically on the test results of an Environmental Qualification test program, this paper/presentation will offer a more detailed look at the mechanical, electrical and thermodynamic requirements as well as the project difficulties and solutions of one such project - particularly an extensive, large-scale, non-typical project. (author)

  11. Remote handling equipment design for the HEDL fuel supply program

    International Nuclear Information System (INIS)

    Metcalf, I.L.

    1984-09-01

    A process line is currently being developed for fabrication of high exposure mixed uranium-plutonium core assemblies. This paper describes the design philosophy, process flow, equipment, and the handling and radiation shielding techniques used for inspection of Fast Flux Test Facility (FFTF) fuel pins and assembly of Driver Fuel Assemblies (DFAs) 6 figures

  12. Small Portable Analyzer Diagnostic Equipment (SPADE) Program -- Diagnostic Software Validation

    Science.gov (United States)

    1984-07-01

    Electronic Equipment Electromagnetic Emission and Susceptibility Requirements for the Control of Electromagnetic Interference Electromagnetic...ONLY. ORIENTATION OF DEFECT LOOKING HHO QIlILL: t -ed’-o· Significant efforts were expended to simulate spalling failures associated with naturally

  13. Qualification according to PDI's techniques UT EPRI methodology Phased Array for the inspection of vessels of PWR reactor with advanced robotic equipment; Cualificacion segun metodologia PDI de EPRI de te cnicas UT Phased Array para la inspeccion de vasijas de reactor PWR con eq uipos roboticos avanzados

    Energy Technology Data Exchange (ETDEWEB)

    Gadea, J. R.; Gonzalez, P.; Fernandez, F.

    2014-07-01

    The techniques and procedures qualified in the program EPRI PDI are directly applicable in plants whose reference code is ASME XI - specifically the Appendix VIII-, mainly USA and countries in which it is established American PWR technology. While countries with reactors in operation technology ABB (Sweden) or type VVER (Finland and Eastern countries) requires a qualification of specific technical type ENIQ, PDI qualification is a valuable reference since it allows to deal with such qualifications with guarantees. (Author)

  14. Democratic Dialogue as a Process to Inform Public Policy: Reconceptualizing a Supervisory Officer’s Qualification Program

    Directory of Open Access Journals (Sweden)

    Deirdre M. Smith

    2015-06-01

    Full Text Available An exploration of the collaborative reconceptualization of a provincial Supervisory Officer’s Qualification Program (SOQP through the use of dialogic approaches is the focus of this inquiry. The stories, perspectives, and lived experiences of supervisory officers, principals, teachers, parents, students, and members of the public in Ontario were included as essential voices and information sources within policy development conversations. These narratives of experience revealed the forms of knowledge, skills, dispositions, and ethical commitments necessary for effective supervisory officers today and in the future. They also illustrated the transformative nature of narrative dialogue to enlighten, deepen understanding, and alter perspec- tives. The policy development processes used in this publicly shared educational initiative serve as a model of democratic dialogue. The inclusive and dialogic methods employed to collectively reconceptualize a supervisory officer formation program illustrate an innovative framework for developing policies governing the public good.

  15. Guidelines for Selection, Screening and Qualification of Low-Voltage Commercial Multilayer Ceramic Capacitors for Space Programs

    Science.gov (United States)

    Teverovsky, Alexander A.

    2012-01-01

    This document has been developed in the course of NASA Electronic Parts and Packaging (NEPP) program and is not an official endorsement of the insertion of commercial capacitors in space programs or an established set of requirements for their testing. The purpose of this document is to suggest possible ways for selection, screening, and qualification of commercial capacitors for NASA projects and open discussions in the parts engineering community related to the use of COTS ceramic capacitors. This guideline is applicable to commercial surface mount chip, simple parallel plate design, multi-layer ceramic capacitors (MLCCs) rated to voltages of 100V and less. Parts with different design, e.g. low inductance ceramic capacitors (LICA), land grid array (LGA) etc., might need additional testing and tailoring of the requirements described in this document. Although the focus of this document is on commercial MLCCs, many procedures discussed below would be beneficial for military-grade capacitors

  16. The CABRI fast neutron Hodoscope: Renovation, qualification program and first results following the experimental reactor restart

    Science.gov (United States)

    Chevalier, V.; Mirotta, S.; Guillot, J.; Biard, B.

    2018-01-01

    The CABRI experimental pulse reactor, located at the Cadarache nuclear research center, southern France, is devoted to the study of Reactivity Initiated Accidents (RIA). For the purpose of the CABRI International Program (CIP), managed and funded by IRSN, in the framework of an OECD/NEA agreement, a huge renovation of the facility has been conducted since 2003. The Cabri Water Loop was then installed to ensure prototypical Pressurized Water Reactor (PWR) conditions for testing irradiated fuel rods. The hodoscope installed in the CABRI reactor is a unique online fuel motion monitoring system, operated by IRSN and dedicated to the measurement of the fast neutrons emitted by the tested rod during the power pulse. It is one of the distinctive features of the CABRI reactor facility, which is operated by CEA. The system is able to determine the fuel motion, if any, with a time resolution of 1 ms and a spatial resolution of 3 mm. The hodoscope equipment has been upgraded as well during the CABRI facility renovation. This paper presents the main outcomes achieved with the hodoscope since October 2015, date of the first criticality of the CABRI reactor in its new Cabri Water Loop configuration. Results obtained during reactor commissioning phase functioning, either in steady-state mode (at low and high power, up to 23 MW) or in transient mode (start-up, possibly beyond 20 GW), are discussed.

  17. Technical qualification requirements and training programs for radiation protection personnel at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Copenhaver, E.D.; Houser, B.S.; Butler, H.M. Jr.; Bogard, J.S.; Fair, M.F.; Haynes, C.E.; Parzyck, D.C.

    1986-04-01

    This document deals with the policies and practices of the Environmental and Occupational Safety Division (EOSD) at the Oak Ridge National Laboratory (ORNL) in regard to the selection, training, qualification, and requalification of radiation protection staff assigned to reactor and nonreactor nuclear facilities. Included are personnel at facilities that: (1) operate reactors or particle accelerators; (2) produce, process, or store radioactive liquid or solid waste; (3) conduct separations operations; (4) engage in research with radioactive materials and radiation sources; and (5) conduct irradiated materials inspection, fuel fabrication, deconamination, or recovery operations. The EOSD personnel also have environmental surveillance and operational and industrial safety responsibilities related to the total Laboratory

  18. Interim salt disposition program macrobatch 6 tank 21H qualification monosodium titanate and cesium mass transfer tests

    Energy Technology Data Exchange (ETDEWEB)

    Washington, A. L. II; Peters, T. B.; Fink, S. D.

    2013-02-25

    Savannah River National Laboratory (SRNL) performed experiments on qualification material for use in the Interim Salt Disposition Program (ISDP) Batch 6 processing. This qualification material was a set of six samples from Tank 21H in October 2012. This sample was used as a real waste demonstration of the Actinide Removal Process (ARP) and the Extraction-Scrub-Strip (ESS) tests process. The Tank 21H sample was contacted with a reduced amount (0.2 g/L) of MST and characterized for strontium and actinide removal at 0 and 8 hour time intervals in this salt batch. {sup 237}Np and {sup 243}Am were both observed to be below detection limits in the source material, and so these results are not reported in this report. The plutonium and uranium samples had decontamination factor (DF) values that were on par or slightly better than we expected from Batch 5. The strontium DF values are slightly lower than expected but still in an acceptable range. The Extraction, Scrub, and Strip (ESS) testing demonstrated cesium removal, stripping and scrubbing within the acceptable range. Overall, the testing indicated that cesium removal is comparable to prior batches at MCU.

  19. Analysis of Refrigeration Equipment in School Nutrition Programs in the USDA/FNS Southwest Region

    Science.gov (United States)

    Webb, Virginia Susan

    2012-01-01

    Equipment to store foods at proper temperatures is critical to serving safe and nutritious meals in schools yet little is known about the amount or the adequacy of refrigerated storage in school nutrition programs. The purposes of this study were to identify the types and capacity of refrigeration equipment used in schools, determine the perceived…

  20. Joint Oil Analysis Program Spectrometer Standards SCP Science (Conostan) Qualification Report for D19-0, D3-100, and D12-XXX Series Standards

    Science.gov (United States)

    2015-05-20

    Joint Oil Analysis Program Spectrometer Standards SCP Science (Conostan) Qualification Report For D19-0, D3-100, and D12- XXX Series Standards NF...Candidate Type D19-0 ICP-AES Results ..................................................................... 4 Table V. Candidate Type D12- XXX ...Physical Property Results .................................................. 5 Table VI. Candidate Type D12- XXX Rotrode-AES Results

  1. TDRSS multimode transponder program. Phase 2: Equipment development

    Science.gov (United States)

    Cnossen, R. S.

    1974-01-01

    This report contains a complete description of the TDRS Multimode Transponder and its associated ground support equipment. The transponder will demonstrate candidate modulation techniques to provide the required information for the design of an eventual VHF/UHF transponder suitable for installation in a user satellite, capable of operating as part of a Tracking and Data Relay Satellite (TDRS) systems. Use of geosynchronous TDRS which can serve both low data rate users at VHF and high data rate users at other frequencies has been considered. The effects of radio frequency interference from the earth and of multipath propagation due to reflections from the earth are expected to pose problems for the TDRS system at VHF. Investigations have suggested several modulation techniques that offer promise to overcome these problems.

  2. Hybrid Qualifications

    DEFF Research Database (Denmark)

    Against the background of increasing qualification needs there is a growing awareness of the challenge to widen participation in processes of skill formation and competence development. At the same time, the issue of permeability between vocational education and training (VET) and general education...... has turned out as a major focus of European education and training policies and certainly is a crucial principle underlying the European Qualifications Framework (EQF). In this context, «hybrid qualifications» (HQ) may be seen as an interesting approach to tackle these challenges as they serve «two...

  3. Qualification program for JHR fuel elements: Irradiation of the first JHR test assembly in the BR2-Evita loop

    International Nuclear Information System (INIS)

    Anselmet, M.-C.; Lemoine, P.; Koonen, E.; Benoit, P.; Gouat, P.; Claes, W.; Geens, F.; Miras, G.; Brisson, S.

    2010-01-01

    An experimental program has been designed by CEA to qualify the behaviour of the JHR fuel under conditions representative of the reactor operating ones. This program uses the SCK.CEN facilities, irradiating JHR lead test elements in the BR2 reactor, inside its central channel which has been particularly arranged for this objective (Evita loop). As a first step in the program, a two cycle irradiation (4 weeks by cycle) started mid-July 2009 and ended mid-November (EVITA-1). After a cooling phase, this first JHR lead test element will be submitted to post-irradiation examination. The second JHR test element began its irradiation in the first quarter of 2010; its unloading is planned before the end of 2010, after 5 cycles in the BR2 reactor. The results of these two experiments are expected as input information for the Safety Authority Report. This paper presents the qualification program with the objectives assigned to each phase (irradiation, examination). A first interpretation of the irradiation data for the first element is presented, so as the information available on the progress of the following phases of the programme. (author)

  4. Standard guide for the selection, training and qualification of nondestructive assay (NDA) personnel

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2004-01-01

    1.1 This guide contains good practices for the selection, training, qualification, and professional development of personnel performing analysis, calibration, physical measurements, or data review using nondestructive assay equipment, methods, results, or techniques. The guide also covers NDA personnel involved with NDA equipment setup, selection, diagnosis, troubleshooting, or repair. Selection, training, and qualification programs based on this guide are intended to provide assurance that NDA personnel are qualified to perform their jobs competently. This guide presents a series of options but does not recommend a specific course of action.

  5. A Competency-Based Program for Electronic Gaming Equipment Repair.

    Science.gov (United States)

    Hardman, James R.

    This program is designed to provide entry-level training to individuals (especially workers displaced from industry) who desire employment as "slot technicians" in the casino industry. The 96-hour course includes both classroom instruction and hands-on experience. Sources for direct purchase of required manuals are provided. The 13…

  6. Components of a comprehensive capital equipment planning program.

    Science.gov (United States)

    Gresch, Alan

    2010-01-01

    As you may have already figured out, there is crossover and gaps between all of these capital equipment components. CE often will, and proactively should, make recommendations based on the CE, clinical, and financial components but rarely has direct knowledge of the strategic element. The clinical, finance, and administrative folks likely have visibility to most of these, but may lack full awareness of at least one component. The key is to engage key stakeholders from all these critical areas and develop a process to pull all this information together in one nice, neat package. Defining the person or persons responsible for taking the lead on this in your organization will depend greatly on the organization's type and size. For a single, standalone community hospital, it will likely be the facility administrator. For an integrated delivery network (IDN), a corporate entity, led by supply chain, finance, or both, may take the lead. Your organization may also employ consultative services or software to help facilitate this function. Regardless of who takes the lead, a weighting or scoring system that assigns certain values in all the outlined component categories, is clearly defined, and is easy to understand for all the contributors will need to be developed. If you are unaware or unclear of what the process is, find out and figure out how you can be a vital contributor to the process. This is one more way you can demonstrate the value you and your department bring to your organization.

  7. Mechanical design and construction qualification program on ITER correction coils structures

    Energy Technology Data Exchange (ETDEWEB)

    Foussat, A., E-mail: arnaud.foussat@iter.org [ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance (France); Weiyue, Wu; Jing, Wei; Shuangsong, Du [Academy of Science Institute of Plasma Physics, PO 1126, Hefei, Anhui 230031 (China); Sgobba, S. [European Center for Nuclear Research, CH-1211 Geneva 23 (Switzerland); Hongwei, Li [China International Nuclear Fusion Energy Program Execution Center, Ministry of Science and Technology, 15B Fuxing Rd., Beijing 100862 (China); Libeyre, Paul; Jong, Cornelis; Klofac, Kamil; Mitchell, Neil [ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance (France)

    2014-04-01

    The ITER Magnet system consists of 4 main coils sub-systems, i.e. 18 toroidal field coils (TFC), a central solenoid (CS), 6 poloidal field coils (PF) and 3 sets of correction coils (CC). The ITER fusion project has selected the stainless steel 316LN as main material for the magnet structure. The CC contribute to reducing the range of magnetic error fields created by imperfections in the location and geometry of the other coils used to confine, heat, and shape the plasma. During plasma operation, a large number of loading condition scenarios have been considered and structural analysis performed on key items like Cable-In-Conduit Conductor and the coil case. The results obtained are used for both static and fatigue structural assessment defining the present baseline design. For the construction of the structural cases, welding techniques such as GTAW (Gas Tungsten Arc Welding) and techniques resulting in low distortion and shrinkage like EBW (Electron Beam Welding) or Laser Beam Welding (LBW) with filler metal wire have been selected. Those methods are considered for future qualifications to guarantee proper weld parameters and specified weld properties. In order to determine the strength and fracture toughness of 316LN stainless steel welds with respect to design criteria, some mechanical tests have been carried out at 7 K (or 77 K), and room temperature.

  8. Training and qualification of nuclear power plant operators (4)

    International Nuclear Information System (INIS)

    Ohsuga, Y.

    2009-01-01

    Training center using the simulators, instructor training, training upgrade, deployment of digital control panel and review of training were described with overseas practice. Recently, nuclear power plant on-site simulators were also used for respective operator training. Operator teamwork training, training team performance upgrade, reflection of operating experiences in nuclear power plant accidents, development of training support equipments and management of training records were needed to review and upgrade training and qualification programs. (T. Tanaka)

  9. Qualification of flat welding of nuclear fuel bars

    International Nuclear Information System (INIS)

    Romero C, J.; Rivera M, H.

    2001-01-01

    The qualification of flat welding consists in the process (procedures (11), instructions (5), specifications (4) and programs (3)) and equipment (systems (4), equipment (6)) with the Personal Qualification (operators and supervisors) that was done in simultaneous form and supported with test and training programs with its respective technical reports, liberated by the Quality Assurance Office of ININ. Moreover, specific procedures of process and personal qualification are realized with the respective supervision by Quality Assurance Office. For the process, 20 welding were realized as follow: 5 welding with maximum contributing of heat, 10 welding with nominal contributing of heat, 5 welding with minimum contributing of heat. The heat contributing for the qualification was done maximum, of increasing the welding current, diminishing the helium flux and the revolutions per minute of the bar, at the moment of welding, with respect to nominal values. In the minimum contributing of heat it is diminished the welding current, increasing the helium flux and the revolutions per minute of the bar with respect to nominal values. With the qualification it has been finished the development of flat welding with results which define an own method of ININ. It was implemented a pneumatic system, for the elimination of micron cracks. It was required a control of turn velocity of the bar of hundredth of revolution. Moreover the main welding parameters each 40 μs are acquired. Also it was automated completely the process to avoid possible human mistakes. The standard deviations of the values of the realized inspections in the quality, are lower. Process, equipment and personnel with their respective Quality reports and registries are qualified, as well as the Quality certificates of two operators and one supervisor. (Author)

  10. Program for in-pile qualification of high density silicide dispersion fuel at IPEN/CNEN-SP

    International Nuclear Information System (INIS)

    Silva, Jose E.R. da; Silva, Antonio T. e; Terremoto, Luis A.A.; Durazzo, Michelangelo

    2009-01-01

    The development of high density nuclear fuel (U 3 Si 2 -Al) with 4,8 gU/cm 3 is on going at IPEN, at this time. This fuel has been considered to be utilized at the new Brazilian Multipurpose Reactor (RMB), planned to be constructed up to 2014. As Brazil does not have hot-cell facilities available for post-irradiation analysis, an alternative qualifying program for this fuel is proposed based on the same procedures used at IPEN since 1988 for qualifying its own U 3 O 8 -Al (1,9 and 2,3 gU/cm 3 ) and U 3 Si 2 -Al (3,0 gU/cm 3 ) dispersion fuels. The fuel miniplates and full-size fuel elements irradiations should be tested at IEA-R1 core. The fuel characterization along the irradiation time should be made by means of non-destructive methods, including periodical visual inspections with an underwater video camera system, sipping tests for fuel elements suspected of leakage, and underwater dimensional measurements for swelling evaluation, performed inside the reactor pool. This work presents the program description for the qualification of the high density nuclear fuel (U 3 Si 2 -Al) with 4,8 gU/cm 3 , and describes the IPEN fuel fabrication infrastructure and some basic features of the available systems for non-destructive tests at IEA-R1 research reactor. (author)

  11. Qualification of software and hardware

    International Nuclear Information System (INIS)

    Gossner, S.; Schueller, H.; Gloee, G.

    1987-01-01

    The qualification of on-line process control equipment is subdivided into three areas: 1) materials and structural elements; 2) on-line process-control components and devices; 3) electrical systems (reactor protection and confinement system). Microprocessor-aided process-control equipment are difficult to verify for failure-free function owing to the complexity of the functional structures of the hardware and to the variety of the software feasible for microprocessors. Hence, qualification will make great demands on the inspecting expert. (DG) [de

  12. A program to improve educational qualifications of reactor site technical personnel

    International Nuclear Information System (INIS)

    Christenson, J.M.; Eckart, L.E.

    1982-01-01

    The authors describe the planning and execution of a program that meets all of the Institute for Nuclear Power Operations (INPO) recommendations and Nuclear Regulatory Commission (NRC) requirements for Shift Technical Advisor (STA) education. They recall and comment these recommendations and requirements, the classification categories of the prospective candidates, indicate the courses proposed by the education program, comment the implementation of the STA program plan

  13. OSMOSE: An experimental program for the qualification of integral cross sections of actinides

    International Nuclear Information System (INIS)

    Hudelot, J. P.; Klann, R.; Fougeras, P.; Jorion, F.; Drin, N.; Donnet, L.

    2004-01-01

    The accurate integral cross sectional reaction rates in representative spectra for the actinides are discussed at OSMOSE program. The first step in obtaining better nuclear data consists of measuring accurate integral data and comparing it to integrated energy dependent data: this comparison provides a direct assessment of the effect of deficiencies in the differential data. The OSMOSE program includes a complete analytical program associated with experimental measurement program and aims at understanding and resolving discrepancies between calculated and measured values. The measurement covers a wide range of neutron spectra, from over-moderate thermal spectra to fast spectra. (authors)

  14. Seismic qualification testing at the National Engineering Laboratory

    International Nuclear Information System (INIS)

    Fairbairn, J.

    1984-01-01

    Servohydraulic shaker tables have been developed for the simulation of vibration environments including earthquakes. The use of these facilities for seismic qualification of nuclear equipment is described. (author)

  15. Economic impact evaluation of the Procap 1000: Deep Water Qualification Program from PETROBRAS

    International Nuclear Information System (INIS)

    Furtado, Andre T.; Pereira, Newton M.; Suslick, Saul; Freitas, Adriana G. de; Bach, Laurent

    1999-01-01

    PETROBRAS, a Brazilian petroleum company, managed between 1986 and 1992 a program with purpose to dominate the necessary technology for the petroleum production up to 1000 meters depth. This program was going called Procap 1000. The aim of the work was to evaluate the impacts of Procap 1000. The proposed evaluation method by Beta was going used. The results are presented

  16. Participant outcomes, perceptions, and experiences in the Internationally Educated Engineers Qualification Program, University of Manitoba: An exploratory study

    Science.gov (United States)

    Friesen, Marcia R.

    Immigration, economic, and regulatory trends in Canada have challenged all professions to examine the processes by which immigrant professionals (international graduates) achieve professional licensure and meaningful employment in Canada. The Internationally Educated Engineers Qualification Program (IEEQ) at the University of Manitoba was developed as an alternate pathway to integrate international engineering graduates into the engineering profession in Manitoba. However, universities have the neither mandate nor the historical practice to facilitate licensure for immigrant professionals and, thus, the knowledge base for program development and delivery is predominantly experiential. This study was developed to address the void in the knowledge base and support the program's ongoing development by conducting a critical, exploratory, participant-oriented evaluation of the IEEQ Program for both formative and summative purposes. The research questions focussed on how the IEEQ participants perceived and described their experiences in the IEEQ Program, and how the participants' outcomes in the IEEQ Program compared to international engineering graduates pursuing other licensing pathways. The study was built on an interpretivist theoretical approach that supported a primarily qualitative methodology with selected quantitative elements. Data collection was grounded in focus group interviews, written questionnaires, student reports, and program records for data collection, with inductive data analysis for qualitative data and descriptive statistics for quantitative data. The findings yielded rich understandings of participants' experiences in the IEEQ Program, their outcomes relative to international engineering graduates (IEGs) pursuing other licensing pathways, and their perceptions of their own adaptation to the Canadian engineering profession. Specifically, the study suggests that foreign credentials recognition processes have tended to focus on the recognition and

  17. Analysis of the AMMON experimental program in the EOLE facility supporting the qualification of the JHR neutron and photon tools

    International Nuclear Information System (INIS)

    Vaglio-Gaudard, C.; Colombier, A.C.; Hudelot, J.P.; Leray, O.; Lemaire, M.; Di-Salvo, J.; Gruel, A.; Sireta, P.

    2013-06-01

    The first divergence of the international Jules Horowitz Material Testing Reactor under construction at CEA Cadarache is foreseen in 2016. In order to perform all the design and safety studies, a specific neutron and photon calculation tool, HORUS3D/N and P, dedicated to the JHR simulation, was developed. This development follows the V and V-UQ process; in this frame, the validation and qualification steps aim at quantifying all the biases and associated uncertainties of HORUS3D/N and P calculations. These biases originate from both the nuclear data and the calculation scheme, for calculations at step zero (JHR BOL core) or during depletion (JHR core at equilibrium). This paper focusses on the quantification of the biases due to nuclear data and the associated uncertainties. A new experimental program, named AMMON, was performed between 2010 and 2013 to provide experimental data for this quantification. A large part of the measurements has been today analyzed with the Monte Carlo TRIPOLI-4 R code and the JEFF3.1.1 and EPDL97 data libraries relative to neutron/photon transport and photon emission. The C/E results were transposed from AMMON to JHR. The synthesis of the present analysis is very satisfactory. The calculation biases remains limited. In addition, thanks to a very good control to the experimental uncertainties during measurements, it is shown that the a priori uncertainties due to nuclear data for parameters at step zero was reduced up to a factor of 2. (authors)

  18. Extraction, -scrub, -strip test results from the interim salt disposition program macrobatch 10 tank 21H qualification samples

    Energy Technology Data Exchange (ETDEWEB)

    Peters, T. B. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2017-06-26

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 10 for the Interim Salt Disposition Program (ISDP). The Salt Batch 10 characterization results were previously reported.ii,iii An Extraction, -Scrub, -Strip (ESS) test was performed to determine cesium distribution ratios (D(Cs)) and cesium concentration in the strip effluent (SE) and decontaminated salt solution (DSS) streams; this data will be used by Tank Farm Engineering to project a cesium decontamination factor (DF). This test used actual Tank 21H material, and a sample of the NGS Blend solvent currently being used at the Modular Caustic-Side Solvent Extraction Unit (MCU). The ESS test showed acceptable performance with an extraction D(Cs) value of 110. This value is consistent with results from previous salt batch ESS tests using similar solvent formulations. This is better than the predicted value of 39.8 from a recently created D(Cs) model.

  19. Technical basis for environmental qualification of computer-based safety systems in nuclear power plants

    International Nuclear Information System (INIS)

    Korsah, K.; Wood, R.T.; Tanaka, T.J.; Antonescu, C.E.

    1997-01-01

    This paper summarizes the results of research sponsored by the US Nuclear Regulatory Commission (NRC) to provide the technical basis for environmental qualification of computer-based safety equipment in nuclear power plants. This research was conducted by the Oak Ridge National Laboratory (ORNL) and Sandia National Laboratories (SNL). ORNL investigated potential failure modes and vulnerabilities of microprocessor-based technologies to environmental stressors, including electromagnetic/radio-frequency interference, temperature, humidity, and smoke exposure. An experimental digital safety channel (EDSC) was constructed for the tests. SNL performed smoke exposure tests on digital components and circuit boards to determine failure mechanisms and the effect of different packaging techniques on smoke susceptibility. These studies are expected to provide recommendations for environmental qualification of digital safety systems by addressing the following: (1) adequacy of the present preferred test methods for qualification of digital I and C systems; (2) preferred standards; (3) recommended stressors to be included in the qualification process during type testing; (4) resolution of need for accelerated aging in qualification testing for equipment that is to be located in mild environments; and (5) determination of an appropriate approach to address smoke in a qualification program

  20. 40 CFR 1054.626 - What special provisions apply to equipment imported under the Transition Program for Equipment...

    Science.gov (United States)

    2010-07-01

    ... EMISSIONS FROM NEW, SMALL NONROAD SPARK-IGNITION ENGINES AND EQUIPMENT Special Compliance Provisions § 1054... provisions of this section and send us an annual report, as follows: (1) Notify the Designated Compliance... and manufacturing equipment. Companies that import equipment into the United States without meeting...

  1. The U.S. Navy’s Consultant Development and Qualification Program: Origin and Issues.

    Science.gov (United States)

    1984-03-01

    Navy-wide program, probably as part of an NMPC OE manual (Ref. 9]. a. Pcific Fleet The HRMSYSPACINST 1500.1 is an admirably brief instruction, thirty...profesional OD organizacion external. to USN. 5. The above guidance is not intended to preclude special activities or applications by individual Centers

  2. 76 FR 52678 - Request for Qualification (RFQ) for the Fellowship Placement Pilot Program

    Science.gov (United States)

    2011-08-23

    .... Background In 2010, senior leadership from the White House, HUD, and other federal agencies have assessed... mentoring opportunities fellows may require as they progress through the program; and Tracking and.... HUD recognizes that mentoring fellows will be critical to the success of [[Page 52684

  3. Kennedy Space Center: Constellation Program Electrical Ground Support Equipment Research and Development

    Science.gov (United States)

    McCoy, Keegan

    2010-01-01

    The Kennedy Space Center (KSC) is NASA's spaceport, launching rockets into space and leading important human spaceflight research. This spring semester, I worked at KSC on Constellation Program electrical ground support equipment through NASA's Undergraduate Student Research Program (USRP). This report includes a discussion of NASA, KSC, and my individual research project. An analysis of Penn State's preparation of me for an internship and my overall impressions of the Penn State and NASA internship experience conclude the report.

  4. 78 FR 54197 - Energy Efficiency Program for Commercial and Industrial Equipment: Energy Conservation Standards...

    Science.gov (United States)

    2013-09-03

    .... EERE-2013-BT-STD-0030] RIN 1904-AD01 Energy Efficiency Program for Commercial and Industrial Equipment: Energy Conservation Standards for Commercial Packaged Boilers AGENCY: Office of Energy Efficiency and..., Office of Energy Efficiency and Renewable Energy, Building Technologies Office, EE-2J, 1000 Independence...

  5. 78 FR 11996 - Energy Efficiency Program for Commercial and Industrial Equipment: Commercial and Industrial Pumps

    Science.gov (United States)

    2013-02-21

    .... EERE-2011-BT-STD-0031] RIN 1904-AC54 Energy Efficiency Program for Commercial and Industrial Equipment: Commercial and Industrial Pumps AGENCY: Office of Energy Efficiency and Renewable Energy, Department of... CONTACT: Mr. Charles Llenza, U.S. Department of Energy, Office of Energy Efficiency and Renewable Energy...

  6. Users manual. Pursuit program of use licenses of radioactive material or generator equipment of ionizing radiations

    International Nuclear Information System (INIS)

    Becerril M, V.M.; Villarreal, J.E.

    1992-05-01

    The objective of the program 'Databases for the pursuit of licenses of use of radioactive material', it consists on the application of a computer system carried out in dbase IV that it allows the control of the all the information related with those licenses for use, possession and storage of radioactive material or generator equipment of ionizing radiations. (Author)

  7. Seismic and dynamic qualification methods

    International Nuclear Information System (INIS)

    Lin, C.W.

    1985-01-01

    This book presents the papers given at a conference on seismic effects on nuclear power plants. Topics considered at the conference included seismic qualification of equipment, multifrequency test methodologies, damping in piping systems, the amplification factor, thermal insulation, welded joints, and response factors for seismic risk analysis of piping

  8. The VALMONT Program: Accurate experimental techniques to support the neutronics qualification of UMo/AL

    International Nuclear Information System (INIS)

    Hedelot, J.P.; Doederlein, C.; Antony, M.; Girard, J.M.; Laval, V.; Fougeras, P.; Willermoz, G.; Leconte, P.

    2005-01-01

    The VALMONT program aimed at qualifying the HORUS3D (HOrowitz Reactor simulation Unified System) neutronics calculation route that is used for the development of the JHR core, and to verify the correct treatment of UMo/Al (20% enrichment in 235 U) fuel. The program is composed of two parts. The first part was devoted to the measurement by the oscillation technique of the reactivity effect of UAl/Mo fuel with an accuracy around 1% (1□). The second part consisted of gamma-spectroscopy experiments on a dedicated UMo/Al fuel sample in order to characterize, through axial power profiles and modified conversion ratio of 238 U measurements, the production and absorption effects inside the UAl/Mo fuel. The overall excellent agreement between high accuracy experiments and calculations allowed to qualify the HORUS3D neutronics calculation route for UMo/Al fuel. (author)

  9. Promoting high efficiency residential HVAC equipment: Lessons learned from leading utility programs

    Energy Technology Data Exchange (ETDEWEB)

    Neme, C.; Peters, J.; Rouleau, D.

    1998-07-01

    The Consortium for Energy Efficiency recently sponsored a study of leading electric utility efforts to promote high efficiency residential HVAC equipment. Given growing concerns from some utilities about the level of expenditures associated with rebate programs, special emphasis was placed on assessing the success of financing and other non-rebate options for promoting efficiency. Emphasis was also placed on review of efforts--rebate or otherwise--to push the market to very high levels of efficiency (i.e., SEER 13). This paper presents the results of the study. It includes discussion of key lessons from the utility programs analyzed. It also examines program participation rates and other potential indicators of market impacts. One notable conclusion is that several utility programs have pushed market shares for SEER 12 equipment to about 50% (the national average is less than 20%). At least one utility program has achieved a 50% market share for SEER 13 equipment (the national average is less than 3%). In general, financing does not appear to have as broad an appeal as consumer rebates. However, one unique utility program which combines the other of customer financing with modest incentives to contractors--in the form of frequent seller points that can be redeemed for advertising, technician training, travel and other merchandise--offers some promise that high participation rates can be achieved without customer rebates.

  10. A study on the implementation of an integrated Environmental Qualification Management System(EQMS) for nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Bhang, Keug Jin; Jeong, Sun Chul; Kang, Pil Sun [KHNP CRI, Daejeon (Korea, Republic of)

    2012-10-15

    Environmental Qualification Management System(EQMS) for Nuclear Power Plant is a web based program for preventing degradation and managing original functions of environmental qualification equipment during nuclear power plant life cycle by inspecting and improving status of them periodically. But cognitive issues have stayed in the construction phase of EQMS: almost EQ equipment are not registered in DREAMS because the approach is not based on a standard data structure. In this study, we are to obtain the requirements of integrated EQMS by considering a standard and surveying the problems of current EQMS.

  11. A study on the implementation of an integrated Environmental Qualification Management System(EQMS) for nuclear power plant

    International Nuclear Information System (INIS)

    Bhang, Keug Jin; Jeong, Sun Chul; Kang, Pil Sun

    2012-01-01

    Environmental Qualification Management System(EQMS) for Nuclear Power Plant is a web based program for preventing degradation and managing original functions of environmental qualification equipment during nuclear power plant life cycle by inspecting and improving status of them periodically. But cognitive issues have stayed in the construction phase of EQMS: almost EQ equipment are not registered in DREAMS because the approach is not based on a standard data structure. In this study, we are to obtain the requirements of integrated EQMS by considering a standard and surveying the problems of current EQMS

  12. The OSMOSE Experimental Program for the qualification of integral cross sections of actinides

    Energy Technology Data Exchange (ETDEWEB)

    Antony, Muriel; Hudelot, Jean-Pascal [CEA, Centre de Cadarache, F-13108 Saint Paul lez Durance (France); Klann, Raymond [Nuclear Engineering Division, Argonne. National Laboratory, 9700 South Cass Ave., Argonne, IL 60439-4814 (United States)

    2006-07-01

    The need of better nuclear data on minor actinides has been stressed by various organizations throughout the world. It especially deals with the studies on plutonium management and waste incineration in existing systems and transmutation of waste or Pu burning in future nuclear concepts. To address this issue, a Working Party of the OECD has been concerned with identifying these needs and has produced a detailed High Priority Request List for Nuclear Data. The first step in obtaining better nuclear data consists in measuring accurate integral data and comparing them to integrated energy dependent data: this comparison provides a direct assessment of the effect of deficiencies in the differential data. Several international programs have indicated a strong desire to obtain accurate integral reaction rate data for improving the major and minor actinides cross sections. Data on major actinides (i.e. {sup 235}U, {sup 236}U, {sup 238}U, {sup 239}Pu, {sup 240}Pu, {sup 241}Pu, {sup 242}Pu and {sup 241}Am) are reasonably well-known and available in the Evaluated Nuclear Data Files (JEFF, JENDL, ENDF-B). However information on the minor actinides (i.e. {sup 232}Th, {sup 233}U, {sup 237}Np, {sup 238}Pu, {sup 242}Am, {sup 243}Am, {sup 242}Cm, {sup 243}Cm, {sup 244}Cm, {sup 245}Cm, {sup 246}Cm and {sup 247}Cm) is less well-known and considered to be relatively poor in some cases, having to rely on model and extrapolation of few data points. In this framework, the ambitious OSMOSE program between the Commissariat a l'Energie Atomique (CEA), Electricite de France (EDF) and the U.S. Department of Energy (DOE) has been undertaken with the aim of measuring the integral absorption rate parameters of actinides in the MINERVE experimental facility located at the CEA Cadarache Research Center. The OSMOSE Program (Oscillation in Minerve of isOtopes in 'Eupraxic' Spectra) includes a complete analytical program associated with the experimental measurement program and aims

  13. [The Articulator of Primary Health Care Program: an innovative proposal for qualification of Primary Health Care].

    Science.gov (United States)

    Doricci, Giovanna Cabral; Guanaes-Lorenzi, Carla; Pereira, Maria José Bistafa

    2017-06-01

    In 2009, the Secretary of State for Health of Sao Paulo created a Program with a view to qualify the primary care in the state. This proposal includes a new job function, namely the articulator of primary care. Due to the scarcity of information about the practice of these new professionals in the scientific literature, this article seeks to analyze how articulators interpret their function and how they describe their daily routines. Thirteen articulators were interviewed. The interviews were duly analyzed by qualitative delineation. The results describe three themes: 1)Roles of the articulator: technical communicator and political advisor; 2) Activities performed to comply with the expected roles, examples being diagnosis of the municipalities, negotiation of proposals, participation in meetings, visits to municipalities; and 3) Challenges of the role, which are configured as challenges to the health reform process, examples being the lack of physical and human resources, activities of professionals in the medical-centered model, among others. The conclusion drawn is that the Program has great potential to provide input for the development and enhancement of Primary Care. Nevertheless, there are a series of challenges to be overcome, namely challenges to the context per se.

  14. WTP Waste Feed Qualification: Glass Fabrication Unit Operation Testing Report

    Energy Technology Data Exchange (ETDEWEB)

    Stone, M. E. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL). Hanford Missions Programs; Newell, J. D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL). Process Technology Programs; Johnson, F. C. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL). Engineering Process Development; Edwards, T. B. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL). Engineering Process Development

    2016-07-14

    The waste feed qualification program is being developed to protect the Hanford Tank Waste Treatment and Immobilization Plant (WTP) design, safety basis, and technical basis by assuring waste acceptance requirements are met for each staged waste feed campaign prior to transfer from the Tank Operations Contractor to the feed receipt vessels inside the Pretreatment Facility. The Waste Feed Qualification Program Plan describes the three components of waste feed qualification: 1. Demonstrate compliance with the waste acceptance criteria 2. Determine waste processability 3. Test unit operations at laboratory scale. The glass fabrication unit operation is the final step in the process demonstration portion of the waste feed qualification process. This unit operation generally consists of combining each of the waste feed streams (high-level waste (HLW) and low-activity waste (LAW)) with Glass Forming Chemicals (GFCs), fabricating glass coupons, performing chemical composition analysis before and after glass fabrication, measuring hydrogen generation rate either before or after glass former addition, measuring rheological properties before and after glass former addition, and visual observation of the resulting glass coupons. Critical aspects of this unit operation are mixing and sampling of the waste and melter feeds to ensure representative samples are obtained as well as ensuring the fabrication process for the glass coupon is adequate. Testing was performed using a range of simulants (LAW and HLW simulants), and these simulants were mixed with high and low bounding amounts of GFCs to evaluate the mixing, sampling, and glass preparation steps in shielded cells using laboratory techniques. The tests were performed with off-the-shelf equipment at the Savannah River National Laboratory (SRNL) that is similar to equipment used in the SRNL work during qualification of waste feed for the Defense Waste Processing Facility (DWPF) and other waste treatment facilities at the

  15. Commercial equipment loads: End-Use Load and Consumer Assessment Program (ELCAP)

    Energy Technology Data Exchange (ETDEWEB)

    Pratt, R.G.; Williamson, M.A.; Richman, E.E.; Miller, N.E.

    1990-07-01

    The Office of Energy Resources of the Bonneville Power Administration is generally responsible for the agency's power and conservation resource planning. As associated responsibility which supports a variety of office functions is the analysis of historical trends in and determinants of energy consumption. The Office of Energy Resources' End-Use Research Section operates a comprehensive data collection program to provide pertinent information to support demand-side planning, load forecasting, and demand-side program development and delivery. Part of this on-going program is known as the End-Use Load and Consumer Assessment Program (ELCAP), an effort designed to collect electricity usage data through direct monitoring of end-use loads in buildings. This program is conducted for Bonneville by the Pacific Northwest Laboratory. This report provides detailed information on electricity consumption of miscellaneous equipment from the commercial portion of ELCAP. Miscellaneous equipment includes all commercial end-uses except heating, ventilating, air conditioning, and central lighting systems. Some examples of end-uses covered in this report are office equipment, computers, task lighting, refrigeration, and food preparation. Electricity consumption estimates, in kilowatt-hours per square food per year, are provided for each end-use by building type. The following types of buildings are covered: office, retail, restaurant, grocery, warehouse, school, university, and hotel/motel. 6 refs., 35 figs., 12 tabs.

  16. Present situation and necessity of computer programmed X-ray equipment

    International Nuclear Information System (INIS)

    Shiraishi, Junji; Hatagawa, Masakatsu

    1989-01-01

    In order to take radiographic photos, it is necessary to know a great deal of information. For example, mA, kV, exposure time, screen, grid, phototimer, etc. In this study, we examined 4 widely-used types computer-programmed X-ray equipment. These computer-assisted processes are designed to look at the data and make programmed individual decisions. The purpose is to reduce the differences in radiographic quality and the risk of retaking caused by the differences in experience among technicians. We concluded that none of them has ideal functions but each can be used as a source supply information, if a little remodeling is done, and we confirm that computer-programmed X-ray equipment is, and will continue to go be, necessary. (author)

  17. Refurbishment programs

    International Nuclear Information System (INIS)

    Irish, C.S.

    2004-01-01

    As nuclear plants age, equipment becomes obsolete, outdated or just simply unreliable. This puts a lot of emphasis on replacement of the subject equipment. This can be an expensive proposition for safety related equipment due to design changes, requalification charges and the cost of the new equipment, specifically when the original component is obsolete. The presentation will explain how comprehensive refurbishment programs on many different types of equipment can alleviate this situation. The refurbishment program is a systematic refurbishment of equipment to an as new condition by replacing all of the age sensitive components within the equipment. This is carried out on all of the same type of equipment in a scheduled program. For example the plant may to decide to refurbish all of their Lambda LME-24 power supplies, or all of their Bailey modules, or all of their Agastat DSC Series relays. Independent of the item the process is the same. Refurbish each piece of equipment to an as new condition by replacing all of the age sensitive equipment. The equipment is then returned to the client as safety related, existing qualification maintained and with a new service life/warranty. This is not a simple repair. It is a planned refurbishment to an as new condition of certain equipment types throughout the plant and then carried out from equipment piece to equipment piece. The refurbishment program may even include introducing new spares into the plant. This is normally performed by upgrading (dedicating for safety related use and refurbishing to an 'as new' condition) surplus equipment and using these equipment pieces in the rotation of the plant equipment to refurbish the entire population of a selected piece of equipment at the plant. This process can be performed on many equipment types including power supplies, circuit boards, modules, relays, motors, breakers, and many more. The refurbishment program greatly increases the reliability of the equipment without the

  18. A Global Review of Incentive Programs to Accelerate Energy-Efficient Appliances and Equipment

    Energy Technology Data Exchange (ETDEWEB)

    de la Rue du Can, Stephane; Phadke, Amol; Leventis, Greg; Gopal, Anand

    2013-08-01

    Incentive programs are an essential policy tool to move the market toward energy-efficient products. They offer a favorable complement to mandatory standards and labeling policies by accelerating the market penetration of energy-efficient products above equipment standard requirements and by preparing the market for increased future mandatory requirements. They sway purchase decisions and in some cases production decisions and retail stocking decisions toward energy-efficient products. Incentive programs are structured according to their regulatory environment, the way they are financed, by how the incentive is targeted, and by who administers them. This report categorizes the main elements of incentive programs, using case studies from the Major Economies Forum to illustrate their characteristics. To inform future policy and program design, it seeks to recognize design advantages and disadvantages through a qualitative overview of the variety of programs in use around the globe. Examples range from rebate programs administered by utilities under an Energy-Efficiency Resource Standards (EERS) regulatory framework (California, USA) to the distribution of Eco-Points that reward customers for buying efficient appliances under a government recovery program (Japan). We found that evaluations have demonstrated that financial incentives programs have greater impact when they target highly efficient technologies that have a small market share. We also found that the benefits and drawbacks of different program design aspects depend on the market barriers addressed, the target equipment, and the local market context and that no program design surpasses the others. The key to successful program design and implementation is a thorough understanding of the market and effective identification of the most important local factors hindering the penetration of energy-efficient technologies.

  19. Radiation hardness and qualification of semiconductor electronic devices for nuclear reactors

    International Nuclear Information System (INIS)

    Friant, A.; Payat, R.

    1984-05-01

    After a brief review of radiation effects in semiconductors and radiation damage in semiconductor devices, the problems of qualification of electronic equipment to be used in nuclear reactors are compared to those relative to nuclear weapons or space experiments. The conclusion is that data obtained at very high dose rates or under pulsed irradiation in weapons and space programs should not be directly applied to nuclear plant instrumentation. The need for a specific qualification of semiconductor devices appropriate for nuclear reactors is emphasized. Some irradiation studies at IRDI/DEIN (CEN-Saclay) are related [fr

  20. Comparison of Training Qualifications Programs, for Operating Boats and Yachts, which are not Covered by STCW Convention in the United Kingdom and the Republic of Croatia

    Directory of Open Access Journals (Sweden)

    Darijo Mišković

    2017-03-01

    Full Text Available Research in this paper was conducted under the EU project TRECVET Core Curriculum for Skippers of Small Commercial Vessels (in short TCC-SCV where a Faculty of Maritime Studies Rijeka was a project partner. The goal of the project was to analyze seven professional SCV skipper qualifications from UK, France, Spain, Germany, Slovenia, Czech Republic and Croatia by breaking them into their smallest parts called Fundamental Elements and thereby offering objective comparability. After reviewing and comparing training programs in The United Kingdom and The Republic of Croatia for qualifications, required for operating boats and yachts, set by the appropriate Authorities, this paper analyzed skipper/yacht master certification scheme in terms of theoretical education and practical trainings, syllabus contents, required experience, examination methods and evaluated the overall characteristics. At the end, the authors pointed out to some deficiencies in current training program in The Republic of Croatia and drew the conclusion that experience and lessons from other training programs can find purpose for training program reform in their own country.

  1. The Bosnian Train and Equip Program: A Lesson in Interagency Integration of Hard and Soft Power

    Science.gov (United States)

    2014-03-01

    even before Bos- nia officially declared independence. Most of the weaponry and commanders from the former Yugoslav People’s Army in Bosnia, which was...ability, and disposition.” 505 It covers characteristics that research indicates affect team performance including attitudinal, de- mographic, and...The Train and Equip Program reduced foreign influence in the Federation, which helped remove impediments to reconciliation and integration in Bos- nia

  2. The qualification of electrical components and instrumentations relevant to safety

    International Nuclear Information System (INIS)

    Zambardi, F.

    1989-03-01

    Systems and components relevant to safety of nuclear power plants must maintain their functional integrity in order to assure accident prevention and mitigation. Redundancy is utilized against random failures, nevertheless care must be taken to avoid common failures in redundant components. Main sources of degradation and common cause failures consist in the aging effects and in the changes of environmental conditions which occur during the plant life and the postulated accidents. These causes of degradation are expected to be especially significant for instrumentation and electrical equipment, which can have a primary role in safety systems. The qualification is the methodology by which component safety requirements can be met against the above mentioned causes of degradation. In this report the connection between the possible, plant conditions and the resulting degradation effects on components is preliminarily addressed. A general characterization of the qualification is then presented. Basis, methods and peculiar aspects are discussed and the qualification by testing is taken into special account. Technical and organizational aspects related to a plant qualification program are also focused. The report ends with a look to the most significant research and development activities. (author)

  3. The current status of education and career paths of students after completion of medical physicist programs in Japan: a survey by the Japanese Board for Medical Physicist Qualification.

    Science.gov (United States)

    Kadoya, Noriyuki; Karasawa, Kumiko; Sumida, Iori; Arimura, Hidetaka; Yamada, Syogo

    2015-07-01

    To standardize educational programs and clinical training for medical physics students, the Japanese Board for Medical Physicist Qualification (JBMP) began to accredit master's, doctorate, and residency programs for medical physicists in 2012. At present, 16 universities accredited by the JBMP offer 22 courses. In this study, we aimed to survey the current status of educational programs and career paths of students after completion of the medical physicist program in Japan. A questionnaire was sent in August 2014 to 32 universities offering medical physicist programs. The questionnaire was created and organized by the educational course certification committee of the JBMP and comprised two sections: the first collected information about the university attended, and the second collected information about characteristics and career paths of students after completion of medical physicist programs from 2008 to 2014. Thirty universities (16 accredited and 14 non-accredited) completed the survey (response rate 94 %). A total of 209, 40, and 3 students graduated from the master's, doctorate, and residency programs, respectively. Undergraduates entered the medical physicist program constantly, indicating an interest in medical physics among undergraduates. A large percentage of the students held a bachelor's degree in radiological technology (master's program 94 %; doctorate program 70 %); graduates obtained a national radiological technologist license. Regarding career paths, although the number of the graduates who work as medical physicist remains low, 7 % with a master's degree and 50 % with a doctorate degree worked as medical physicists. Our results could be helpful for improving the medical physicist program in Japan.

  4. Quality Control Program for radiodiagnostic equipment on the Department of Antioquia, Colombia

    International Nuclear Information System (INIS)

    Beltran, Camilo; Viloria, Carolina; Puerta, Anselmo; Morales, Javier; Martinez, Piedad

    2008-01-01

    The Health Sectional Direction of Antioquia DSSA and the National University of Colombia campus Medellin have been formalizing inter-administrative agreements to realize Quality Control Studies on the institutions of medical radiodiagnostics of the department. In the first phase of the project on 2006, quality control studies were completed on 40 conventional and 31 mammography equipment, in the second phase by the end of 2006, 21 fluoroscopy, interventionism and C arms equipment were also studied; the third phase, finished by the end of 2007, counted with 50 conventional equipment. The tests proposed on the ARCAL XLIX IAEA protocol, tests on the installations, on the generator, on the image systems and the patient dosimetry were performed. From the evaluations on the installations, reports with relevant recommendations to be considerate and implemented to perform a better use of own resources on each institution were elaborated. On this paper, current results, impact on the participating institutions and the benefits from the applications that these kinds of practices bring to the institutions are presented. Finally, the necessity to advance towards clear politics in order to impulse the implementation of quality assurance programs in radiodiagnostic institutions, looking to improve the quality of diagnostic images with patient benefits, higher trust on technical conditions of equipment for a better and adequate diagnose, as well as to advance on processes seeking the optimization of radiological protection on the patient and the personnel occupationally exposed, is presented. (author)

  5. Pilot study approach and qualification dossier components

    International Nuclear Information System (INIS)

    Ammirato, F.; Ashwin, P.

    2000-01-01

    The aim of the Pilot Project is to evaluate the IAEA Guidelines and methodology for the benefit of IAEA Member States trough a simulation of qualification activities. The Project is based on a real component and available data - NPP Kozloduy unit 5, weld 3. The initial phase is limited to the Qualification dossier. The Project relies on the input from the team members and Member States. Team organization and responsibilities are presented. The components of the Qualification Dossier (technical specification, inspection procedure and preliminary review, qualification procedure) and their current status are also presented. A comparison is done with their qualification programs. The characteristics of performance demonstrations are discussed. The results show that the teamwork has been successful and the IAEA methodology covers all situations. It is expected that the End Project will become 'Benchmark's' for future qualification activities

  6. Evaluation of training programs and entry-level qualifications for nuclear-power-plant control-room personnel based on the systems approach to training

    International Nuclear Information System (INIS)

    Haas, P.M.; Selby, D.L.; Hanley, M.J.; Mercer, R.T.

    1983-09-01

    This report summarizes results of research sponsored by the US Nuclear Regulatory Commission (NRC) Office of Nuclear Regulatory Research to initiate the use of the Systems Approach to Training in the evaluation of training programs and entry level qualifications for nuclear power plant (NPP) personnel. Variables (performance shaping factors) of potential importance to personnel selection and training are identified, and research to more rigorously define an operationally useful taxonomy of those variables is recommended. A high-level model of the Systems Approach to Training for use in the nuclear industry, which could serve as a model for NRC evaluation of industry programs, is presented. The model is consistent with current publically stated NRC policy, with the approach being followed by the Institute for Nuclear Power Operations, and with current training technology. Checklists to be used by NRC evaluators to assess training programs for NPP control-room personnel are proposed which are based on this model

  7. Evaluation of training programs and entry-level qualifications for nuclear-power-plant control-room personnel based on the systems approach to training

    Energy Technology Data Exchange (ETDEWEB)

    Haas, P M; Selby, D L; Hanley, M J; Mercer, R T

    1983-09-01

    This report summarizes results of research sponsored by the US Nuclear Regulatory Commission (NRC) Office of Nuclear Regulatory Research to initiate the use of the Systems Approach to Training in the evaluation of training programs and entry level qualifications for nuclear power plant (NPP) personnel. Variables (performance shaping factors) of potential importance to personnel selection and training are identified, and research to more rigorously define an operationally useful taxonomy of those variables is recommended. A high-level model of the Systems Approach to Training for use in the nuclear industry, which could serve as a model for NRC evaluation of industry programs, is presented. The model is consistent with current publically stated NRC policy, with the approach being followed by the Institute for Nuclear Power Operations, and with current training technology. Checklists to be used by NRC evaluators to assess training programs for NPP control-room personnel are proposed which are based on this model.

  8. Intelligent Processing Equipment Research and Development Programs of the Department of Commerce

    Science.gov (United States)

    Simpson, J. A.

    1992-01-01

    The intelligence processing equipment (IPE) research and development (R&D) programs of the Department of Commerce are carried out within the National Institute of Standards and Technology (NIST). This institute has had work in support of industrial productivity as part of its mission since its founding in 1901. With the advent of factory automation these efforts have increasingly turned to R&D in IPE. The Manufacturing Engineering Laboratory (MEL) of NIST devotes a major fraction of its efforts to this end while other elements within the organization, notably the Material Science and Engineering Laboratory, have smaller but significant programs. An inventory of all such programs at NIST and a representative selection of projects that at least demonstrate the scope of the efforts are presented.

  9. THE PROGRAM-TARGET PLANNING AND MANAGEMENT OF DEVELOPMENT OF MEASURING EQUIPMENT PARK

    Directory of Open Access Journals (Sweden)

    Marichev Pavel Aleksandrovich

    2018-02-01

    Full Text Available Subject: study of the Park of Measuring Equipment (PME that includes hundreds of thousands of standard samples, measuring instruments, control and measuring devices and other measuring mechanisms with different areas of application, levels of reliability, service life, levels of technical perfection and levels of technical condition. Research objectives: 1. Development of a complex of mathematical models to simulate the processes of development of PME, control indicators of PME performance as a whole, purposefully control the stages of life cycle of measuring equipment samples. 2. Development of the method which, with a sufficient degree of validity and objectivity, would solve the tasks of management of procurement and repairs both in preparation of proposals for preliminary long-term plan documents (LTPD and to ensure control over the implementation of adopted plans. Thus, the method being developed should be fairly simple to use, easily adjustable for solving problems of different dimensions, suitable for solving the optimal control problem for PME as a whole, for a part of PME, and also suitable for solving a generalized problem for certain “aggregated objects” such as the Metrology Centers. Materials and methods: the methods of mathematical simulation, methods of comparative analysis, simplex method for solving linear programming problem, methods of program-target planning were used. Results: an approach to the solution of problems of program-target planning based on solving a series of linear programming problems has been developed. The results have been presented of using the approach both for formulation of proposals into the preliminary LTPD and also for introducing revisions (amendments to annual plans, which are implemented in the framework of the state defense order. Conclusions: the described method and algorithms constitute an effective tool for solving practical problems of target-oriented management of PME performance

  10. Training for the seismic qualification utility group (SQUG) generic implementation procedure (GIP) for verification of seismic effects on nuclear power plant equipment

    International Nuclear Information System (INIS)

    Schaffstall, R.E.; Smith, N.P.; Baker, K.M.

    1993-01-01

    Resolution of USI A-46 was accomplished May, 1992 with the issuance of the SER for the GIP, Revision 2. The implementation of the resolution for the SQUG plants will be completed by 1996. Both the USNRC and the SQUG utilities have expended considerable resources to effect a common understanding that the effort has been worth the price. The Training Program developed to ensure that the efforts expended by the SQUG was indeed worth the price will be a major contributor in the success of the implementation. All of the older nuclear power plants in the United States now have an alternative standard to determine seismic resistance using experience data- a standard against which they can be evaluated and found seismically adequate to achieve and maintain a safe and reliable shutdown when subjected to strong motion earthquakes

  11. On ISI effectiveness through inspection qualification

    International Nuclear Information System (INIS)

    Harutyunov, R.

    2000-01-01

    There are two units of WWER type in the ANPP. The results of the implementation of the IAEA qualification guidelines for the ANPP Primary Circuit for WWER are presented. The control methods according to the ISI Program are foreseen in the design and implemented during the preparation for the unit 2 restart. The result of control is plugging of more tubes than during the last operation period. During the next years in the presence of the blowdown water activity, the search on defective tubes was performed by Lumhydraulic methods and the tubes were plugged by welding plugs. In 1999 was performed the visual control on the Steam Generator 6 by WNIAES experts and by the ANPP experts from the Metal Laboratory. The result is confirmation of the irreversible process on erosive-corrosion destruction of feed waters distribution header; definition of the defects coordinates defined; detection of sediments within the SG vessel surfaces and in the head exchanged surface tubes. The purpose of the ISI effectiveness improvement is to discover the defects in the base metal and in the welds before developing into a problem at operating level or a safety problem. For the solution on the specific problems at the ANPP the project for technological co-operation with IAEA has been developed. It is necessary to organize training, certification, assessment methodology. The expected results after the project implementation are to establish the base for the equipment qualification body and staff certification; to upgrade the ANPP staff qualification; to prepare a group of experts, supported by ANRA, which to be also involved in the development of NDM national regulators

  12. MGR COMPLIANCE PROGRAM GUIDANCE PACKAGE FOR RADIATION PROTECTION EQUIPMENT, INSTRUMENTATION, AND FACILITIES

    International Nuclear Information System (INIS)

    2000-01-01

    This Compliance Program Guidance Package identifies the regulatory guidance and industry codes and standards addressing radiation protection equipment, instrumentation, and support facilities considered to be appropriate for radiation protection at the Monitored Geologic Repository (MGR). Included are considerations relevant to radiation monitoring instruments, calibration, contamination control and decontamination, respiratory protection equipment, and general radiation protection facilities. The scope of this Guidance Package does not include design guidance relevant to criticality monitoring, area radiation monitoring, effluent monitoring, and airborne radioactivity monitoring systems since they are considered to be the topics of specific design and construction requirements (i.e., ''fixed'' or ''built-in'' systems). This Guidance Package does not address radiation protection design issues; it addresses the selection and calibration of radiation monitoring instrumentation to the extent that the guidance is relevant to the operational radiation protection program. Radon and radon progeny monitoring instrumentation is not included in the Guidance Package since such naturally occurring radioactive materials do not fall within the NRC's jurisdiction at the MGR

  13. Evaluation of the Nuclear Medicine facilities in Minas Gerais state: quality control program of equipment

    International Nuclear Information System (INIS)

    Kubo, Tadeu Takao Almodovar; Biancardi, Rodrigo; Rocha, Adriana Marcia Guimaraes; Ferreira, Denia Romao; Silva, Franciele Aquiles Anjos; Assuncao, Jonathan Buenos Aires; Alves, Ederson Henrique; Almeida, Ana Flavia Batista; Alves, Nathalia Fernandes; Xavier, Faber Henrique Zacarias; Gontijo, Rodrigo Modesto Gadelha; Mamede, Marcelo; Universidade Federal de Minas Gerais

    2017-01-01

    With the reformulation of the CNEN-NN-3.05 standard in December 2013, Brazil's Nuclear Medicine (NMS) services have to perform a greater number of quality controls for SPECT and PET equipment. However, little is known about the reality of the quality control programs of these services regarding the application of the new standard. Thus, in this context, the objective of the present study was to evaluate the quality control program of MNSs in the state of Minas Gerais. All NMSs in the state of Minas Gerais were invited to participate in the project. Of these, 34.48% (20 facilities) agreed to participate in the project, 50.00% (29 facilities) did not respond to the invitation and 15.52%(9 facilities) declined their participation. Thus, as of November 2015, 20 SPECT and 2 PET/CT equipment were evaluated for the performance of the quality control tests recommended by the new CNEN standard. The phantoms required for the evaluation came from the Laboratory of Dosimetry and Quality Control of UFMG. Even with the deadlines set by CNEN for the implementation of the quality control program in the NMSs, more than 50% of the evaluated services did not implement the quality controls, and the absence of specific phantoms is the main reason for the failure. Among the problems found in the installations, the most critical were: collimators with no conditions of use in the clinical routine, linearity problems of the evaluated image and values of image uniformity superior to the limits of acceptance. Problems in the uniformity and linearity of the image found directly impacted the performance of other tests, such as spatial resolution, SPECT performance, among others. In a general way, the NMSs in the state of Minas Gerais evaluated with the present study are in clinical feasible conditions. (author)

  14. Qualification of organizations for independent technical supervision

    International Nuclear Information System (INIS)

    1981-04-01

    The requirements are established on trial for the qualification of an organization as an independent technical supervision organization in nuclear facilities, in activities related with quality assurance programs. (I.C.R.) [pt

  15. Solar array qualification through qualified analysis

    Science.gov (United States)

    Zijdemans, J.; Cruijssen, H. J.; Wijker, J. J.

    1991-04-01

    To achieve qualification is in general a very expensive exercise. For solar arrays this is done by a dedicated test program through which final qualification is achieved. Due to severe competition on the solar array market, cheaper means are looked for to achieve a qualified product for the customers. One of the methods is to drastically limit the environmental test program and to qualify the solar-array structure against its environmental loads by analysis. Qualification by analysis is possible. The benefits are that a significant amount of development effort can be saved in case such a powerful tool is available. Extensive testing can be avoided thus saving time and money.

  16. Policies and practices pertaining to the selection, qualification requirements, and training programs for nuclear-reactor operating personnel at the Oak Ridge National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Culbert, W.H.

    1985-10-01

    This document describes the policies and practices of the Oak Ridge National Laboratory (ORNL) regarding the selection of and training requirements for reactor operating personnel at the Laboratory's nuclear-reactor facilities. The training programs, both for initial certification and for requalification, are described and provide the guidelines for ensuring that ORNL's research reactors are operated in a safe and reliable manner by qualified personnel. This document gives an overview of the reactor facilities and addresses the various qualifications, training, testing, and requalification requirements stipulated in DOE Order 5480.1A, Chapter VI (Safety of DOE-Owned Reactors); it is intended to be in compliance with this DOE Order, as applicable to ORNL facilities. Included also are examples of the documentation maintained amenable for audit.

  17. Policies and practices pertaining to the selection, qualification requirements, and training programs for nuclear-reactor operating personnel at the Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Culbert, W.H.

    1985-10-01

    This document describes the policies and practices of the Oak Ridge National Laboratory (ORNL) regarding the selection of and training requirements for reactor operating personnel at the Laboratory's nuclear-reactor facilities. The training programs, both for initial certification and for requalification, are described and provide the guidelines for ensuring that ORNL's research reactors are operated in a safe and reliable manner by qualified personnel. This document gives an overview of the reactor facilities and addresses the various qualifications, training, testing, and requalification requirements stipulated in DOE Order 5480.1A, Chapter VI (Safety of DOE-Owned Reactors); it is intended to be in compliance with this DOE Order, as applicable to ORNL facilities. Included also are examples of the documentation maintained amenable for audit

  18. 78 FR 79423 - Energy Efficiency Program for Industrial Equipment: Petition of CSA Group for Classification as a...

    Science.gov (United States)

    2013-12-30

    ... DEPARTMENT OF ENERGY Office of Energy Efficiency and Renewable Energy [Docket No. EERE-2013-BT-DET-0053] Energy Efficiency Program for Industrial Equipment: Petition of CSA Group for Classification as a Nationally Recognized Certification Program for Small Electric Motors AGENCY: Office of Energy Efficiency and...

  19. Mississippi Curriculum Framework for Diesel Equipment Technology (CIP: 47.0605--Diesel Engine Mechanic & Repairer). Postsecondary Programs.

    Science.gov (United States)

    Mississippi Research and Curriculum Unit for Vocational and Technical Education, State College.

    This document, which is intended for use by community and junior colleges throughout Mississippi, contains curriculum frameworks for the course sequences in the diesel equipment technology programs cluster. Presented in the introductory section are a description of the program and suggested course sequence. Section I lists baseline competencies,…

  20. Pilot program of quality control in mammography and conventional equipment in the Antioquia Department

    International Nuclear Information System (INIS)

    Martinez, P.; Puerta, J.A.; Morales, J.; Beltran, C.C.

    2006-01-01

    The Sectional Health Division of Antioquia and the National University of Colombia- Medellin Headquarters formalized an agreement for the realization of the quality control of thirty mammographs and twenty-five conventional X-ray equipment located in the one metropolitan area of Medellin, and ten municipalities of the nine regions in that the antioquen county is divided. The National University of Colombia- Headquarters Medellin possesses a program for the formation in quality control and radiological protection at master level in physics for that which endowed a radiodiagnostic laboratory for these purposes. In the Antioquia department only exists an institution, the San Vicente of Paul University Hospital that possesses a quality control program in radiodiagnostic; this hospital given its great volume of studies in radiodiagnostic has a medical physicist and of that instrumental necessary to maintain the program. The quality control programs have not been implemented in the rest of health institutions, public or private, big or small, until the moment. The project then allowed to carry out an initial evaluation of the pertinent parameters of the quality control of the facilities like its are those that refer to the state of the x-ray generator, the disposition of the installation, the dark room, the film processor and negatoscopies room; these its were carried out with base in the protocol produced in the ARCAL XLIX project in which participated six Latin American countries. The dose average in mammography, following the proposed course in the ARCAL LXXV, where its participate eleven Latin American countries was also evaluated. This study pilot serves like reference of the current state of the regional radiodiagnostic services, with base in this sampling that is representative. The obtained data gave the necessary information so that the Sectional Division of Health of Antioquia can generate tending actions to the implementation of quality guarantee programs and

  1. Development Of A Macro-Batch Qualification Strategy For The Hanford Tank Waste Treatment And Immobilization Plant

    International Nuclear Information System (INIS)

    Herman, Connie C.

    2013-01-01

    following: Collection and characterization of samples for relevant process analytes from the tanks to be blended during the staging process; Initiation of qualification activities earlier in the staging process to optimize the campaign composition through evaluation from both a processing and glass composition perspective; Definition of the parameters that are important for processing in the WTP facilities (unit operations) across the anticipated range of wastes and as they relate to qualification-scale equipment; Performance of limited testing with simulants ahead of the waste feed qualification sample demonstration as needed to determine the available processing window for that campaign; and Demonstration of sufficient mixing in the staging tank to show that the waste qualification sample chemical and physical properties are representative of the transfers to be made to WTP. Potential flowcharts for derivatives of the Hanford waste feed qualification process are also provided in this report. While these recommendations are an extension of the existing WTP waste qualification program, they are more in line with the processes currently performed for SRS. The implementation of these processes at SRS has been shown to offer flexibility for processing, having identified potential processing issues ahead of the qualification or facility processing, and having provided opportunity to optimize waste loading and throughput in the DWPF

  2. Evaluation of the revised training program for senior control room staff: science fundamentals and equipment principles

    International Nuclear Information System (INIS)

    Jervis, R.E.; Evans, G.J.

    1996-10-01

    Canadian nuclear utilities have formed an Inter-Utility Working Group to revise their program for training nuclear generating station senior control room staff, namely Control Room Operators and Shift Supervisors, in Science Fundamentals and Equipment Principles. This report documents the findings of an external review of this revision process, addressing, amongst other topics, the process of revision undertaken by the Working Group, their outline of topics to be included, and, the pertinence and comprehensiveness of the detailed training objectives identified for two of the courses. The approach to revising the program being followed by the Working Group appears to be reasonable insomuch that some training needs have been identified and used to construct detailed sets of training objectives. However, as assessed by the consultants without full documentation being available, some important steps appear to have been missed. Specifically, much of the basis of the revision process has not been documented, neither has the approach selected for the revision process, nor has any justification for not performing a CANDU specific job and task analysis been offered. Furthermore, the Working Group has not yet proposed any criteria for evaluation of the program or provided any test items. As a result, the consultants have had to develop criteria for evaluation of the overall program and of individual courses. These criteria were applied in a more detailed review of the training objectives for two particular courses: Plant Chemistry, and Nuclear Physics and Reactor Theory. Many of the training objectives for these courses were found to be too qualitative or ones that require trainees to memorize blocks of information rather than develop in them an ability to arrive at conclusions about scientific phenomena using principles and reasoning. This assessment indicates that the training objectives are designed to achieve too low a level of cognition, inconsistent with developing an

  3. Laboratory services series: an electrical outlet and corded equipment inspection program

    International Nuclear Information System (INIS)

    Davis, E.A.

    1976-04-01

    A research and development laboratory has thousands of electrical outlets providing power to laboratories, offices, shops, and service areas. These outlets provide power for a wide variety of portable equipment and tools that are equipped with cord and plug. Electric safety requires a periodic check of outlet grounding capability and continuing inspection and repair of corded equipment. Personnel, equipment, reports, procedures, and schedule requirements are reported

  4. Advantages of a program of quality control in the nuclear medicine equipment

    International Nuclear Information System (INIS)

    Trujillo Z, F.E.; Argumosa, E.; Herrera R, M.R.

    2007-01-01

    In Nuclear Medicine more 90% of the entirety of the carried out procedures its are with diagnostic ends where it is acquired one or several images. This makes indispensable to have an appropriate operation of the dedicated equipment to produce images and also of those non former images, as the activity caliper, to assure an appropriate quality diagnoses not from the images and the correct dose administration to the patient. In this work the main calibrations that should be carried out and an example of the program of quality control of a gamma camera mark Siemens and model E.CAM are presented. Considerations that should take as for the radiological protection are exposed. Comments on the parameters that correct the required calibrations and the images taken place by an operation or inadequate calibrations are included. In conclusion, the necessity of a program that it contains as minimum the quality control of the gamma cameras and of the activity caliper, having as main advantages a good image quality diagnoses and to minimize the dose imparted the patient are exposed. (Author)

  5. 40 CFR 1054.625 - What requirements apply under the Transition Program for Equipment Manufacturers?

    Science.gov (United States)

    2010-07-01

    ... manufacturers to produce equipment with Class II engines that are subject to less stringent exhaust emission... equipment with Class II engines exempted under this section. You may use the exemptions in this section only... by determining your U.S.-directed production volume of equipment with Class II engines from January 1...

  6. 77 FR 76972 - Energy Conservation Program for Consumer Products and Certain Commercial and Industrial Equipment...

    Science.gov (United States)

    2012-12-31

    ... motors and pumps and certain other industrial equipment to conserve the energy resources of the nation... the efficiency of electric motors, pumps and certain other industrial equipment to conserve the energy... electric motors as covered equipment. A compressor may have some or all of the following components: piston...

  7. 45 CFR 2522.950 - What requirements and qualifications apply if my program focuses on supplemental academic support...

    Science.gov (United States)

    2010-10-01

    ... program focuses on supplemental academic support activities other than tutoring? 2522.950 Section 2522.950... support activities other than tutoring? (a) If your program does not involve tutoring as defined in § 2522... SERVICE AMERICORPS PARTICIPANTS, PROGRAMS, AND APPLICANTS Program Management Requirements for Grantees...

  8. Guidelines for training and qualification of radiological protection technicians

    International Nuclear Information System (INIS)

    1987-08-01

    These guidelines, used in combination with plant-specific job analysis, provide the framework for a training and qualification program for radiological protection technicians at nuclear power plants. Radiological protection technicians are defined as those individuals, both plant and contractor, who will be engaged in the evaluation of radiological conditions in the nuclear plant and the implementation of the necessary radiological safety measures as they apply to nuclear plant workers and members of the general public. An important aspect of this work is recognizing and handling unusual situations involving radioactivity, including incidents related to degraded core conditions. These guidelines incorporate the results of an industry-wide job analysis and task analysis (JTA) combined with industry operating experience review. However, the industry-wide analyses did not identify all important academic and fundamental knowledge and skills. Further in-depth analysis by subject matter experts produced additional knowledge and skills that were added to these guidelines. All utilities should use these guidelines in conjunction with plant-specific and industry-wide JTA results to develop or validate their radiological protection technician training program. Plant-specific information should be used to establish appropriate training program content. This plant-specific information should reflect unique job duties, equipment, operating experience, and trainee entry-level qualifications. Revisions to these guidelines should be reviewed for applicability and incorporated into the training program using each utility's training system development (TSD) procedures. Plant-specific job analysis and task analysis data is essential to the development of performance-based training programs. These analyses are particularly useful in selecting tasks for training and in developing on-the-job training (OJT), laboratory training, and mock-up training. Qualification programs based on these

  9. Evaluation of China's local enforcement of energy efficiency standards and labeling programs for appliances and equipment

    International Nuclear Information System (INIS)

    Khanna, Nina Zheng; Zhou, Nan; Fridley, David; Fino-Chen, Cecilia

    2013-01-01

    Aims: This paper aims to evaluate local enforcement of China's mandatory appliance and equipment energy efficiency standards and labeling programs, two increasingly important policies for meeting national energy and carbon reduction targets. The expected energy savings of efficiency standards and labels can be fully realized only with strong enforcement to ensure compliance for all products sold. This paper provides comprehensive retrospective evaluation of the methodologies, results, progress and remaining challenges in pilot enforcement projects initiated in the absence of consistent national check-testing focused on energy efficiency. Scope: This paper's scope is focused on 2006–2009 pilot local check-tests conducted to verify appliance and equipment compliance with China's mandatory energy label and efficiency standards. Conclusions: This paper finds both improvement and some backsliding in compliance rates over time. Compared to earlier efforts, 2009 check-tests covered a wider regional and product scope but demonstrated greater variation in compliance rates. Labeling display and energy efficiency compliance was generally high across regions and most products, but lower compliance rates were observed in less economically developed regions and for lighting and industrial products. Based on these findings, areas for improvement in local awareness, product sampling methodology, check-testing tools and procedures are identified. - Highlights: • China's mandatory standards and labeling crucial to national energy saving goals. • China's 2006–2009 pilot efficiency check-testing for standards and labeling evaluated. • Wider geographic and product scope in 2009, but greater variation in compliance. • Generally high compliance, but lower rates for less economically developed region. • Local check-test capacity improving but methodological challenges remain

  10. Periodic and in-service inspection programs

    International Nuclear Information System (INIS)

    Dinu, M.

    2000-01-01

    Periodic and in-service inspection programs for Cernavoda NPP consists of periodic inspections of CANDU NPP components CSAN N-285.4 and CSAN N-285.4, in-service inspections and repair and modifications general inspection. Periodic inspection program document (PIPD) determines the systems and components subject to inspection, the category of the inspection, techniques, areas and other details.The current status of the inspection programs is presented, including containment , erosion/corrosion, pressure vessel support and snubbers, main steam lines inspection programs. Qualification program in Cernavoda NPP involves equipment qualification in the on-site laboratory, yearly certification, special equipment qualification in the National Institute of Metrology. All procedures are approved by the ISCIR (regulatory body for pressure vessel and lifting equipment) and CNCAN (National Commission on Nuclear Activities Control). Qualification of the personnel is performed according to the ISCIR Technical prescription CR 11/82 for up to 3 year period. Final qualification and licensing is performed by CNCAN

  11. The role of a certified calibration laboratory in a station's measuring and test equipment calibration, repair, and documentation program

    International Nuclear Information System (INIS)

    Ebenstreit, K.; MacIntosh, N.

    1995-01-01

    This paper outlines the role of a Certified Calibration Laboratory in- ensuring that the requirements of Measuring and Test Equipment calibration, identification, and traceability are met and documented. The Nuclear environment is one which is subject to influences from numerous 'quality agents'. One of the fields which comes under the scrutiny of the quality agents is that of equipment calibration and repair (both field components and M and TE). There is a responsibility to produce a superior product for the Ontario Consumer. The maintenance and calibration of Station Systems and their components have a direct impact on this output. The Measuring and Test Equipment element in each of these needs can be addressed by having a defined group of Maintenance Staff to execute a Measuring and Test Equipment Program which meets specific parameters. (author)

  12. TOUGH2 software qualification

    International Nuclear Information System (INIS)

    Pruess, K.; Simmons, A.; Wu, Y.S.; Moridis, G.

    1996-02-01

    TOUGH2 is a numerical simulation code for multi-dimensional coupled fluid and heat flow of multiphase, multicomponent fluid mixtures in porous and fractured media. It belongs to the MULKOM (open-quotes MULti-KOMponentclose quotes) family of codes and is a more general version of the TOUGH simulator. The MULKOM family of codes was originally developed with a focus on geothermal reservoir simulation. They are suited to modeling systems which contain different fluid mixtures, with applications to flow problems arising in the context of high-level nuclear waste isolation, oil and gas recovery and storage, and groundwater resource protection. TOUGH2 is essentially a subset of MULKOM, consisting of a selection of the better tested and documented MULKOM program modules. The purpose of this package of reports is to provide all software baseline documents necessary for the software qualification of TOUGH2

  13. TOUGH2 software qualification

    Energy Technology Data Exchange (ETDEWEB)

    Pruess, K.; Simmons, A.; Wu, Y.S.; Moridis, G.

    1996-02-01

    TOUGH2 is a numerical simulation code for multi-dimensional coupled fluid and heat flow of multiphase, multicomponent fluid mixtures in porous and fractured media. It belongs to the MULKOM ({open_quotes}MULti-KOMponent{close_quotes}) family of codes and is a more general version of the TOUGH simulator. The MULKOM family of codes was originally developed with a focus on geothermal reservoir simulation. They are suited to modeling systems which contain different fluid mixtures, with applications to flow problems arising in the context of high-level nuclear waste isolation, oil and gas recovery and storage, and groundwater resource protection. TOUGH2 is essentially a subset of MULKOM, consisting of a selection of the better tested and documented MULKOM program modules. The purpose of this package of reports is to provide all software baseline documents necessary for the software qualification of TOUGH2.

  14. Development of remote handling tools and equipment

    International Nuclear Information System (INIS)

    Nakahira, Masataka; Oka, Kiyoshi; Taguchi, Kou; Ito, Akira; Fukatsu, Seiichi; Oda, Yasushi; Kajiura, Soji; Yamazaki, Seiichiro; Aoyama, Kazuo.

    1997-01-01

    The remote handling (RH) tools and equipment development in ITER focuses mainly on the welding and cutting technique, weld inspection and double-seal door which are essential factors in the replacement of in-vessel components such as divertor and blanket. The conceptual design of these RH tools and equipment has been defined through ITER engineering design activity (EDA). Similarly, elementary R and D of the RH tools and equipment have been extensively performed to accumulate a technological data base for process and performance qualification. Based on this data, fabrications of full-scale RH tools and equipment are under progress. A prototypical bore tool for pipe welding and cutting has already been fabricated and is currently undergoing integrated performance tests. This paper describes the design outline of the RH tools and equipment related to in-vessel components maintenance, and highlights the current status of RH tools and equipment development by the Japan Home Team as an ITER R and D program. This paper also includes an outline of insulation joint and quick-pipe connector development, which has also been conducted through the ITER R and D program in order to standardize RH operations and components. (author)

  15. Implementation of a quality control program of the equipment of the nuclear medicine services in Chile

    International Nuclear Information System (INIS)

    Astudillo, R.; Diaz, G.; Ferreira, A.; Garcia, M.; Hermosilla, A.; Pacheco, F.; Vasquez, M.; Coca, M.

    2014-08-01

    Now days in Chile there are more of 43 Nuclear Medicine centers; most of them have gamma cameras in order to study physiological process in diagnostic and treatment of patients pathologies. This requires having the equipment in optimal operating condition and it is ensured with quality control programs that are based on a series of tests relating to protocols, such as TECDOC-602 y AAPM No.6. Planar test often applied in gamma cameras including: spatial resolution, spatial linearity, sensitivity and uniformity. SPECT tests consider: tomography uniformity, rotation center tomography resolution and total performance. The tests in dose calibrator are: background measurement, accuracy, precision, linearity and reproducibility. The tests above require the use of radioactive sources and specific simulators patterns or phantom based on international standards such as The National Electrical Manufacturers Association (Nema), International Atomic Energy Agency (IAEA) and The American Association of Medical Physics (AAPM). In this work we carried out several tests of quality control in a Nuclear Medicine Center of Temuco and we propose to implement the applied methodology in others similar Chilean centers. (author)

  16. Greenbelt Homes Pilot Program: Summary of Building Envelope Retrofits, Planned HVAC Equipment Upgrades, and Energy Savings

    Energy Technology Data Exchange (ETDEWEB)

    Wiehagen, J. [Partnership for Home Innovation, Upper Marlboro, MD (United States); Del Bianco, M. [Partnership for Home Innovation, Upper Marlboro, MD (United States); Mallay, D. [Partnership for Home Innovation, Upper Marlboro, MD (United States)

    2015-05-01

    In the fall of 2010, a multiyear pilot energy efficiency retrofit project was undertaken by Greenbelt Homes, Inc, (GHI) a 1,566 home cooperative of circa 1930 and 1940 homes in Greenbelt, Maryland. GHI established this pilot project to serve as a basis for decision making for the rollout of a decade-long community-wide upgrade program that will incorporate energy efficiency improvements to the building envelope and mechanical equipment. It presents a unique opportunity to evaluate and prioritize the wide-range of benefits of high-performance retrofits based on member experience with and acceptance of the retrofit measures implemented during the pilot project. Addressing the complex interactions between benefits, trade-offs, construction methods, project management implications, realistic upfront costs, financing, and other considerations, serves as a case study for energy retrofit projects to include high-performance technologies based on the long-term value to the homeowner. The pilot project focused on identifying the added costs and energy savings benefits of improvements.

  17. The Petroleum Handling Equipment Research and Development Program of the Department of the Army

    National Research Council Canada - National Science Library

    1956-01-01

    .... The various Technical Services have made very significant progress in the development of improved equipment and techniques for storing, transporting, dispensing and testing fuels and lubricants...

  18. Qualification test on class 1E charger and inverter in nuclear power plant

    International Nuclear Information System (INIS)

    Li Mingcheng; Lin Jian; Fu Mingxing; Xu Benfu; Ma Peifeng

    2014-01-01

    The qualification approach for class lE electrical equipment was introduced, based on IEC, IEEE and RCC-E standards and technical documents. Combined with a lot of practical experience, the qualification scheme for class lE charger and inverter was developed. The component evaluation, performance and stress test, EMC test, seismic test and software qualification for the equipment were analyzed in detail. (authors)

  19. 77 FR 38375 - Advisory Circular (AC) 150/5345-53D, Airport Lighting Equipment Certification Program; Proposed...

    Science.gov (United States)

    2012-06-27

    ... DEPARTMENT OF TRANSPORTATION Federal Aviation Administration Advisory Circular (AC) 150/5345-53D... Advisory Circular (AC) 150/5345-53D, Airport Lighting Equipment Certification Program, is being circulated... on a separate document and not embedded in the draft AC. Additionally, please provide justification...

  20. Guidelines for seismic qualification by experience in ALWRs

    International Nuclear Information System (INIS)

    Bandyopadhyay, K.K.

    1993-01-01

    The methodologies and acceptance criteria for seismic qualification of equipment are provided in IEEE Std. 344 endorsed by the Nuclear Regulatory Commission (NRC) in the Standard Review Plan. The IEEE Standard allows seismic qualification by use of the similarity analysis method. Data available from past earthquake events or vibration tests can be used in this regard. The nuclear industry has collected a vast amount of earthquake experience and test data in the last decade, and is planning to use it for seismic qualification of equipment in advanced light water reactor (ALWR) plants. This paper discusses the existing data bases including their limitations and describes the ways these data bases can be used for equipment qualification in ALWR plants

  1. Guidelines for seismic qualification by experience in ALWRs

    International Nuclear Information System (INIS)

    Bandyopadhyay, K.K.

    1994-01-01

    The methodologies and acceptance criteria for seismic qualification of equipment are provided in IEEE Std. 344 endorsed by the Nuclear Regulatory Commission (NRC) in the Standard Review Plan. The IEEE Standard allows seismic qualification by use of the similarity analysis method. Data available from past earthquake events or vibration tests can be used in this regard. The nuclear industry has collected a vast amount of earthquake experience and test data in the last decade, and is planning to use it for seismic qualification of equipment in advanced light water reactor (ALWR) plants. This paper discusses the existing data bases including their limitations and describes the ways these data bases can be used for equipment qualification in ALWR plants

  2. Results of a literature review on the environmental qualification of low-voltage electric cables

    International Nuclear Information System (INIS)

    Lofaro, R.; Lee, B.; Villaran, M.; Gleason, J.; Aggarwal, S.

    1995-01-01

    In the design of nuclear power plants in the US, safety-related electric equipment must be qualified to provide reasonable assurance it can withstand the effects of a design basis event (DBE) and still be able to perform its prescribed safety function, even if the accident were to occur at the end of its service life. The requirement for environmental qualification (EQ) originates from the General Design Criteria in the Code of Federal Regulations, Title 10, Part 50 (10 CFR 50). The acceptable method of performing the qualification of this equipment has evolved over the years, starting with the NRC Division of Operating Reactors (DOR) Guidelines, which were issued in Bulletin 79--01B, and NUREG-0588 requirements and ending with the current EQ Rule, 10 CFR 50.49. While the EQ methods described in these documents have the same overall objective, there are some notable differences for which a clear technical basis has not been established. One difference is the preaging requirement for equipment prior to LOCA testing. In addition, specific issues related to current EQ practices have been raised by the US NRC which need to be addressed. These issues, which are discussed in detail later in this paper, are related to the sources of conservatism and uncertainty in IEEE Standard 323--1974, which is the qualification standard currently endorsed by the NRC. To address these issues, the NRC Office of Nuclear Reactor Regulation (NRR) implemented a Task Action Plan (TAP), and the Office of Nuclear Reactor Research (RES) initiated a complementary research program. The current focus of this program is on the qualification of low-voltage instrumentation and control cables. These cables were selected since they are not typically replaced on a routine basis, and their degradation could impact plant safety

  3. 78 FR 25627 - Energy Conservation Program for Certain Industrial Equipment: Energy Conservation Standards for...

    Science.gov (United States)

    2013-05-02

    ... average life of the product in the type (or class) compared to any increase in the price of, or in the... well as the market penetration of such equipment. b. Three-Phase Equipment With an Input Capacity Less... standards. This is done by applying a markup multiplier to the manufacturer's [[Page 25632

  4. 78 FR 63410 - Energy Conservation Program for Consumer Products: Test Procedures for Direct Heating Equipment...

    Science.gov (United States)

    2013-10-24

    ... test procedures for direct heating equipment and pool heaters established under the Energy Policy and... U.S.C. 6293(e)(2)) The current energy conservation standards for direct heating equipment and pool... DEPARTMENT OF ENERGY 10 CFR Part 430 [Docket Number EERE-2013-BT-TP-0004] RIN 1904-AC94 Energy...

  5. A Failing Grade for WEEE Take-Back Programs for Information Technology Equipment

    Science.gov (United States)

    Nakajima, Nina; Vanderburg, Willem H.

    2005-01-01

    Product take-back (also called extended producer responsibility) has become a trend for dealing with the garbage resulting from categories of problematic products. Waste electrical and electronic equipment (WEEE) is one such category with computer equipment being of particular significance. This article provides a description of the European…

  6. APM for a Constellation Intersatellite Link - EM Qualification and Lessons Learned

    Science.gov (United States)

    Hartel, Frank; Kozilek, Horst

    2016-01-01

    For an Intersatellite Link (ISL) of a future constellation program, a study phase was initiated by ESA to design a mechanism for Radio Frequency communication. Airbus DS Friedrichshafen (ADSF) proposed a design based on the Antenna Pointing Mechanism (APM) family with modifications that met the stated needs of the constellation. A qualification program was started beginning in September 2015 to verify the launch and thermal loads and the equipment performance (Radio Frequency, Pointing, Microvibration and Magnetic Moment). Technical challenges identified with the Engineering Model will be discussed within this paper.

  7. Radiological Control Technician: Standardized technician Qualification Standard

    International Nuclear Information System (INIS)

    1992-10-01

    The Qualification Standard states and defines the knowledge and skill requirements necessary for successful completion of the Radiological Control Technician Training Program. The standard is divided into three phases: Phase I concerns RCT Academic training. There are 13 lessons associated with the core academics program and 19 lessons associated with the site academics program. The staff member should sign the appropriate blocks upon successful completion of the examination for that lesson or group of lessons. In addition, facility specific lesson plans may be added to meet the knowledge requirements in the Job Performance Measures (JPM) of the practical program. Phase II concerns RCT core/site practical (JPMs) training. There are thirteen generic tasks associated with the core practical program. Both the trainer/evaluator and student should sign the appropriate block upon successful completion of the JPM. In addition, facility specific tasks may be added or generic tasks deleted based on the results of the facility job evaluation. Phase III concerns the oral examination board successful completion of the oral examination board is documented by the signature of the chairperson of the board. Upon completion of all of the standardized technician qualification requirements, final qualification is verified by the student and the manager of the Radiological Control Department and acknowledged by signatures on the qualification standard. The completed Qualification Standard shall be maintained as an official training record

  8. Understanding interdisciplinary health care teams: using simulation design processes from the Air Carrier Advanced Qualification Program to identify and train critical teamwork skills.

    Science.gov (United States)

    Hamman, William R; Beaudin-Seiler, Beth M; Beaubien, Jeffrey M

    2010-09-01

    In the report "Five Years After 'To Err is Human' ", it was noted that "the combination of complexity, professional fragmentation, and a tradition of individualism, enhanced by a well-entrenched hierarchical authority structure and diffuse accountability, forms a daunting barrier to creating the habits and beliefs of common purpose, teamwork, and individual accountability for successful interdependence that a safe culture requires". Training physicians, nurses, and other professionals to work in teams is a concept that has been promoted by many patient safety experts. However the model of teamwork in healthcare is diffusely defined, no clear performance metrics have been established, and the use of simulation to train teams has been suboptimal. This paper reports on the first three years of work performed in the Michigan Economic Development Corporation (MEDC) Tri-Corridor life science grant to apply concepts and processes of simulation design that were developed in the air carrier industry to understand and train healthcare teams. This work has been monitored by the American Academy for the Advancement of Science (AAA) and is based on concepts designed in the Advanced Qualification Program (AQP) from the air carrier industry, which trains and assesses teamwork skills in the same manner as technical skills. This grant has formed the foundation for the Center of Excellence for Simulation Education and Research (CESR).

  9. Approach to customer qualification of the BNFL Sellafield Mox Plant

    International Nuclear Information System (INIS)

    Sullivan, P.

    2003-01-01

    BNFL started plutonium commissioning of its Sellafield MOX Plant (SMP) in December 2001, with the first MOX pellets being produced in May 2002. SMP was designed to manufacture a range of both PWR and BWR fuel types for a number of different customers. During commissioning and early MOX fuel manufacturing BNFL has been demonstrating its ability to both automatically manufacture and inspect MOX fuel to meet the requirements of different customers' specifications and fuel types. The qualification project consisted of common and project specific qualification. Common qualification was carried out to demonstrate BNFL could meet several customers' requirements during the same qualification test. Project specific qualification was carried out for one customer only as the fabrication or inspection equipment was specific to their fuel type. An example is the fuel assembly process. The reasons for BNFL carrying out common qualification were: - Develop a common qualified process to meet different customer specifications. - Minimise future qualifications prior to starting future fuel campaigns. - Ensure BNFL understands and effectively manages different customer requirements in SMP. BNFL has approached qualification of SMP systematically. Firstly the inspection system was qualified, and once completed the inspection system was then used in the qualification of the manufacturing process. (orig.)

  10. On relaxing the Mangasarian-Fromovitz constraint qualification

    Czech Academy of Sciences Publication Activity Database

    Kruger, A.Y.; Minchenko, L.; Outrata, Jiří

    2014-01-01

    Roč. 18, č. 1 (2014), s. 171-189 ISSN 1385-1292 R&D Projects: GA ČR GAP402/12/1309 Institutional support: RVO:67985556 Keywords : Nonlinear programming * Regularity conditions * Constraint qualifications * Lagrange multipliers * Mangasarian–Fromovitz constraint qualification * Constant rank constraint qualification Subject RIV: BA - General Mathematics Impact factor: 0.679, year: 2014 http://library.utia.cas.cz/separaty/2014/MTR/outrata-0426110.pdf

  11. Hanford Waste Vitrification Plant Quality Assurance Program description for high-level waste form development and qualification

    International Nuclear Information System (INIS)

    1993-08-01

    The Hanford Waste Vitrification Plant Project has been established to convert the high-level radioactive waste associated with nuclear defense production at the Hanford Site into a waste form suitable for disposal in a deep geologic repository. The Hanford Waste Vitrification Plant will mix processed radioactive waste with borosilicate material, then heat the mixture to its melting point (vitrification) to forin a glass-like substance that traps the radionuclides in the glass matrix upon cooling. The Hanford Waste Vitrification Plant Quality Assurance Program has been established to support the mission of the Hanford Waste Vitrification Plant. This Quality Assurance Program Description has been written to document the Hanford Waste Vitrification Plant Quality Assurance Program

  12. DOE handbook: Guide to good practices for training and qualification of maintenance personnel

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-03-01

    The purpose of this Handbook is to provide contractor training organizations with information that can be used to verify the adequacy of and/or modify existing maintenance training programs, or to develop new training programs. This guide, used in conjunction with facility-specific job analyses, provides a framework for training and qualification programs for maintenance personnel at DOE reactor and nonreactor nuclear facilities. Recommendations for qualification are made in four areas: education, experience, physical attributes, and training. The functional positions of maintenance mechanic, electrician, and instrumentation and control technician are covered by this guide. Sufficient common knowledge and skills were found to include the three disciplines in one guide to good practices. Contents include: qualifications; on-the-job training; trainee evaluation; continuing training; training effectiveness evaluation; and program records. Appendices are included which relate to: administrative training; industrial safety training; fundamentals training; tools and equipment training; facility systems and component knowledge training; facility systems and component skills training; and specialized skills training.

  13. DOE handbook: Guide to good practices for training and qualification of maintenance personnel

    International Nuclear Information System (INIS)

    1996-03-01

    The purpose of this Handbook is to provide contractor training organizations with information that can be used to verify the adequacy of and/or modify existing maintenance training programs, or to develop new training programs. This guide, used in conjunction with facility-specific job analyses, provides a framework for training and qualification programs for maintenance personnel at DOE reactor and nonreactor nuclear facilities. Recommendations for qualification are made in four areas: education, experience, physical attributes, and training. The functional positions of maintenance mechanic, electrician, and instrumentation and control technician are covered by this guide. Sufficient common knowledge and skills were found to include the three disciplines in one guide to good practices. Contents include: qualifications; on-the-job training; trainee evaluation; continuing training; training effectiveness evaluation; and program records. Appendices are included which relate to: administrative training; industrial safety training; fundamentals training; tools and equipment training; facility systems and component knowledge training; facility systems and component skills training; and specialized skills training

  14. Hanford Waste Vitrification Plant quality assurance program description for defense high-level waste form development and qualification

    International Nuclear Information System (INIS)

    Hand, R.L.

    1990-12-01

    The US Department of Energy-Office of Civilian Radioactive Waste Management has been designated the national high-level waste repository licensee and the recipient for the canistered waste forms. The Office of Waste Operations executes overall responsibility for producing the canistered waste form. The Hanford Waste Vitrification Plant Project, as part of the waste form producer organization, consists of a vertical relationship. Overall control is provided by the US Department of Energy-Environmental Restoration and Waste Management Headquarters; with the US Department of Energy-Office of Waste Operations; the US Department of Energy- Headquarters/Vitrification Project Branch; the US Department of Energy-Richland Operations Office/Vitrification Project Office; and the Westinghouse Hanford Company, operations and engineering contractor. This document has been prepared in response to direction from the US Department of Energy-Office of Civilian Radioactive Waste Management through the US Department of Energy-Richland Operations Office for a quality assurance program that meets the requirements of the US Department of Energy. This document provides guidance and direction for implementing a quality assurance program that applies to the Hanford Waste Vitrification Plant Project. The Hanford Waste Vitrification Plant Project management commits to implementing the quality assurance program activities; reviewing the program periodically, and revising it as necessary to keep it current and effective. 12 refs., 6 figs., 1 tab

  15. AGR-1 Data Qualification Report

    International Nuclear Information System (INIS)

    Abbott, Michael

    2010-01-01

    Projects for the very high temperature reactor (VHTR) Technology Development Office (TDO) program provide data in support of Nuclear Regulatory Commission licensing of the VHTR. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high temperature and high fluence environments. The VHTR program has established the NGNP Data Management and Analysis System (NDMAS) to ensure that VHTR data are (1) qualified for use, (2) stored in a readily accessible electronic form, and (3) analyzed to extract useful results. This document focuses on the first NDMAS objective. It describes the data streams associated with the first Advanced Gas Reactor experiment (AGR-1), the processing of these data within NDMAS, and reports the qualification status of the data. Data qualification activities within NDMAS for specific types of data are determined by the data qualification category assigned by the data generator. They include: (1) capture testing, to confirm that the data stored within NDMAS are identical to the raw data supplied, (2) accuracy testing, to confirm that the data are an accurate representation of the system or object being measured, and (3) documentation that the data were collected under an NQA-1 or equivalent quality assurance program. The NDMAS database processing and qualification status of the following five data streams is reported in this document: (1) Fuel fabrication data. All data have been processed into the NDMAS database and qualified (1,819 records). (2) Fuel irradiation data. Data from all 13 AGR-1 reactor cycles have been processed into the NDMAS database and tested. Of these, 85% have been qualified and 15% have failed NDMAS accuracy testing. (3) FPMS data. Reprocessed (January 2010) data from all 13 AGR-1 reactor cycles have been processed into the database and capture tested. Final qualification of these data will be recorded after QA approval of an Engineering Calculations and Analysis Report currently

  16. Inspector qualification guidelines

    International Nuclear Information System (INIS)

    Batty, A.C.; Van Binnebeek, J.J.; Ericsson, P.O.; Fisher, J.C.; Geiger, P.; Grandame, M.; Grimes, B.K.; Joode, A. de; Kaufer, B.; Kinoshita, M.; Klonk, H.; Koizumi, H.; Maeda, N.; Maqua, M.; Perez del Moral, C.; Roselli, F.; Warren, T.; Zimmerman, R.

    1994-07-01

    The OECD Nuclear Energy Agency Committee on Nuclear Regulatory Activities (CNRA) has a Working Group on Inspection Practices (WGIP). The WGIP provides a forum for the exchange of Information and experience on the safety Inspection practices of regulatory authorities In the CNRA member countries. A consistent qualification process and well defined level of training for all Inspectors who participate In the safety Inspections are needed to provide consistent Inspections and reliable Inspection results. The WGIP organized in 1992 a workshop on the conduct of inspections, inspector qualification and training, and shutdown inspections at the Technical Training Center of the US NRC in Chattanooga, Tennessee. In the connection of workshop the WGIP identified a need to develop guidance for inspector qualification which could be used as a model by those who are developing their qualification practices. The inspector qualification journals of US NRC provided a good basis for the work. The following inspector qualification guideline has been developed for guidance of qualification of a new inspector recruited to the regulatory body. This guideline has been developed for helping the supervisors and training officers to give the initial training and familiarization to the duties of a new inspector in a controlled manner. US NRC inspector qualification journals have been used to define the areas of attention. This guideline provides large flexibility for application in different type organizations. Large organizations can develop separate qualification journals for each inspector positions. Small regulatory bodies can develop individual training programmes by defining the necessary training topics on case by case basis. E.g. the guideline can be used to define the qualifications of contracted inspectors used in some countries. The appropriate part would apply. Annex 1 gives two examples how this guideline could be applied

  17. Inspector qualification guidelines

    Energy Technology Data Exchange (ETDEWEB)

    Batty, A. C.; Van Binnebeek, J. J.; Ericsson, P. O.; Fisher, J. C.; Geiger, P.; Grandame, M.; Grimes, B. K.; Joode, A. de; Kaufer, B.; Kinoshita, M.; Klonk, H.; Koizumi, H.; Maeda, N.; Maqua, M.; Perez del Moral, C.; Roselli, F.; Warren, T.; Zimmerman, R.

    1994-07-15

    The OECD Nuclear Energy Agency Committee on Nuclear Regulatory Activities (CNRA) has a Working Group on Inspection Practices (WGIP). The WGIP provides a forum for the exchange of Information and experience on the safety Inspection practices of regulatory authorities In the CNRA member countries. A consistent qualification process and well defined level of training for all Inspectors who participate In the safety Inspections are needed to provide consistent Inspections and reliable Inspection results. The WGIP organized in 1992 a workshop on the conduct of inspections, inspector qualification and training, and shutdown inspections at the Technical Training Center of the US NRC in Chattanooga, Tennessee. In the connection of workshop the WGIP identified a need to develop guidance for inspector qualification which could be used as a model by those who are developing their qualification practices. The inspector qualification journals of US NRC provided a good basis for the work. The following inspector qualification guideline has been developed for guidance of qualification of a new inspector recruited to the regulatory body. This guideline has been developed for helping the supervisors and training officers to give the initial training and familiarization to the duties of a new inspector in a controlled manner. US NRC inspector qualification journals have been used to define the areas of attention. This guideline provides large flexibility for application in different type organizations. Large organizations can develop separate qualification journals for each inspector positions. Small regulatory bodies can develop individual training programmes by defining the necessary training topics on case by case basis. E.g. the guideline can be used to define the qualifications of contracted inspectors used in some countries. The appropriate part would apply. Annex 1 gives two examples how this guideline could be applied.

  18. The OSMOSE program for the qualification of integral cross sections of actinides: Preliminary results in a PWR-UOx spectrum

    Energy Technology Data Exchange (ETDEWEB)

    Hudelot, J. P. [CEA Cadarache, DEN/DER, 13108 Saint Paul lez Durance (France); Klann, R. [Argonne National Laboratory, 9700 South Cass Avenue, Argonne, IL 60439 (United States); Antony, M.; Bernard, D.; Fougeras, P. [CEA Cadarache, DEN/DER, 13108 Saint Paul lez Durance (France); Jorion, F.; Drin, N.; Donnet, L.; Leorier, C. [CEA VALRHO, DEN/DRCP, BP171, 30207 Bagnols-sur-Ceze Cedex (France); Zhong, Z. [Argonne National Laboratory, 9700 South Cass Avenue, Argonne, IL 60439 (United States)

    2006-07-01

    The need for improved nuclear data for minor actinides has been stressed by various organizations throughout the world - especially for studies relating to plutonium management, waste incineration, transmutation of waste, and Pu burning in future nuclear concepts. Several international programs have indicated a strong desire to obtain accurate integral reaction rate data for improving the major and minor actinides cross sections. Data on major actinides (i.e. {sup 235}U, {sup 236}U, {sup 238}U, {sup 239}Pu, {sup 240}Pu, {sup 241}Pu, {sup 242}Pu and {sup 241}Am) are reasonably well-known and available in the Evaluated Nuclear Data Files (JEFF, JENDL, ENDF-BX However information on the minor actinides (i.e. {sup 232}Th, {sup 233}U, {sup 237}Np, {sup 238}Pu, {sup 242}Am, {sup 243}Am, {sup 243}Cm, {sup 235}Cm, {sup 244}Cm, {sup 245}Cm, {sup 246}Cm and {sup 247}Cm) is less well-known and considered to be relatively poor in some cases, having to rely on model and extrapolation of few data points. In this framework, the ambitious OSMOSE program between the Commissariat a l'Energie Atomique (CEA), Electricite de France (EDF) and the U.S. Dept. of Energy (DOE) has been undertaken with the aim of measuring the integral absorption rate parameters of actinides in the MINERVE experimental facility located at the CEA Cadarache Research Center. The OSMOSE Program (Oscillation in Minerve of isotopes in 'Eupraxic' Spectra) includes a complete analytical program associated with the experimental measurement program and aims at understanding and resolving potential discrepancies between calculated and measured values. In the OSMOSE program, the reactivity worth of samples containing separated actinides are measured in different neutron spectra using an oscillation technique with an overall expected accuracy better than 3%. Reactivity effects of less than 10 pcm (0.0001 or approximately 1.5 cents) are measured and compared with calibrations to determine the differential

  19. Maintenance and environmental qualification

    International Nuclear Information System (INIS)

    Martin, R.S.; Austin, D.G.

    1995-01-01

    The design of today's nuclear generating plants involves many detailed design considerations. This includes comprehensive look at aging effects on plant components over their expected lifetimes. This is important to ensuring that the plant operates safely throughout its life. The effects of aging are required to be documented in detail in today's designs. This documentation provides assurance that safe operating conditions are maintained throughout the station life cycle. This requirement is analogous to the longer standing requirement to ensure pressure boundary integrity. The pressure boundary integrity requirement has existed in the industry since its inception. The subject of plant aging effects and the maintenance of functionality is known as Environmental Qualification (EQ). This paper will attempt to explain the wisdom of EQ and the potential for optimizing maintenance activities (to move from reactive to proactive activities), within the context of the overall maintenance program. It is the author's intent to encourage the active involvement of maintenance professionals in the effective implementation of the ongoing EQ program so that the benefits are maximized

  20. Program outline of seismic fragility capacity tests on nuclear power plant equipment

    International Nuclear Information System (INIS)

    Lijima, T.; Abe, H.; Fujita, T.

    2004-01-01

    A seismic probabilistic safety assessment (PSA) is an available method to evaluate residual risk of nuclear plant that is designed with definitive seismic design condition. Seismic fragility capacity data are necessary for seismic PSA, but we don't have sufficient data of active components of nuclear plants in Japan. This paper describes a plan of seismic fragility capacity tests on nuclear power plant equipment. The purpose of those tests is to obtain seismic fragility capacity of important equipment from a safety design point of view. And the equipment for the fragility capacity tests were selected considering effect on core damage frequency (CDF) that was evaluated by our preliminary seismic PSA. Consequently horizontal shaft pump, electric cabinets, Control Rod Drive system (CRD system) of BWR and PWR plant and vertical shaft pump were selected. The seismic fragility capacity tests are conducted from phase-1 to phase-3, and horizontal shaft pump and electric cabinets are tested on phase-1. The fragility capacity test consists of two types of tests. One is actual equipment test and another is element test. On actual equipment test, a real size model is tested with high-level seismic motion, and critical acceleration and failure mode are investigated. Regarding fragility test phase-1, we selected typical type horizontal shaft pump and electric cabinets for the actual equipment test. Those were Reactor Building Closed Cooling Water (RCW) Pump and eight kinds of electric cabinets such as relay cabinet, motor control center. On the test phase-1, maximum input acceleration for the actual equipment test is intended to be 6-G-force. Since the shaking table of TADOTSU facility did not have capability for high acceleration, we made vibration amplifying system. In this system, amplifying device is mounted on original shaking table and it moves in synchronization with original table. The element test is conducted with many samples and critical acceleration, median and

  1. Dynamic testing and qualification

    International Nuclear Information System (INIS)

    Kleine Tebbe, A.; Schmidt, G.; Theymann, W.

    1990-01-01

    The core structure of an HTR-plant consists of the side reflector, the bottom reflector, the top reflector and the pebble bed of spherical fuel elements. Dynamically this system is a many-body structure with non-linear force-deformation couplings. The integrity of the system under seismic loads is given by radially orientated spring packs. These spring packs must be stiff against earthquake loads, but must allow radial thermal movements. To verify the seismic safety of the system, scaled-down models were tested. The results of these tests were compared with those of analytical methods. The good-natured behaviour of the pebble-bed under seismic loads has been confirmed. Due to the granular structure of the non-regular packed pebble-bed, high damping occurs during seismic excitations. With increasing depth the damping ratio decreases because of restriction of movement. We are able to describe the seismic behaviour of the pebble-bed analytically. The one- and two-dimensional test configurations of the top reflector were used to analyse resonance and lumping effects. The experimental results were verified by the computer codes CRUNCH-1D AND CRUNCH-2D. The experimental investigations of the side reflector are underway. The results show a non-critical behaviour under horizontal excitations. Small rigid-body motions of single blocks are detected, but they do not cause any global ovalisations of the complete ring structure. Finite element calculations with contact and friction between the blocks show a close agreement with the experimental results. Seismic qualification of ground mounted electrical equipment is usually performed on the basis of codes like IEEE, IEC, KTA, etc. These standards give different possibilities of the excitation mode: sinusoidal excitation in every natural frequency (continuous or sine beat) or time history excitation which covers a prescribed required response spectrum. Recently performed tests are compared regarding the usefulness and severity

  2. AP-102/104 Retrieval control system qualification test procedure

    International Nuclear Information System (INIS)

    RIECK, C.A.

    1999-01-01

    This Qualification Test Procedure documents the results of the qualification testing that was performed on the Project W-211, ''Initial Tank Retrieval Systems,'' retrieval control system (RCS) for tanks 241-AP-102 and 241-AP-104. The results confirm that the RCS has been programmed correctly and that the two related hardware enclosures have been assembled in accordance with the design documents

  3. Impact on environmental qualification from a longer fuel cycle

    International Nuclear Information System (INIS)

    Sanwarwalla, M.H.; Akhtar, S.; Drankhan, D.A.

    1996-01-01

    There is a general trend in the nuclear industry towards longer fuel cycles because of the economic benefits. The economic benefits for increasing the fuel cycle from eighteen to twenty four months is estimated by the industry to be about $5.05 million per unit year based on a two week mid-cycle maintenance outage. Equipment with a unique characteristic may require maintenance and/or inspection more frequently than can be accommodated in a longer cycle. The maintenance and surveillance (M ampersand S) requirements for these equipment need to be reviewed to accommodate a longer cycle and avoid any unplanned outage. ComEd's LaSalle Station is considering a move to a longer fuel cycle. A study was done to determine the impact of a longer fuel cycle on their current environmental qualification (EQ) program, and the feasibility of implementing changes to their program to accommodate a longer fuel cycle. This paper discusses (1) the impact, if any, the longer fuel cycle will have on the maintenance and surveillance requirements of the 50.49 or environmentally qualified equipment at LaSalle Station, (2) the various techniques, i.e., partial testing, performance based monitoring etc., employed to extend the existing maintenance and surveillance requirements, and (3) the estimated economic savings, if any, from the extended M ampersand S interval

  4. 78 FR 64295 - Energy Conservation Program: Test Procedure for Commercial Refrigeration Equipment

    Science.gov (United States)

    2013-10-28

    ... they are consumer products or commercial and industrial equipment. Under 42 U.S.C. 6314(c)(1), no later... requirements a consumer would expect. DOE requests comment on the proposed definition for chef base or griddle... projection is normal to the plane of the door, and the way customers typically view products through the door...

  5. 76 FR 77914 - Energy Conservation Program for Certain Commercial and Industrial Equipment: Test Procedures for...

    Science.gov (United States)

    2011-12-15

    ... lifetime. Correlated color temperature (CCT) and color rendering index (CRI) would also be measured as potential means to delineate equipment classes for HID lamps. This notice of proposed rulemaking (NOPR) also... Conditions a. Ambient Conditions i. Ambient Test Temperature ii. Air Speed b. Power Supply Characteristics i...

  6. 77 FR 16769 - Energy Conservation Program for Certain Industrial Equipment: Energy Conservation Standards and...

    Science.gov (United States)

    2012-03-22

    ... provisions from AHRI operations manuals (OMs) in its test procedures that would clarify the application of... Compressor Break-In Period.... Small Unitary OM 3.8 (Break-in Certain AHRI OMs DOE is proposing to Operation... equipment class. Period). hours. Tolerances Multiple OMs.... N/A Certain AHRI OMs and Compliance with DOE...

  7. 77 FR 28927 - Energy Conservation Program for Certain Industrial Equipment: Energy Conservation Standards and...

    Science.gov (United States)

    2012-05-16

    ... provisions (with some modification) from AHRI operations manuals (AHRI OMs) that would harmonize equipment... DOE published for notice and comment. By adopting some of the guidance in the AHRI OMs, DOE hopes to... and DOE-initiated testing. In certain cases, the AHRI OMs require manufacturers to provide information...

  8. 77 FR 10291 - Energy Conservation Program: Test Procedure for Commercial Refrigeration Equipment

    Science.gov (United States)

    2012-02-21

    ... Volume and Total Shelf Area of Household Refrigerators and Household Wine Chillers''; and sections 5.1..., some equipment is designed for storing goods such as wine, candy, and flowers at temperatures that are..., No. 19 at p. 145), and offered that night curtains could provide benefits for doored cases. (Zero...

  9. 78 FR 48367 - TRICARE Program; Clarification of Benefit Coverage of Durable Equipment and Ordering or...

    Science.gov (United States)

    2013-08-08

    ...., Seeing Eye dogs, hearing/handicapped assistance animals, etc.). AT devices are authorized only under... must not be otherwise covered as a prosthetic, augmentative communication device, or a benefit under... animals (e.g., Seeing Eye dogs, hearing/handicapped assistance animals, etc.) or specialized equipment and...

  10. Two fuzzy possibilistic bi-objective zero-one programming models for outsourcing the equipment maintenance problem

    Science.gov (United States)

    Vahdani, Behnam; Jolai, Fariborz; Tavakkoli-Moghaddam, Reza; Meysam Mousavi, S.

    2012-07-01

    Maintenance outsourcing can be regarded as a strategic weapon to increase productivity and customer satisfaction in many companies, and this critical activity can be performed in a more efficient and effective way. This article presents two novel fuzzy possibilistic bi-objective zero-one programming (FPBOZOP) models for outsourcing of the equipment maintenance. In these models, cost parameters, including outsourcing cost, risk cost, time operations for performing the equipment maintenance and reliability level, as well as other influential parameters are considered through the outsourcing process. Moreover, the presented models can measure the capability of the company in doing different activities, unlike previous studies, in order to see the possibility of maintenance in-house, and can lead to make a best decision on the basis of the models' results. Both models are developed under uncertainty, which bring top managers the possibility of assigning more than one equipment or project to the supplier so that the profit is maximized, and the cost is minimized by considering bi-objectives concurrently. Then, a new fuzzy mathematical programming based possibilistic approach is introduced as a solution methodology from the recent literature to solve the proposed bi-objective zero-one programming (BOZOP) models and to reach a preferred compromise solution. Furthermore, a real-case study is utilized to demonstrate and to validate the effectiveness of the presented models. The computational results revealed that the models can be implemented in variety of problems in the domain of the equipment maintenance outsourcing and project outsourcing either from theory or application perspectives.

  11. Lower-Level Qualifications as a Stepping Stone for Young People. Occasional Paper

    Science.gov (United States)

    Oliver, Damian

    2012-01-01

    Lower-level qualifications (certificate I and II programs) provide little or no immediate return to the individual in terms of increased wages. However, lower-level qualifications are intended to prepare students who would otherwise not be capable of enrolling in and completing a higher-level qualification or making a successful transition into…

  12. Reaction Qualifications Revisited

    DEFF Research Database (Denmark)

    Lippert-Rasmussen, Kasper

    2009-01-01

      When, in a competitive sphere, people are selected on the basis of qualifications only, their chances of acquiring positions of advantage may seem to depend entirely upon their abilities, not discriminatory bias. However, if reaction qualifications - i.e. characteristics which contribute...... to a person's effectiveness by causing a favourable reaction in customers, co-workers etc. (for short: recipients) - are involved, this assumption is false. Building on work by Wertheimer, Mason, and Miller, this paper proposes an account of the reaction qualifications that count, from the point of view...... of merit. Specifically, it preserves symmetry between negative evaluations of antimeritocratic bases of selection and negative evaluations of qualifications rooted in comparable antimeritocratic reactions. So if employers should not select among applicants on the basis of their (the employers') racial...

  13. Defense Health Program Financial Reporting of General Property, Plant, and Equipment

    National Research Council Canada - National Science Library

    Lane, F

    2000-01-01

    .... The Defense Health Program funds the operations of the Military Departments' medical treatment facilities, the development of DoD medical systems software, and congressionally directed research...

  14. Qualifications and Competencies for Population Health Management Positions: A Content Analysis of Job Postings.

    Science.gov (United States)

    Meyer, Melanie

    2017-12-01

    The need for population health management expertise has increased as the health care industry shifts toward value-based care. However, many organizations report hiring gaps as they seek to fill positions. The purpose of this study was to analyze the types of population health management positions for which health care organizations are hiring, including qualifications and competencies required for these positions. A content analysis was conducted on 271 job postings collected during a 2-month period. A typology of qualifications and competencies was developed based on the content analysis. Profiles were generated for the top 5 job title classifications: directors, coordinators, care managers, analysts, and specialists. This study highlights the investment health care organizations are making in population health management and the prominent role these positions are playing in the health care environment today. Many organizations are building out population health management teams resulting in multiple positions at different levels being added. As the market demands competent candidates who are equipped with specialized population health expertise as well as practical experience in program development, technology applications, care management, and analytics, professional education programs will need to adapt curricula to address the required areas. Competencies for specific job title classifications may need further evaluation and refinement over time. Study results can be used by organizations for strategic planning, by educators to target needed qualifications and competencies, and by researchers and policy advisors to assess progress toward value-based care.

  15. Greenbelt Homes Pilot Program. Summary of Building Envelope Retrofits, Planned HVAC Equipment Upgrades, and Energy Savings

    Energy Technology Data Exchange (ETDEWEB)

    Wiehagen, J. [Home Innovation Research Labs, Marlboro, MD (United States); Del Bianco, M. [Home Innovation Research Labs, Marlboro, MD (United States); Mallay, D. [Home Innovation Research Labs, Marlboro, MD (United States)

    2015-05-22

    The U.S. Department of Energy Building America team Partnership for Home Innovation wrote a report on Phase 1 of the project that summarized a condition assessment of the homes and evaluated retrofit options within the constraints of the cooperative provided by GHI. Phase 2 was completed following monitoring in the 2013–2014 winter season; the results are summarized in this report. Phase 3 upgrades of heating equipment will be implemented in time for the 2014–2015 heating season and are not part of this report.

  16. 75 FR 13114 - Energy Conservation Program for Certain Industrial Equipment: Publication of the Petition for...

    Science.gov (United States)

    2010-03-18

    ... capacity ECO-i (commercial) multi- split heat pumps. Through this document, DOE: (1) Solicits comments.... Brenda Edwards, U.S. Department of Energy, Building Technologies Program, Mailstop EE-2J/1000... Technologies Program, 950 L'Enfant Plaza, SW., Suite 600, Washington, DC 20024. Please submit one signed...

  17. 77 FR 35299 - Energy Conservation Program for Consumer Products and Certain Commercial and Industrial Equipment...

    Science.gov (United States)

    2012-06-13

    ... Conservation Program for Consumer Products Other Than Automobiles,\\2\\ a program covering most major household... polluting than sources that must be used during peak demand times. The utilities indicated that a survey... customarily treated as confidential within the industry; (3) whether the information is generally known by or...

  18. 15 CFR 40.2 - Qualifications.

    Science.gov (United States)

    2010-01-01

    ... Qualifications. (a) To be eligible for a training grant at the Bureau of the Census the applicant must be: (1) A... training programs. (2) Able to speak, read, write, and understand the English language. (3) Sponsored by his government either directly with the United States or through a public international agency. (4...

  19. B and W NPGD quality assurance program for nuclear equipment. Revision 1

    International Nuclear Information System (INIS)

    1975-03-01

    B and W's Quality Assurance Program (QAP) is described. The program is implemented through the Nuclear Power Generation Division (NPGD) and includes design, procurement, and manufacturing activities of NPGD and all its suppliers furnishing items in the B and W scope of supply including other Divisions/ Subsidiaries of B and W. These activities are controlled by including applicable quality assurance requirements, as described, in NPGD procurement documents imposed on its suppliers. Each supplier must then establish and/or maintain a documented QA Program to meet the requirements imposed by the procurement documents. Implementation of the suppliers' NPGD-approved QA Program is verified by NPGD through Audit and QC Surveillance activities. The position and relationships of the NPGD within the Company's corporate structure are described. An overview of the QAP describing its implementation, its operation, the controls imposed on all suppliers (both corporate and vendor) and site consulting activities is presented. (U.S.)

  20. Shuttle Ground Support Equipment (GSE) T-0 Umbilical to Space Shuttle Program (SSP) Flight Elements Consultation

    Science.gov (United States)

    Wilson, Timmy R.; Kichak, Robert A.; McManamen, John P.; Kramer-White, Julie; Raju, Ivatury S.; Beil, Robert J.; Weeks, John F.; Elliott, Kenny B.

    2009-01-01

    The NASA Engineering and Safety Center (NESC) was tasked with assessing the validity of an alternate opinion that surfaced during the investigation of recurrent failures at the Space Shuttle T-0 umbilical interface. The most visible problem occurred during the Space Transportation System (STS)-112 launch when pyrotechnics used to separate Solid Rocket Booster (SRB) Hold-Down Post (HDP) frangible nuts failed to fire. Subsequent investigations recommended several improvements to the Ground Support Equipment (GSE) and processing changes were implemented, including replacement of ground-half cables and connectors between flights, along with wiring modifications to make critical circuits quad-redundant across the interface. The alternate opinions maintained that insufficient data existed to exonerate the design, that additional data needed to be gathered under launch conditions, and that the interface should be further modified to ensure additional margin existed to preclude failure. The results of the assessment are contained in this report.

  1. AGR-2 Data Qualification Interim Report

    Energy Technology Data Exchange (ETDEWEB)

    Michael L. Abbott

    2010-09-01

    Projects for the very high temperature reactor (VHTR) Technology Development Office program provide data in support of Nuclear Regulatory Commission licensing of the VHTR. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high temperature and high fluence environments. The VHTR program established the NGNP Data Management and Analysis System (NDMAS) to manage and document VHTR data qualification, for storage of the data in a readily accessible electronic form, and to assist in the analysis and presentation of the data. This document gives the status of NDMAS processing and qualification of data associated with the initial reactor cycle (147A) of the second Advanced Gas Reactor (AGR-2) experiment which began on June 21, 2010. Because it is early in the AGR-2 experiment, data from only two AGR-2 data streams are reported on: Fuel Fabrication and Fuel Irradiation data. As of August 1, 2010, approximately 311,000 irradiation data records have been stored in NDMAS, and qualification tests are in progress. Preliminary information indicates that TC 2 in Capsule 2 failed prior to start of the experiment, and NDMAS testing has thus far identified only two invalid data values from the METSO data collection system Data from the Fission Product Monitoring System (FPMS) are not currently processed until after reactor cycle shutdown and have not yet been received. A description of the ATR operating conditions data associated with the AGR-2 experiment (e.g., power levels) are summarized in the AGR-1 data qualification report (INL/EXT-09-16460). Since ATR data are collected under ATR program data quality requirements (i.e., outside the VHTR program), the NGNP program and NDMAS do not take additional actions to qualify these data other than NDMAS capture testing. Data qualification of graphite characterization data collected under the Graphite Technology Development Project is reported in a separate status report (Hull 2010).

  2. AGR-2 Data Qualification Interim Report

    International Nuclear Information System (INIS)

    Abbott, Michael L.

    2010-01-01

    Projects for the very high temperature reactor (VHTR) Technology Development Office program provide data in support of Nuclear Regulatory Commission licensing of the VHTR. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high temperature and high fluence environments. The VHTR program established the NGNP Data Management and Analysis System (NDMAS) to manage and document VHTR data qualification, for storage of the data in a readily accessible electronic form, and to assist in the analysis and presentation of the data. This document gives the status of NDMAS processing and qualification of data associated with the initial reactor cycle (147A) of the second Advanced Gas Reactor (AGR-2) experiment which began on June 21, 2010. Because it is early in the AGR-2 experiment, data from only two AGR-2 data streams are reported on: Fuel Fabrication and Fuel Irradiation data. As of August 1, 2010, approximately 311,000 irradiation data records have been stored in NDMAS, and qualification tests are in progress. Preliminary information indicates that TC 2 in Capsule 2 failed prior to start of the experiment, and NDMAS testing has thus far identified only two invalid data values from the METSO data collection system Data from the Fission Product Monitoring System (FPMS) are not currently processed until after reactor cycle shutdown and have not yet been received. A description of the ATR operating conditions data associated with the AGR-2 experiment (e.g., power levels) are summarized in the AGR-1 data qualification report (INL/EXT-09-16460). Since ATR data are collected under ATR program data quality requirements (i.e., outside the VHTR program), the NGNP program and NDMAS do not take additional actions to qualify these data other than NDMAS capture testing. Data qualification of graphite characterization data collected under the Graphite Technology Development Project is reported in a separate status report (Hull 2010).

  3. Personal Protective Equipment

    National Research Council Canada - National Science Library

    1998-01-01

    ... of personal protective equipment A safety program for new employees is a necessary part of any orientation program An on-going safety program should be used to motivate employees to continue to use...

  4. Design requirements, criteria and methods for seismic qualification of CANDU power plants

    International Nuclear Information System (INIS)

    Singh, N.; Duff, C.G.

    1979-10-01

    This report describes the requirements and criteria for the seismic design and qualification of systems and equipment in CANDU nuclear power plants. Acceptable methods and techniques for seismic qualification of CANDU nuclear power plants to mitigate the effects or the consequences of earthquakes are also described. (auth)

  5. Characterization of changes in commercial building structure, equipment, and occupants: End-Use Load and Consumer Assessment Program

    Energy Technology Data Exchange (ETDEWEB)

    Lucas, R.G.; Taylor, Z.T.; Miller, N.E.; Pratt, R.G.

    1990-12-01

    Changes in commercial building structure, equipment, and occupants result in changes in building energy use. The frequency and magnitude of those changes have substantial implications for conservation programs and resource planning. For example, changes may shorten the useful lifetime of a conservation measure as well as impact the savings from that measure. This report summarizes the frequency of changes in a commercial building sample that was end-use metered under the End-Use Load and Consumer Assessment Program (ELCAP). The sample includes offices, dry good retails, groceries, restaurants, warehouses, schools, and hotels. Two years of metered data, site visit records, and audit data were examined for evidence of building changes. The observed changes were then classified into 12 categories, which included business type, equipment, remodel, vacancy, and operating schedule. The analysis characterized changes in terms of frequency of types of change; relationship to building vintage and floor area; and variation by building type. The analysis also examined the energy impacts of various changes. The analysis determined that the rate of change in commercial buildings is high--50% of the buildings experienced one type of change during the 2 years for which monitoring data were examined. Equipment changes were found to be most frequent in offices and retail stores. Larger, older office buildings tend to experience a wider variety of changes more frequently than the smaller, newer buildings. Key findings and observations are presented in Section 2. Section 3 provides the underlying motivation and objectives. In Section 4, the methodology used is documented, including the commercial building sample and the data sources used. Included are the definitions of change events and the overall approach taken. Results are analyzed in Section 5, with additional technical details in Appendixes. 2 refs., 46 figs., 22 tabs. (JF)

  6. Evaluation of Storage for Transportation Equipment, Unfueled Convertors, and Fueled Convertors at the INL for the Radioisotope Power Systems Program

    Energy Technology Data Exchange (ETDEWEB)

    S. G. Johnson; K. L. Lively

    2010-05-01

    This report contains an evaluation of the storage conditions required for several key components and/or systems of the Radioisotope Power Systems (RPS) Program at the Idaho National Laboratory (INL). These components/systems (transportation equipment, i.e., type ‘B’ shipping casks and the radioisotope thermo-electric generator transportation systems (RTGTS), the unfueled convertors, i.e., multi-hundred watt (MHW) and general purpose heat source (GPHS) RTGs, and fueled convertors of several types) are currently stored in several facilities at the Materials and Fuels Complex (MFC) site. For various reasons related to competing missions, inherent growth of the RPS mission at the INL and enhanced efficiency, it is necessary to evaluate their current storage situation and recommend the approach that should be pursued going forward for storage of these vital RPS components and systems. The reasons that drive this evaluation include, but are not limited to the following: 1) conflict with other missions at the INL of higher priority, 2) increasing demands from the INL RPS Program that exceed the physical capacity of the current storage areas and 3) the ability to enhance our current capability to care for our equipment, decrease maintenance costs and increase the readiness posture of the systems.

  7. Implementation plans for the Korean certified tumor registrar qualification system.

    Science.gov (United States)

    Boo, Yoo-Kyung; Lim, Hyun-Sook; Won, Young-Joo

    2014-01-01

    Cancer registration data is used to understand the nation's cancer burden, and to provide significant baseline data for cancer control efforts, as well as, research on cancer incidence, mortality, survival, and prevalence. A system that approves, assesses, and manages the qualification of specialists, responsible for performing cancer registration, has not been developed in Korea. This study presents ways to implement a certification system designed for the qualification of tumor registrars in Korea. Requirements for implementing a certified tumor registrar qualification system were determined by reviewing the system for establishing qualifications in Korea and the American qualification system via the National Cancer Registrars Association (NCRA). Moreover, a survey was conducted on Korean medical records administrators, who had taken the U.S. Certified Tumor Registrar (CTR) examination, in order to review their opinions regarding these requirements. This study verified the feasibility of a qualification examination based on the opinions of CTR specialists by determining the following: items, and the associated ratings, of the qualifications necessary to register individuals as certified tumor registrars in a private qualification system; status of human resources required for the examination or training processes; plans regarding the organization needed for management, and operation of qualifications, examination standards, subject areas, examination methods, examination qualifications, or education and training programs. The implementation of a certified tumor registrar qualification system will lead to enhanced job competency for specialists and a qualitative improvement of cancer registration data. It will also reliably foster human resources that will lay the groundwork needed to establish scientific and reasonable national cancer management policies.

  8. 75 FR 41845 - Energy Conservation Program for Certain Commercial and Industrial Equipment: Decision and Order...

    Science.gov (United States)

    2010-07-19

    ... conditioners and heat pumps. The waiver is specific to the Sanyo variable capacity ECO-i (commercial) multi... in this notice to test and rate its ECO-i multi-split products. DATES: This Decision and Order is..., Building Technologies Program, Mailstop EE-2J, 1000 Independence Avenue, SW., Washington, DC 20585-0121...

  9. 78 FR 62970 - Energy Conservation Program for Consumer Products and Certain Commercial and Industrial Equipment...

    Science.gov (United States)

    2013-10-23

    ... Standard E. Definition of Basic Model F. Statistical Sampling Plans G. Information To Be Provided in... administrative convenience based on their nature or type. Under EPCA, the energy conservation program consists... Reference of Standards 5. Basic Models 6. Statistical Sampling Plans 7. Information To Be Provided in...

  10. Development of 3 D Electric Field Analysis Program under Power System Equipment

    Energy Technology Data Exchange (ETDEWEB)

    Myung, S. H.; Lee, K. C.; Lee, J. B.; Ha, T. H. [Korea Electrotechnology Research Institute, Changwon (Korea, Republic of)

    1996-12-01

    Recently, as the effects of electric fields on animals, human beings and sensitive equipment have been reported, the study on electric fields has become more important. Transmission lines and substation among power facilities are dominant parts related to electrical environment. Electric field analysis of transmission line has been made using image charge method or CSM since 1970`s, however electric field analysis in substation has been rarely studied due to the complexity of three dimensional evaluation of an electric field in substation. For the rather complicated and time-consuming three-dimensional electric field calculation in the vicinity of transmission lines and substations, this study proposes an effective numerical calculation method based on Charge Simulation Method(CSM). In order to represent non-uniform charge distribution on an electrode better, it is subdivided into small segments with linear charge density. Each segment with linear charge density can be easily represented by a generalized finite line type of charge whose expressions for potential and electric field were analytically derived and which was named {sup f}inite slant line charge in this study. As for the arrangement of small segments of a subdivided electrode, it has been found that unequally spaced arrangement method is superior to equally spaced one. In order to arrange segments fast and effectively, effective formulas were derived from multiple regression analysis of many simulations. The proposed method is applied to the electric field calculation around the transmission lines with significant change in direction and substation busbars. (author). refs., figs., tabs.

  11. A programming system for a modular, flexible multicomputer system for the automatic control of automated test equipment

    International Nuclear Information System (INIS)

    Schmidt, J.

    1984-11-01

    The hardware used is operationally directed, consisting of largely self-functioning, micro-computing modules, combined together over a parallel systembus. For communication purposes between the modules and to synchronize their activities a multi microcomputing operating system is being developed which corresponds to the specific demands of computerized process-control (handling of real-word events under real-time conditions and operation of several parallel-running subprocesses). In order to program the user-specific test cycles a programming language has to be made available which can be coordinated with the operational range of specific test equipment in terms of commands and syntax and which can also easily be learned by operators having no specialised knowledge of data processing. With this objective in mind, a structural system is developed in this work, by the aid of which application-oriented programming languages can be implemented. The adaption of the programming system to a wide spectrum of applications in automatic testing is facilitated by its modular structure. The efficiency of the system is demonstrated by means of an industrial pilot-scale implementation. (orig./HP) [de

  12. Mississippi Curriculum Framework for Diesel Equipment Repair & Service (Program CIP: 47.0605--Diesel Engine Mechanic & Repairer). Secondary Programs.

    Science.gov (United States)

    Mississippi Research and Curriculum Unit for Vocational and Technical Education, State College.

    This document, which reflects Mississippi's statutory requirement that instructional programs be based on core curricula and performance-based assessment, contains outlines of the instructional units required in local instructional management plans and daily lesson plans for diesel engine mechanics I and II. Presented first are a program…

  13. Space Shuttle Program (SSP) Shock Test and Specification Experience for Reusable Flight Hardware Equipment

    Science.gov (United States)

    Larsen, Curtis E.

    2012-01-01

    As commercial companies are nearing a preliminary design review level of design maturity, several companies are identifying the process for qualifying their multi-use electrical and mechanical components for various shock environments, including pyrotechnic, mortar firing, and water impact. The experience in quantifying the environments consists primarily of recommendations from Military Standard-1540, Product Verification Requirement for Launch, Upper Stage, and Space Vehicles. Therefore, the NASA Engineering and Safety Center (NESC) formed a team of NASA shock experts to share the NASA experience with qualifying hardware for the Space Shuttle Program (SSP) and other applicable programs and projects. Several team teleconferences were held to discuss past experience and to share ideas of possible methods for qualifying components for multiple missions. This document contains the information compiled from the discussions

  14. Counterterrorism: DOD Should Enhance Management of and Reporting on Its Global Train and Equip Program

    Science.gov (United States)

    2016-04-01

    this work may contain copyrighted images or other material , permission from the copyright holder may be necessary if you wish to reproduce this... material separately. Page 1 GAO-16-368 Counterterrorism 441 G St. N.W. Washington, DC 20548 April 18, 2016 Congressional Committees...The fiscal year 2015 National Defense Authorization Act (NDAA) included a provision for GAO to conduct biennial audits of programs conducted pursuant

  15. Painting for nuclear power stations and machinery and equipments according to quality assurance program of ANSI

    International Nuclear Information System (INIS)

    Fukuda, Shinzo; Tsuchiya, Yukikazu.

    1979-01-01

    Recently, painting for nuclear power stations is carried out with the paints made domestically, and these paints are tested and judged generally according to the items of performance evaluation decided by the American National Standard Institute. In Japan, there is no standard regarding the paints for nuclear power stations. Painting is very important process, and it is appropriate to introduce quality assurance program into it. In this paper, the contents of ANSI standard concerning the paints and painting for nuclear power stations are explained, and the outline of the painting of heat exchangers carried out in accordance with the quality assurance program in the Tamano Shipyard, Mitsui Shipbuilding and Engineering Co., Ltd., is described. The test items for evaluating the general performance of the paints, the testing method for evaluating the endurance at the time of an accident, the quality assurance for the paints used for the facilities handling radiation and others are explained. Various problems arise when the quality assurance program of ANSI is applied actually to painting. It is difficult to judge the quality of paints and painting with numerical values, and much efforts were required to establish the quality assurance organization. The conditions for painting, the handling of many documents, the measures to unsatisfactory painting and so on caused much difficulties. (Kako, I.)

  16. 40 CFR 60.2635 - What are the operator training and qualification requirements?

    Science.gov (United States)

    2010-07-01

    ...) Combustion controls and monitoring. (v) Operation of air pollution control equipment and factors affecting... Construction On or Before November 30, 1999 Model Rule-Operator Training and Qualification § 60.2635 What are...

  17. 40 CFR 62.14595 - What are the operator training and qualification requirements?

    Science.gov (United States)

    2010-07-01

    ... control equipment and factors affecting performance (where applicable). (vi) Inspection and maintenance of... Commenced Construction On or Before November 30, 1999 Operator Training and Qualification § 62.14595 What...

  18. Integrated Information System for Higher Education Qualifications

    Directory of Open Access Journals (Sweden)

    Catalin Ionut SILVESTRU

    2012-10-01

    Full Text Available In the present article we aim to study thoroughly and detail aspects related to architectures specific for e-learning and management of human resources training interconnected to management of qualifications. In addition, we take into consideration combining e-learning architectures with software in an e-learning system interconnected with the National Registry of Qualifications of Higher Education, in view of developing and information system that correlates educational supply from higher education from Romania with labor market demands through qualifications. The scientific endeavor consists of original architectural solutions to integrate data, systems, processes, services from various sources and to use them in the proposed system. The practical result of the scientific endeavor is represented by design of architectures required for developing an e-learning system interconnected with the National Registry of Qualifications from Romania, which involve in first stage the qualifications provided by higher education. The proposed innovative solution consists in the fact that the proposed information system combines the advantages of content management system (CMS with learning content management system (LCMS and with reusable learning objects (RLO. Thus, the architecture proposed in the research ensures the integration of a content management system with a portal for information, guidance and support in making a professional project. The integration enables correlation of competences with content areas and specific items from various teaching subjects, thus evaluating the usefulness for this registry from learning/educational perspective. Using the proposed information system in enables correlation among qualifications, content of educational program and continuous self-evaluation opportunities, which facilitate monitoring of progress and adjustment of learning content.

  19. Analysis of the extension and reduction method of qualified life used in equipment with ambiental qualification; Analisis del metodo de extension y reduccion de vida calificada utilizado en equipo con calificacion ambiental

    Energy Technology Data Exchange (ETDEWEB)

    Serrano R, M.L. [CNSNS, 03020 Mexico D.F. (Mexico)].e -mail: mlserrano@cnsns.gob.mx

    2005-07-01

    With the purpose of reducing costs of acquisition, maintenance, design, hour-man, dose, production, etc. or by changes in the temperature of service, diverse Nuclear Plants (NP) in the world have been carried out extensions and reductions of life of equipment and/or components related with the safety. The used methods are mainly tests type on equipment or component aged quickly, tests type on equipment or component aged naturally and use of the Arrhenius model with monitoring of temperatures in place. The present article carries out an analysis of the Arrhenius model with monitoring of temperatures in place, which is presented in two variants, equation (1) and (2), since it is the but used by the NP with extension purposes and reduction of qualified life. As back information, it was made one search of investigations, applied to diverse fields of the science that try about the reliability of the results provided by Arrhenius for the aging case. The results of the analysis indicate: I) that this method make uncertainties in some intervals of temperature and 2) which of the two variants it provides data more reliable. (Author)

  20. A system of programs of an automated processing of a map of failures in energy equipment

    Energy Technology Data Exchange (ETDEWEB)

    Gerr, A.D.; Chernysheva, S.K.; Zigangirova, N.E.

    1981-01-01

    Purposeful effects on the factors affecting the reliability of the operation of electric power stations requires reliable data on the level of the reliability of the elements of the system. From 1973, an accumulation of such information has been carried out, and they are being incorporated into a map charting out the failures. In order to increase the effectiveness of the processing of the information contained in them, a system of programs, whose important merits are the necessity of a small operative memory capacity and simplicity of use, is developed.

  1. AGR-1 Data Qualification Interim Report

    International Nuclear Information System (INIS)

    Abbott, Machael

    2009-01-01

    Projects for the very-high-temperature reactor (VHTR) program provide data in support of Nuclear Regulatory Commission licensing of the VHTR. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high temperature and high fluence environments. The VHTR Program has established the NGNP Data Management and Analysis System (NDMAS) to ensure that VHTR data are (1) qualified for use, (2) stored in a readily accessible electronic form, and (3) analyzed to extract useful results. This document focuses on the first NDMAS objective. It describes the data streams associated with the first Advanced Gas Reactor (AGR-1) experiment, the processing of these data within NDMAS, and reports the interim FY09 qualification status of the AGR-1 data to date. Data qualification activities within NDMAS for specific types of data are determined by the data qualification category, which is assigned by the data generator, and include: (1) capture testing, to confirm that the data stored within NDMAS are identical to the raw data supplied, (2) accuracy testing, to confirm that the data are an accurate representation of the system or object being measured, and (3) documentation that the data were collected under an NQA-1 or equivalent QA program. The interim qualification status of the following four data streams is reported in this document: (1) fuel fabrication data, (2) fuel irradiation data, (3) fission product monitoring system (FPMS) data, and (4) Advanced Test Reactor (ATR) operating conditions data. A final report giving the NDMAS qualification status of all AGR-1 data (including cycle 145A) is planned for February 2010

  2. Development of the environmental qualification safety requirement matrix for the containment system of in-service CANDU reactors

    International Nuclear Information System (INIS)

    Chun, R.M.; Low, J.; Sobolewski, J.

    1994-01-01

    Over the last several years, Ontario Hydro Nuclear (OHN) has placed increasing emphasis on environmental qualification (EQ) at its Pickering and Bruce NGS A and B nuclear generating stations (NGSs). The program currently underway (at the time of the conference) builds upon the experience gained from the extensive Darlington NGS EQ experience and from EQ programs conducted by other utilities. Some of the major steps of the OHN EQ program include: defining Safety Requirement Matrices (SRMs), establishing environmental conditions, developing an EQ List, conducting an EQ Assessment and maintaining Operational EQ Assurance during the plant life. The SRM identifies safety related components, their required safety functions and their mission times for each postulated design basis accident (DBA). This is a critical step, as the SRM defines the equipment that requires assurance of EQ and precise requirements must be provided to ensure a cost effective EQ program. This paper describes the development of the SRMs for the containment system of the Bruce stations. The introductory section briefly discusses how the industry has dealt with equipment qualification as it has evolved and the role of the SRMs in the OHN EQ Program. In Section 2, the preparation of the SRM is described along with the applicable ground rules used. The results of the application of the SRM preparation guidelines to the containment system are discussed in Section 3. A summary of the major findings and conclusions is presented. 3 refs., 3 figs

  3. Systematic Model for Validating Equipment Uses in Selected Marketing and Distribution Education Programs. Final Report, February 1, 1980-June 30, 1981.

    Science.gov (United States)

    Gildan, Kate; Buckner, Leroy

    Research was conducted to provide a model for selecting equipment for marketing and distributive education programs that was required for the development of the skills or competencies needed to perform in marketing and distribution occupation. A research of the literature identified both competency statements for three program areas--Fashion…

  4. Qualification of uranium-molybdenum alloy fuel - conclusions of an international workshop

    International Nuclear Information System (INIS)

    Snelgrove, J.L.; Languille, A.

    2000-01-01

    Thirty-one participants representing 21 reactors, fuel developers, fuel fabricators, and fuel reprocessors in 11 countries discussed the requirements for qualification of U-Mo alloy fuel at a workshop held at Argonne National Laboratory on January 17-18, 2000. Consensus was reached that the qualification plans of the U.S. RERTR program and the French U-Mo fuel development program are valid. The items to be addressed during qualification are summarized in the paper. (author)

  5. Equipment support for the implementation of safeguards

    International Nuclear Information System (INIS)

    Arlt, R.; Bosler, G.; Goldfarb, M.; Schanfein, M.; Whichello, J.

    2001-01-01

    Full text: The provision of effective, reliable, and user-friendly equipment needed for the implementation of safeguards is one of the main objectives of the Division of Technical Services (SOTS) in the Department of Safeguards. As an outcome of a review by an independent external consultant firm, the instrumentation sections of the SGTS were reorganized in January 2001 into two new sections, the Section for NDA Systems and Seals (TNS) and Section for Installed Systems (TIE). Each section has 'cradle-to-grave' responsibilities for development, implementation, maintenance, and decommissioning of safeguards instruments and measurement systems. Unattended assay, monitoring and surveillance instruments are the responsibility of TIE while attended nondestructive assay (NDA) instruments and seals are handled by TNS. The principal goals of both sections are to define equipment requirements based on Departmental needs, to coordinate Support Programme tasks concerning development and implementation activities, to provide system engineering of commercial components, manage laboratory and to do field testing and prove system suitability for defined safeguards applications. In addition both sections coordinate equipment and supply needs for the Department, including acquisition, preparation, servicing, installation, commissioning, troubleshooting, maintenance and repair, ensuring their availability when needed. As required, TIE and TNS provide specialized field support to the Operations Divisions. Each section is working to standardize equipment as much as possible and reduce the number of instruments performing the same function. This reduces both inspector and technician training, required parts inventories, and overall life-cycle costs. Development based on User Needs from the Operations Divisions follows a strict quality control program that includes a thorough qualification testing procedure with the last phase being field-testing under actual facility conditions. A

  6. Methodology for qualification of in-service inspection systems for WWER nuclear power plants. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

    International Nuclear Information System (INIS)

    1998-03-01

    Program was initiated by IAEA in 1990 with the aim to assist the countries of Central and Eastern Europe and former Soviet Union in evaluating the safety of their first generation WWER-440/230 nuclear power plants. The main objectives were: to identify major design and operational safety issues; to establish international consensus on priorities for safety improvements; and to provide assistance in the review of the competence and and adequacy of safety improvement programs. The scope was extended in 1992 to include RBMK, WWER-440/312 and WWER-1000 plants in operation and under construction. Integrity of primary circuit is fundamental for the safe operation of any nuclear power plant. In-service inspection (ISI) in general terms and in particular, non-destructive tests (NDT) play a key role in maintaining primary circuit integrity. This report provides a methodology for qualification of ISI systems which might be used by WWER operating countries as a commonly accepted basis for further development of the necessary qualification related infrastructures. It also provides several qualification principles defining the administrative framework needed for the practical implementation of the methodology, a description of the process of qualification of an inspection system, specifying its minimum technical and documentation related requirements, as well as specific requirements with regard to the NDT procedures, equipment and personnel to be qualified and the test specimen to be used in practical trials. Finally, the report suggests an appropriate distribution of responsibilities among all the parties involved in a qualification process, based on international practice

  7. Aircraft impact qualification of RBMK systems and components. Technical report. Rev. 00, May 1999

    International Nuclear Information System (INIS)

    1999-01-01

    In the present report, the problem of qualification procedures of electrical equipment with respect to the dynamic excitation subsequent to an aircraft impact (ACC) on a Nuclear Power Plant (NPP) is approached, within the context of IAEA Benchmark on vulnerability of equipment and structures of RBMK-type NPP against the aircraft impact. After a short description of the main objectives of the work and the relevant area of concern (Chapter 1), the safety related equipment more commonly installed in a NPP are grouped in few classes, according to widely accepted classification criteria and the relevant failure modes are described (Chapter 2). Taking as reference a deeply studied RBMK reactor (Ignalina NPP), an overview of its main characteristics and of the equipment ensemble housed in is given in Chapter 3. An overview of the worldwide most used qualification standards for safety related equipment for NPPs is reported in Chapter 4, and a comparison of the practices used in Europe for the qualification of safety related electrical and I and C equipment is described with special attention to seismic and impact qualification (Chapter 5). In the hypothesis that the equipment to qualify against impact excitation has been already qualified against seismic excitation, the problems relevant to the different nature of earthquake and shock phenomena are listed, together with the main criteria to implement a procedure which, based on standardized shock pulses, could be applied for ACC qualification purposes (Chapter 6). Consequently, a possible ACC qualification procedure is outlined (Chapter 7) and the interface data (data coming from numerical analysis and seismic qualification, to be used for ACC qualification purposes) are listed (Chapter 8). Finally, the main conclusions of the work are described (Chapter 9). The main references are listed in Chapter 10. (author)

  8. Training and qualification of inspectors

    International Nuclear Information System (INIS)

    Aro, I.; Anderson, R.; Ericsson, P.O.; Lee, I.

    1993-01-01

    A total of four workshop breakout sessions were conducted on this subject: one double session and three single sessions. The following discussion describes common points and difference among the countries in the areas of inspector training and qualifications. In most countries there are resident or non-resident site-specific inspectors who have general plant supervision duties. In addition, there are specialized inspectors who visit NPP when requested or according to the scheduled inspection program. Most countries try to recruit experienced personnel. Many countries prefer to have candidates who have extensive plant experience. Some countries do not recruit inspectors from utilities because of potential conflict of interest or credibility reasons. In many countries, the typical training time to become an independent inspector is one year. In some countries an inspector is formally certified after their training period and completion of an examination

  9. French nuclear plant safeguard pump qualification testing: EPEC test loop

    International Nuclear Information System (INIS)

    Guesnon, H.

    1985-01-01

    This paper reviews the specifications to which nuclear power plant safeguard pumps must be qualified, and surveys the qualification methods and program used in France to verify operability of the pump assembly and major pump components. The EPEC test loop is described along with loop capabilities and acheivements up to now. This paper shows, through an example, the Medium Pressure Safety Injection Pump designed for service in 1300 MW nuclear power plants, and the interesting possibilities offered by qualification testing

  10. Lessons learned in testing of Safeguards equipment

    International Nuclear Information System (INIS)

    Pepper, Susan; Farnitano, Michael; Carelli, Joseph

    2001-01-01

    Upgrade Travel Funding' - This subtask provides funding for the upgrade of DIS equipment installed in the field; E.125.3, 'DIS Radiation Field Characterization' - This subtask provides for the procurement by the IAEA of radiation measurement equipment and technical assistance for the characterization of radiation conditions in the locations where DIS will be installed. This will help the IAEA ensure that the design specifications for the equipment are consistent with the location where the instrument will be used; E.125.4, 'DIS Design Limit Testing and Advise to Strengthen IAEA's Current Equipment Qualification Criteria' - Under this subtask, Wyle Laboratories and Quanterion Solutions will conduct SDIS design limit testing, including harsh environmental testing and accelerated aging, to determine the expected lifetime and produce a design limit report to include maximum operating environment vs. design limit analysis. Additionally, this task will include the development of a strengthened environmental qualification test plan and reliability and maintainability definition methodology for all safeguards equipment. The implementation of new equipment by the Department of Safeguards is costly. Expected costs associated with the implementation of equipment include capital costs, training and in some cases travel. The cost is dramatically increased when operational issues arise due to the costs of studying the issues, modifying and upgrading the equipment and additional travel. The U.S. Support Program believes that the IAEA's Division of Safeguards Technical Support (SGTS) must strengthen its equipment-testing program to ensure that the equipment it approves for inspection use is reliable and will not place additional burden on the Department of Safeguards' maintenance and inspection staff. The U.S. Support Program recognizes that SGTS already requires a series of fundamentally important and revealing tests, but we believe that additional tests should be added to the testing

  11. Reaction Qualifications Revisited

    DEFF Research Database (Denmark)

    Lippert-Rasmussen, Kasper

    2009-01-01

    to a person's effectiveness by causing a favourable reaction in customers, co-workers etc. (for short: recipients) - are involved, this assumption is false. Building on work by Wertheimer, Mason, and Miller, this paper proposes an account of the reaction qualifications that count, from the point of view...... preferences, recipients should not respond to the applicant actually hired on the basis of their (the recipients') racial preferences. My account decomposes the meritocratic ideal into four separate norms, one of which applies to recipients rather than to selectors. Finally, it defends the view that reaction...... qualifications based on antimeritocratic reactions, while not unproblematic, are not entirely irrelevant from the point of view of merit. Notably, selectors need not discount them when no one - including the targets of the objectionable preferences - is unfairly disadvantaged. Because not all problematic...

  12. Qualification of conditioning process

    International Nuclear Information System (INIS)

    Wolf, J.

    1989-01-01

    A conditioning process is qualified by the PTB if the execution of pre-treatment and conditioning occurs so that a safe and orderly final storage of the products and waste containers produced can be assumed. All the relevant operating conditions for the plant are laid down by the producer/conditioner of the waste in a handbook. The elements of product inspection by process qualification are shown in tabular form. (DG) [de

  13. Determining the Residual Lifetime of Qualified Electrical and I and C Equipment in Units 5 and 6 of Kozloduy NPP

    International Nuclear Information System (INIS)

    Radoslavov, Biser

    2012-01-01

    The proposed paper clarifies the environmental qualification and residual lifetime of installed equipment and electrical cables in operating WWER 1000 type units 5 and 6 of Kozloduy NPP. The qualification approach is a combination of analyses and tests in consideration of some specific features of WWER equipment. As a result of the study, selected equipment is divided in 26 groups. Qualification groups include similar types of equipment with equal resistance to foreign impacts, analogous critical parts, and same methods of control and estimation of residual lifetime. Qualification protocols were made for each group. (author)

  14. REGULATION OF NATIONAL QUALIFICATIONS SYSTEMS

    Directory of Open Access Journals (Sweden)

    Anna A. Muravyeva

    2014-01-01

    Full Text Available The paper looks into the diverse aspects of qualifications system regulation, designed for balancing the supply and demand in the labor and educational service markets. Both the objects and mechanisms of such regulation are described. Special attention is given to institutions, involved in regulation of qualifications, and their jurisdiction. Another emphasis is on the industry-related regulation of qualifications which proved to be effective both on the national and European level. Such structures were first established on the national levels to regulate the qualifications and ensure their comparability and compatibility, given the economic globalization and growing labor and academic mobility. The author points out the role of the ministries of education and labor in maintaining a steady qualifications system, and outlines the positive experience of Great Britain using the industry councils for continuing development of qualifications system.

  15. Qualification of contractor/consultant instructors

    International Nuclear Information System (INIS)

    Hanson, H.D.

    1985-01-01

    Following a brief discussion of the role of consultant instructors in Public Service Electric and Gas Company's training organization, the qualification process is presented. Consultant instructors are provided with information regarding supervision of the trainees and the instructional process and procedures required. Each individual must have his or her instructional capability, supervisory skills and technical competence verified and documented prior to conducting training independently. Concluding comments describe the overall satisfactory experience with this program

  16. Internationalization of graduate programs in Psychology: profile and qualification goals / A internacionalização dos programas de pós-graduação em Psicologia: perfil e metas de qualificação

    Directory of Open Access Journals (Sweden)

    Anna Carolina Lo Bianco

    2010-01-01

    Full Text Available Internationalization is examined as part of the efforts pursued by graduate courses in Brazil to enhance the possibilities of exchanges with courses abroad which may improve their qualification. Even encompassed by the indisputable phenomenon of globalization, a critical view must be kept over internationalization, especially on its consequences for institutional functioning. Data of 57 Psychology graduate programs regarding academic education and production are analyzed. Conclusions point to the accentuated valorization for publishing in international journals as far as evaluating agencies are concerned. On the other hand, aiming the internationalization, innumerable actions which are presented in a more diversified form in order to follow the sub-areas covered by Psychology in Brazil are observed.

  17. IAEA activities on NPP personnel training and qualification

    International Nuclear Information System (INIS)

    Kossilov, A.

    1998-01-01

    Activities of IAEA concerning training and qualification of NPP personnel consider the availability of sufficient number of competent personnel which is one of the most critical requirements for safe and reliable NPP operation and maintenance. Competence of personnel is essential for reducing the frequency of events connected to human errors and equipment failures. The IAEA Guidebook on Nuclear Power Plant Personnel Training and its Evaluation incorporates the experience gained worldwide and provides recommendations on the use of SAT being the best practice for attaining and maintaining the qualification and competence of NPP personnel and for quality assurance of training

  18. Passive autocatalytic recombiner process features and new status of international qualification

    International Nuclear Information System (INIS)

    Eckardt, Bernd A.; Losch, Norbert

    2010-01-01

    New results of International PAR-Severe Accidents Qualification in frame of EC/IRSN Core Melt Program PHEBUS (with real molten core) are presented. Example Results: AREVA PAR Design: Best performance very fast start-up • highest efficiency absolutely constant hydrogen depletion rates. Others: Some industrial competitors failed. This enveloping real severe accident tests represents the new international PAR qualification standard and finalized the PAR qualification successfully. The design features supports PAR Dual function

  19. Data Qualification guidelines

    International Nuclear Information System (INIS)

    Edwards, T.B.; Shine, E.P.

    1992-01-01

    Data Qualification (DQ) is a formal, technical process whose objective is to affirm that experimental data are suitable for their intended use. Although it is not possible to develop a fixed recipe for the DQ process to cover all test situations, these general guidelines have been developed for the Nuclear Engineering Section to establish a framework for qualifying data from steady-state processing. These guidelines outline the role of the DQ team providing insight into the planning and conducting of the DQ process

  20. The qualification of electrical components and instrumentations relevant to safety; La qualificazione dei componenti elettrici e di strumentazione rilevanti per la sicurezza

    Energy Technology Data Exchange (ETDEWEB)

    Zambardi, F [ENEA - Direzione Sicurezza Nucleare e Protezione Sanitaria, Divisione Sistemi Elettrici e Strumentazione, Rome (Italy)

    1989-03-15

    Systems and components relevant to safety of nuclear power plants must maintain their functional integrity in order to assure accident prevention and mitigation. Redundancy is utilized against random failures, nevertheless care must be taken to avoid common failures in redundant components. Main sources of degradation and common cause failures consist in the aging effects and in the changes of environmental conditions which occur during the plant life and the postulated accidents. These causes of degradation are expected to be especially significant for instrumentation and electrical equipment, which can have a primary role in safety systems. The qualification is the methodology by which component safety requirements can be met against the above mentioned causes of degradation. In this report the connection between the possible, plant conditions and the resulting degradation effects on components is preliminarily addressed. A general characterization of the qualification is then presented. Basis, methods and peculiar aspects are discussed and the qualification by testing is taken into special account. Technical and organizational aspects related to a plant qualification program are also focused. The report ends with a look to the most significant research and development activities. (author)

  1. Industrial Technology Modernization Program. Project 44. Modernize Facility Equipment and Processes. Volume 2. Revision 2. Phase 2

    Science.gov (United States)

    1988-05-01

    not be implemented. A change in foreign exchange rates (which increase the equipment cost) and a reduction in marketing forecast resulted in an...project will not be implemented due to unfavorable changes in foreign exchange rates (which increase the equipment costs) and a reduction in market

  2. High Temperature Materials Interim Data Qualification Report

    International Nuclear Information System (INIS)

    Lybeck, Nancy

    2010-01-01

    Projects for the very high temperature reactor (VHTR) Technology Development Office provide data in support of Nuclear Regulatory Commission licensing of the VHTR. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high temperature and high fluence environments. The VHTR program has established the NGNP Data Management and Analysis System (NDMAS) to ensure that VHTR data are qualified for use, stored in a readily accessible electronic form, and analyzed to extract useful results. This document focuses on the first NDMAS objective. It describes the High Temperature Materials characterization data stream, the processing of these data within NDMAS, and reports the interim FY2010 qualification status of the data. Data qualification activities within NDMAS for specific types of data are determined by the data qualification category assigned by the data generator. The High Temperature Materials data are being collected under NQA-1 guidelines, and will be qualified data. For NQA-1 qualified data, the qualification activities include: (1) capture testing, to confirm that the data stored within NDMAS are identical to the raw data supplied, (2) accuracy testing to confirm that the data are an accurate representation of the system or object being measured, and (3) documenting that the data were collected under an NQA-1 or equivalent Quality Assurance program. Currently, data from two test series within the High Temperature Materials data stream have been entered into the NDMAS vault: (1) Tensile Tests for Sm (i.e., Allowable Stress) Confirmatory Testing - 1,403,994 records have been inserted into the NDMAS database. Capture testing is in process. (2) Creep-Fatigue Testing to Support Determination of Creep-Fatigue Interaction Diagram - 918,854 records have been processed and inserted into the NDMAS database. Capture testing is in process.

  3. Qualification and training of quality assurance personnel

    International Nuclear Information System (INIS)

    Ribeiro da Costa, J.

    1980-01-01

    Introduction. Qualification and certification: definitions; approach of the problem. A first attempt for its solutions. The 'sample' course; results and conclusions. Planning a comprehensive program: results. Analysis and preliminary conclusions. Absorption of the know-how and planning further programs for training. Development and updating the general training course with the introduction of German experience - summary of results. General planning of a training course for quality and reliability are as for the next courses. Evaluation, grading and final results awarded to participants, as followed in QA-Training courses - certification. Future trends (tentative) - conclusions. (orig./RW)

  4. IEEE Std 382-1985: IEEE standard for qualification of actuators for power operated valve assemblies with safety-related functions for nuclear power plants

    International Nuclear Information System (INIS)

    Anon.

    1992-01-01

    This standard describes the qualification of all types of power-driven valve actuators, including damper actuators, for safety-related functions in nuclear power generating stations. This standard may also be used to separately qualify actuator components. This standard establishes the minimum requirements for, and guidance regarding, the methods and procedures for qualification of power-driven valve actuators with safety-related functions Part I describes the qualification process. Part II describes the standard qualification cases and their environmental parameters for the usual locations of safety-related equipment in a nuclear generating station. Part III describes the qualification tests outlined in 6.3.3

  5. Survey of NDT techniques, services, qualifications and certification of NDT personnel-preliminary results

    International Nuclear Information System (INIS)

    Aleta, C.R.; Kinilitan, V.E.; Lailo, R.M.

    1987-01-01

    This paper presented the results of a survey conducted to determine the profile of the NDT industry including its problems. A questionnaire designed in three parts 1) present practices on qualification and certification, 2) NDT equipment and 3) services and problems in NDT. Of the 36 firms contacted only 20 responded. Results indicated the following: a) most firms are engaged in four (4) main techniques, RT, UT, MT and PT. Only 2 indicated capability of ET. b) level III personnel are relatively few in number, c) most firms allow the ASNT recommendation as a basis for their qualifications and certification and are in favor of standardization of the qualification and certification process and supportive of a national center for training of NDT personnel and d) most firms perceived the lack of adequate repair/maintenance skills/facilities, followed by high cost of equipment and the lack of national standard for qualification and certification. (ELC)

  6. Strategy for Qualification of the Plutonium Immobilized Form

    International Nuclear Information System (INIS)

    Marra, J.C.; Marra, S.L.; Bibler, N.E.; Strachan, D.M.; Shaw, H.F.

    1998-01-01

    In order to dispose of a radioactive waste form in a federal high- level waste repository, a waste form qualification strategy and program must be developed. The waste form qualification program must include the acceptance specifications for the product, show how compliance with these specifications will be met, and then demonstrate compliance. An important element of this program is developing a measure to demonstrate product consistency. For the can- in-canister option, waste form qualification is needed not only for the Pu immobilized form but also for the high-level waste glass canister containing the Pu waste form. The latter will require close interaction and coordination with the U.S. Department of Energy - Office of Environmental Management (DOE-EM) who, through their contractor at the Savannah River Site (SRS), is the producer of the high-level waste form at the Defense Waste Processing Facility (DWPF). In this paper a waste form qualification strategy for the plutonium ceramic form is described that utilizes, as much as possible, the qualification strategy successfully used for vitrified high-level waste

  7. The Inspection Process of the Army Reset Program for Equipment for Units Returning from Operation Iraqi Freedom

    National Research Council Canada - National Science Library

    2008-01-01

    The subject of this report directly applies to the work of DoD civilian and military personnel responsible for the reset of equipment provided to the warfighter deployed in support of Operation Iraqi Freedom...

  8. Qualification standard for photovoltaic concentrator modules

    Energy Technology Data Exchange (ETDEWEB)

    McConnell, R.; Kurtz, S.; Bottenberg, W. R.; Hammond, R.; Jochums, S. W.; McDanal, A. J.; Roubideaux, D.; Whitaker, C.; Wohlgemuth, J.

    2000-05-05

    The paper describes a proposed qualification standard for photovoltaic concentrator modules. The standard's purpose is to provide stress tests and procedures to identify any component weakness in photovoltaic concentrator modules intended for power generation applications. If no weaknesses are identified during qualification, both the manufacturer and the customer can expect a more reliable product. The qualification test program for the standard includes thermal cycles, humidity-freeze cycles, water spray, off-axis beam damage, hail impact, hot-spot endurance, as well as electrical tests for performance, ground continuity, isolation, wet insulation resistance, and bypass diodes. Because concentrator module performance can not be verified using solar simulator and reference cell procedures suitable for flat-plate modules, the standard specifies an outdoor I-V test analysis allowing a performance comparison before and after a test procedure. Two options to this complex analysis are the use of a reference concentrator module for side-by-side outdoor comparison with modules undergoing various tests and a dark I-V performance check.

  9. 14 CFR 91.1089 - Qualifications: Check pilots (aircraft) and check pilots (simulator).

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 2 2010-01-01 2010-01-01 false Qualifications: Check pilots (aircraft) and check pilots (simulator). 91.1089 Section 91.1089 Aeronautics and Space FEDERAL AVIATION ADMINISTRATION... RULES Fractional Ownership Operations Program Management § 91.1089 Qualifications: Check pilots...

  10. Environmental data qualification system

    International Nuclear Information System (INIS)

    Hester, O.V.; Groh, M.R.

    1989-01-01

    The Integrated Environmental Data Management System (IEDMS) is a PC-based system that can support environmental investigations from their design stage and throughout the duration of the study. The system integrates data originating from the Sampling and Analysis Plan, field data and analytical findings. The IEDMS automated features include sampling guidance forms, barcoded sample labels and tags, field and analytical forms reproduction, sample tracking, analytical data qualification, completeness reports, and results and QC data reporting. The IEDMS has extensive automated capabilities that support a systematic and comprehensive process for performing quality assessment of EPA-CLP chemical analyses data. One product of this process is a unique and extremely useful tabular presentation of the data. One table contains the complete set of results and QC data included on the CLP data forms while presenting the information consistent with the chronology in which the analysis was performed. 3 refs., 1 fig

  11. IEEE Standard for qualification of Class 1E lead storage batteries for nuclear power generating stations

    International Nuclear Information System (INIS)

    Anon.

    1980-01-01

    This document describes qualification methods for Class 1E lead storage batteries and racks to be used in nuclear power generating stations outside of primary containment. Qualification required in ANSI/IEEE Std 279-1979 and IEEE Std 308-1978, can be demonstrated by using the procedures provided in this Standard in accordance with IEEE Std 323-1974. Battery sizing, maintenance, capacity testing, installation, charging equipment and consideration of other types batteries are beyond the scope of this Standard

  12. Nuclear safety review for qualification of class 1E motor inside containment for nuclear power stations

    International Nuclear Information System (INIS)

    Li Shixin; Wu Qi; Zhang Yunbo; Wu Caixia

    2013-01-01

    In nuclear power plants with pressurized water reactors, the review for class 1E motor inside containment qualification process and documents is an important aspect of nuclear safety equipment review, and the reviewers should make evaluations for the qualification test results in terms of the compliance with standard and regulation, and the consistency with inside containment environment. Firstly, this paper introduces the qualification test of class 1E motor inside containment for nuclear power generating stations, such as aging test and design-basis-event test. Second, there is a discussion about typical problems of review. At last, comparison of IEEE334 with RCC-E is conducted and explored. (authors)

  13. Contributions to the research programs in nuclear and industrial electronics, domestic production of instrumentation, safety and control systems and equipment for nuclear reactors and auxiliary installations

    International Nuclear Information System (INIS)

    Talpariu, C; Talpariu, J.; Matei, C.

    2001-01-01

    Domestic production of component system and equipment for the control and safety of nuclear facilities was one of the priority objective of the Nuclear Research Institute Pitesti. The problems addressed were particularly related to design and production of analog and digital equipment for measurements, triggering and display of the values of process parameters as well as to regulating complex functions of this equipment. Associated to this effort were the research works concerning: - reliability and in-service life-time of the electronic components and equipment in the safety and control systems for nuclear processes; - radiation endurance of industrial electronic components; utilization of whirling currents in calandria tube testing; - expert systems and applications in nuclear reactor control and safety; design and testing methods of process real time software packages for safety in control critical systems for nuclear domain. There are presented characteristics of the following equipment: 1. amplifier for ionization chambers with triggering comparator circuits for the CANDU 600 reactor shut down system; 2. amplifier for ionization chambers without triggering comparator circuits for power regulating system; 3. safety and regulating computerized system for C9 and C5 cans; 4. acquisition system for dosimetric data in nuclear facilities; 5. program able digital comparator for the reactor shut down system; 6. stationary gamma areal monitors for CANDU 600 reactors and other nuclear facilities

  14. Equipment considerations

    International Nuclear Information System (INIS)

    Anon.

    1992-01-01

    Trace or ultratrace analyses require that the HPLC equipment used, including the detector, be optimal for such determinations. HPLC detectors are discussed at length in Chapter 4; discussion here is limited to the rest of the equipment. In general, commercial equipment is adequate for trace analysis; however, as the authors approach ultratrace analysis, it becomes very important to examine the equipment thoroughly and optimize it, where possible. For this reason they will review the equipment commonly used in HPLC and discuss the optimization steps. Detectability in HPLC is influenced by two factors (1): (a) baseline noise or other interferences that lead to errors in assigning the baseline absorbance; (b) peak width. 87 refs

  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. Optimized qualification protocol on particle cleanliness for EUV mask infrastructure

    Science.gov (United States)

    van der Donck, J. C. J.; Stortelder, J. K.; Derksen, G. B.

    2011-11-01

    With the market introduction of the NXE:3100, Extreme Ultra Violet Lithography (EUVL) enters a new stage. Now infrastructure in the wafer fabs must be prepared for new processes and new materials. Especially the infrastructure for masks poses a challenge. Because of the absence of a pellicle reticle front sides are exceptionally vulnerable to particles. It was also shown that particles on the backside of a reticle may cause tool down time. These effects set extreme requirements to the cleanliness level of the fab infrastructure for EUV masks. The cost of EUV masks justifies the use of equipment that is qualified on particle cleanliness. Until now equipment qualification on particle cleanliness have not been carried out with statistically based qualification procedures. Since we are dealing with extreme clean equipment the number of observed particles is expected to be very low. These particle levels can only be measured by repetitively cycling a mask substrate in the equipment. Recent work in the EUV AD-tool presents data on added particles during load/unload cycles, reported as number of Particles per Reticle Pass (PRP). In the interpretation of the data, variation by deposition statistics is not taken into account. In measurements with low numbers of added particles the standard deviation in PRP number can be large. An additional issue is that particles which are added in the routing outside the equipment may have a large impact on the testing result. The number mismatch between a single handling step outside the tool and the multiple cycling in the equipment makes accuracy of measurements rather complex. The low number of expected particles, the large variation in results and the combined effect of added particles inside and outside the equipment justifies putting good effort in making a test plan. Without a proper statistical background, tests may not be suitable for proving that equipment qualifies for the limiting cleanliness levels. Other risks are that a

  17. Problems associated with accelerated thermal aging of electrical equipment

    International Nuclear Information System (INIS)

    Isgro, J.R.

    1984-01-01

    This paper discusses the potential problems that may be experienced when accounting for aging mechanisms in organic polymers when utilizing accelerated thermal aging techniques for electrical equipment qualification. Included are discussions of actual experiences and problems encountered in the qualification of electrical and electronic equipment for a complete nuclear power plant. The wide variety of approaches to thermal accelerated aging by various manufacturers of diverse equipment types provides depth to the discussion. A description of how to account for aging mechanisms is also presented

  18. 77 FR 59345 - Environmental Qualifications of Electrical Equipment

    Science.gov (United States)

    2012-09-27

    .... ADDRESSES: Please refer to Docket ID NRC-2012-0177 when contacting the NRC about the availability of... intrusion. It was generally assumed (petitioner Blanch included) that these containers would remain dry... ``[t]he aforementioned `high probability of impairment' that helped focus the selection of cable...

  19. Radiation data definitions and compilation for equipment qualification data bank

    International Nuclear Information System (INIS)

    Bouquet, F.L.; Winslow, J.W.

    1986-01-01

    Dose definitions, physical properties, mechanical properties, electrical properties, and particle definitions are listed for insulators and dielectrics, elastomeric seals and gaskets, lubricants, adhesives, and coatings

  20. Impact of Binding Study Advice on Study Behavior and Pre-University Education Qualification Factors in a Problem-Based Psychology Bachelor Program

    Science.gov (United States)

    de Koning, Björn B.; Loyens, Sofie M. M.; Rikers, Remy M. J. P.; Smeets, Guus; van der Molen, Henk T.

    2014-01-01

    In the Netherlands, university programs increasingly use the binding study advice (BSA) to select students after the first year. Students with insufficient progress after the first year and who therefore do not conform to pre-defined BSA norms have to quit their program. This study investigated whether the introduction of the BSA is associated…

  1. Policy analysis of the budget used in training program for reducing lower back pain among heavy equipment operators in the construction industry: System dynamics approach

    Science.gov (United States)

    Vitharana, V. H. P.; Chinda, T.

    2018-04-01

    Lower back pain (LBP), prevalence is high among the heavy equipment operators leading to high compensation cost in the construction industry. It is found that proper training program assists in reducing chances of having LBP. This study, therefore aims to examine different safety related budget available to support LBP related training program for different age group workers, utilizing system dynamics modeling approach. The simulation results show that at least 2.5% of the total budget must be allocated in the safety and health budget to reduce the chances of having LBP cases.

  2. NFC based Inspection and Qualification Management (NIQM) System Preventing Counterfeit and Fraudulent Item

    International Nuclear Information System (INIS)

    Chang, Choong Koo; Kim, Young Joo

    2013-01-01

    Design, manufacturing, fabrication, transportation and installation of the devices and equipment for nuclear power plants shall be conducted under the thorough quality assurance program for the nuclear safety. However, from late in the 1980s, NRC began to issue a number of communications alerting licenses to issues involving counterfeit and fraudulent items. A number of incidents identified by the NRC in the 1980s and 1990s catalyzed the US nuclear industry to adopt standard precautions to guard against counterfeit items. The purpose of this paper is to develop the NFC (Near Field Communication) based Inspection and Qualification Management(NIQM) system preventing counterfeit and fraudulent items. NFC is one of the latest wireless communication technologies. As a short-range wireless connectivity technology, NFC offers safe-yet simple and intuitive-communication between electronic devices. As described above, NFC technology can be applied to the inspection and qualification management system very effectively to prevent counterfeit and fraudulent items. In addition, NIQM system can use existing data and information through the interface with legacy system

  3. NFC based Inspection and Qualification Management (NIQM) System Preventing Counterfeit and Fraudulent Item

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Choong Koo; Kim, Young Joo [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2013-10-15

    Design, manufacturing, fabrication, transportation and installation of the devices and equipment for nuclear power plants shall be conducted under the thorough quality assurance program for the nuclear safety. However, from late in the 1980s, NRC began to issue a number of communications alerting licenses to issues involving counterfeit and fraudulent items. A number of incidents identified by the NRC in the 1980s and 1990s catalyzed the US nuclear industry to adopt standard precautions to guard against counterfeit items. The purpose of this paper is to develop the NFC (Near Field Communication) based Inspection and Qualification Management(NIQM) system preventing counterfeit and fraudulent items. NFC is one of the latest wireless communication technologies. As a short-range wireless connectivity technology, NFC offers safe-yet simple and intuitive-communication between electronic devices. As described above, NFC technology can be applied to the inspection and qualification management system very effectively to prevent counterfeit and fraudulent items. In addition, NIQM system can use existing data and information through the interface with legacy system.

  4. Qualification test and analysis report: solar collectors

    Energy Technology Data Exchange (ETDEWEB)

    1978-12-01

    Test results show that the Owens-Illinois Sunpak/sup TM/ Model SEC 601 air-cooled collector meets the national standards and codes as defined in the Subsystem Performance Specification and Verification Plan of NASA/MSFC Contract NAS8-32259, dated October 28, 1976. The architectural and engineering firm of Smith, Hinchman and Grylls, Detroit, Michigan, acted in the capacity of the independent certification agency. The program calls for the development, fabrication, qualification and delivery of an air-liquid solar collector for solar heating, combined heating and cooling, and/or hot water systems.

  5. The application of NISA II FEM package in seismic qualification of small class IE electric motors

    International Nuclear Information System (INIS)

    Fancev, T.; Saban, I.; Grgic, D.

    1995-01-01

    According to the IEEE standards 323/1974 and 344/1975, seismic qualification of class IE equipment is appropriate combination of test and analysis methods. Complex equipment and assemblies are usually tested through seismic testing. The analysis is recommended for simple equipment that can be easily modeled to correctly predict its response. This article deals with the application of NISA II FEM package in 3D FE modeling and mode shape calculations of small power low voltage electric motors. (author)

  6. Accreditation of qualification testing organizations: the industry viewpoint

    International Nuclear Information System (INIS)

    Roby, A.

    1983-01-01

    This paper presents the industry viewpoint on the program for the Accreditation of Qualification Testing Organizations, which has been proposed for rulemaking by the Nuclear Regulatory Commission. The IEEE has agreed to establish the program content, and would administer its requirements in accordance with an agreement between the NRC and IEEE of September 30th, 1981. Presented in this paper is the industry perspective, developed and prepared through the AIF, identifying the serious concerns which the accreditation program has raised. Discussed are the disadvantages of the program and those present benefits which would be lost if the program was adopted. The value of greater emphasis on current regulation to improve the qualification process is presented and the paper details areas where the NRC proposals do not provide adequate justification for the accreditation program

  7. Thermal Analysis for Environmental Qualification of Kori Nuclear power plant unit 3 and 4

    International Nuclear Information System (INIS)

    Seo, Kwi Hyun; Byun, Choong Sup; Song, Dong Soo

    2006-01-01

    This paper shows the temperature profiles of safety related electrical equipment exposed to MSLB inside containment. It must be demonstrated that the LOCA qualification conditions exceed or are equivalent to the maximum calculated MSLB conditions. COPATTA as Bechtel's vendor code is used for the containment pressure and temperature prediction in power uprating project for Kori 3,4 and Yonggwang 1,2 nuclear power plants(NPPs). However, CONTEMPT-LT/028 is used for calculating the containment pressure and temperatures in equipment qualification project for the same NPPs. Power uprating code that is, COPATTA benchmarking study performed in six equipment at saturation temperature and surface temperature. Specially, thermal analysis carefully investigate that view point environmental qualification and NUREG- 0588 be mentioned in regard to safety-related heat sink it boundary condition or geometry information

  8. Thermal Analysis for Environmental Qualification of Kori Nuclear power plant unit 3 and 4

    Energy Technology Data Exchange (ETDEWEB)

    Seo, Kwi Hyun [ENERGEO Inc., Sungnam (Korea, Republic of); Byun, Choong Sup; Song, Dong Soo [KEPRI, Taejon (Korea, Republic of)

    2006-07-01

    This paper shows the temperature profiles of safety related electrical equipment exposed to MSLB inside containment. It must be demonstrated that the LOCA qualification conditions exceed or are equivalent to the maximum calculated MSLB conditions. COPATTA as Bechtel's vendor code is used for the containment pressure and temperature prediction in power uprating project for Kori 3,4 and Yonggwang 1,2 nuclear power plants(NPPs). However, CONTEMPT-LT/028 is used for calculating the containment pressure and temperatures in equipment qualification project for the same NPPs. Power uprating code that is, COPATTA benchmarking study performed in six equipment at saturation temperature and surface temperature. Specially, thermal analysis carefully investigate that view point environmental qualification and NUREG- 0588 be mentioned in regard to safety-related heat sink it boundary condition or geometry information.

  9. Development and Qualification of ATV Propulsion Assemblies

    Science.gov (United States)

    Riehle, M.; Jost, R.

    2002-01-01

    qualification will be presented starting from components and assemblies up to sub- system. Exemplarily, the path of the 200N shall be described in more detail since requirements of various kinds are to be applied here. This thruster is used in a total of 28 engines located on 4 thruster cluster assemblies on the bottom and 4 on the front of the space craft delivering steady state thrust as well as impulse bit to the ATV and can be used also as backup for the main thrusters. Safety and thus redundancy is one of the major driver for the design. As a first step i.e. the thrusters are equipped with measures to detect malfunctions and problems by continuous measuring chamber temperature and combustion pressure. The layout of the thruster clusters arrangement in combination with control electronics are such are such that multiple independent branches are controlling the system by which each of them could to fulfil the whole operational objectives. The thruster clusters are also affected by most of the environmental constraints that require careful thermal or mechanical design. For example severe shock loads induced by the stage separation nearby as well as meteorites and debris have to be taken into account for mechanical design. Or large transient pressure spikes and water hammer caused by simultaneous operation of thrusters have to be considered for hydraulic design. As well as extreme conditions for thermal design facing high thermal loads both radiation and conductive during thruster firing and sun exposure of the externally mounted assembly as well as low heater budget and I/F flux limitations when exposed to deep space during long phases. Intensive test programs have been carried out or are under preparation as well as complementary numerical analysis are completing and supporting each step of the development. The paper will describe those design and qualification activities as well as the results as far as available to that time in order to give an overview of the status of

  10. Inspection of pressurised nuclear equipment by certified organizations

    International Nuclear Information System (INIS)

    Marez, Y.

    2010-01-01

    The A.Q.U.A.P. is a technical association created on the 17 october 1978 grouping control organisms that define methodologies in order to apply the same procedures among their customers. It writes cards to interpret the regulation for organisms, operators and manufacturers. The areas covered by the A.Q.U.A.P. works concern the conformity evaluation of new pressure vessels, qualification of qualification of welding procedures and permanent assemblies and the qualification of the personnel realizing these assemblies, the follow up of the equipment in service. (N.C.)

  11. 78 FR 25916 - Authorization of Radiofrequency Equipment

    Science.gov (United States)

    2013-05-03

    ...] Authorization of Radiofrequency Equipment AGENCY: Federal Communications Commission. ACTION: Proposed rule... bodies, and measurement procedures used to determine RF equipment compliance. The Commission believes... Commission is responsible for an equipment authorization program for radiofrequency (RF) devices under part 2...

  12. 10 CFR 26.85 - Collector qualifications and responsibilities.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Collector qualifications and responsibilities. 26.85 Section 26.85 Energy NUCLEAR REGULATORY COMMISSION FITNESS FOR DUTY PROGRAMS Collecting Specimens for... reports, if any; results of tests to establish employee competency for the position he or she holds...

  13. Qualification tests of materials for spallation neutron sources

    International Nuclear Information System (INIS)

    Sommer, W.F.; Maloy, S.; Wechsler, M.S.

    1997-01-01

    Several laboratories will take part in an extensive materials qualification program that includes irradiation in the proton beam and neutron field available at the Los Alamos Spallation Radiation Damage Facility (LASREF). A number of candidate materials will be exposed to prototypic spallation producing particle radiation. Studies of corrosion-related phenomena and the mitigation of these effects will also be accomplished

  14. 78 FR 39825 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2013-07-02

    ...-2013-0018] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor... diagnosis of diabetes mellitus currently requiring insulin for control'' [49 CFR 391.41(b)(3)]. FMCSA... Congress on the Feasibility of a Program to Qualify Individuals with Insulin-Treated Diabetes Mellitus to...

  15. Chapter 9. Personnel qualification and training

    International Nuclear Information System (INIS)

    2001-01-01

    The overall training system and the development of projects for training of all categories of NPP V-1, NPP V-2 Bohunice, SE-VYZ and NPP Mochovce staff were the subject of Nuclear Regulatory Authority of the Slovak Republic (UJD) attention. During 2000, the following inspections were carried out on nuclear personnel training: (a) NPP Bohunice: an inspection focused on compliance with requirements for staff qualifications and compliance with the prescribed training of Bohunice plant staff ; (b) NPP Mochovce: an inspection focused on compliance with the requirements for staff qualifications and compliance with the prescribed training of NPP Mochovce staff; an inspection focused on verifying the simulator aided training; an inspection focused on checking the preparedness of NPP Mochovce operation and technical personnel for NPP Mochovce Unit 2 operation; (c) Technology for treatment and conditioning of radioactive waste Bohunice (BSC): an inspection focused on compliance with the requirements for staff qualifications and compliance with the prescribed training of SE-VYZ staff; VUJE Trnava: verification of technical equipment and professional skills of VUJE Trnava staff and tasks arising out of the 'Authorisation on nuclear installation staff training'. Examinations of selected personnel were scheduled according to the plan of examining committee meetings. For each examined person written tests are generated by the computer from the database of test questions at the Training Centre of VUJE Trnava for individual positions - categories of selected staff of NPP V-1 and NPP V-2 Bohunice and NPP Mochovce so that the examination questions both in written and oral part equally cover individual facilities and regimes of operation of NPP. The database is continuously updated, thereby containing new questions resulting from the recent changes carried out at NPPs. A part of the examination in case of promotion to a higher position is the practical part, which is conducted under

  16. Hanford Waste Vitrification Plant Quality Assurance Program description for high-level waste form development and qualification. Revision 3, Part 2

    Energy Technology Data Exchange (ETDEWEB)

    1993-08-01

    The Hanford Waste Vitrification Plant Project has been established to convert the high-level radioactive waste associated with nuclear defense production at the Hanford Site into a waste form suitable for disposal in a deep geologic repository. The Hanford Waste Vitrification Plant will mix processed radioactive waste with borosilicate material, then heat the mixture to its melting point (vitrification) to forin a glass-like substance that traps the radionuclides in the glass matrix upon cooling. The Hanford Waste Vitrification Plant Quality Assurance Program has been established to support the mission of the Hanford Waste Vitrification Plant. This Quality Assurance Program Description has been written to document the Hanford Waste Vitrification Plant Quality Assurance Program.

  17. Qualification Test for Korean Mockups of ITER Blanket First Wall

    International Nuclear Information System (INIS)

    Kim, S. K.; Lee, D. W.; Bae, Y. D.; Hong, B. G.; Jung, H. K.; Jung, Y. I.; Park, J. Y.; Jeong, Y. H.; Choi, B. K.; Kim, B. Y.

    2009-01-01

    ITER First Wall (FW) includes the beryllium armor tiles joined to CuCrZr heat sink with stainless steel cooling tubes. This first wall panels are one of the critical components in the ITER machine with the surface heat flux of 0.5 MW/m 2 or above. So qualification program needs to be performed with the goal to qualify the joining technologies required for the ITER First Wall. Based on the results of tests, the acceptance of the developed joining technologies will be established. The results of this qualification test will affect the final selection of the manufacturers for the ITER First Wall

  18. AZ-101 Mixer Pump Test Qualification Test Procedures (QTP)

    International Nuclear Information System (INIS)

    THOMAS, W.K.

    2000-01-01

    Describes the Qualification test procedure for the AZ-101 Mixer Pump Data Acquisition System (DAS). The purpose of this Qualification Test Procedure (QTP) is to confirm that the AZ-101 Mixer Pump System has been properly programmed and hardware configured correctly. This QTP will test the software setpoints for the alarms and also check the wiring configuration from the SIMcart to the HMI. An Acceptance Test Procedure (ATP), similar to this QTP will be performed to test field devices and connections from the field

  19. Status of safety-related qualification and design verification and support programs in support of HTGR PSARs. Biannual report for period ending January 31, 1975

    International Nuclear Information System (INIS)

    Tully, G.R. Jr.; Stiehl, G.L. Jr.

    1975-01-01

    Programs reported are core seismic studies, core support posts, primary coolant moisture monitor, moisture monitor compressor, control rod system, orifice and drive mechanism, reserve shutdown system, main loop coolant shutoff valve, auxiliary loop coolant shutoff valve, core auxiliary heat exchanger, auxiliary loop coolant circulator assembly, auxiliary loop coolant circulator motor speed controls, PPS electronic modules and main loop helium circulator. (U.S.)

  20. Open-Source RTOS Space Qualification: An RTEMS Case Study

    Science.gov (United States)

    Zemerick, Scott

    2017-01-01

    NASA space-qualification of reusable off-the-shelf real-time operating systems (RTOSs) remains elusive due to several factors notably (1) The diverse nature of RTOSs utilized across NASA, (2) No single NASA space-qualification criteria, lack of verification and validation (V&V) analysis, or test beds, and (3) different RTOS heritages, specifically open-source RTOSs and closed vendor-provided RTOSs. As a leader in simulation test beds, the NASA IV&V Program is poised to help jump-start and lead the space-qualification effort of the open source Real-Time Executive for Multiprocessor Systems (RTEMS) RTOS. RTEMS, as a case-study, can be utilized as an example of how to qualify all RTOSs, particularly the reusable non-commercial (open-source) ones that are gaining usage and popularity across NASA. Qualification will improve the overall safety and mission assurance of RTOSs for NASA-agency wide usage. NASA's involvement in space-qualification of an open-source RTOS such as RTEMS will drive the RTOS industry toward a more qualified and mature open-source RTOS product.

  1. Development of KSC program for investigating and generating field failure rates. Reliability handbook for ground support equipment

    Science.gov (United States)

    Bloomquist, C. E.; Kallmeyer, R. H.

    1972-01-01

    Field failure rates and confidence factors are presented for 88 identifiable components of the ground support equipment at the John F. Kennedy Space Center. For most of these, supplementary information regarding failure mode and cause is tabulated. Complete reliability assessments are included for three systems, eight subsystems, and nine generic piece-part classifications. Procedures for updating or augmenting the reliability results are also included.

  2. Procurement strategic analysis of nuclear safety equipment

    International Nuclear Information System (INIS)

    Wu Caixia; Yang Haifeng; Li Xiaoyang; Li Shixin

    2013-01-01

    The nuclear power development plan in China puts forward a challenge on procurement of nuclear safety equipment. Based on the characteristics of the procurement of nuclear safety equipment, requirements are raised for procurement process, including further clarification of equipment technical specification, establishment and improvement of the expert database of the nuclear power industry, adoption of more reasonable evaluation method and establishment of a unified platform for nuclear power plants to procure nuclear safety equipment. This paper makes recommendation of procurement strategy for nuclear power production enterprises from following aspects, making a plan of procurement progress, dividing procurement packages rationally, establishing supplier database through qualification review and implementing classified management, promoting localization process of key equipment continually and further improving the system and mechanism of procurement of nuclear safety equipment. (authors)

  3. Earthquake experience and seismic qualification by indirect methods in nuclear installations

    International Nuclear Information System (INIS)

    2003-01-01

    In recent years, many operational nuclear power plants around the world have conducted seismic re-evaluation programmes either as part of a review of seismic hazards or to comply with best international nuclear safety practices. In this connection, Member States have called on the IAEA to carry out several seismic review missions at their plants, primarily those of WWER and RBMK design. One of the critical safety issues that arose during these missions was that of seismic qualification (determination of fitness for service) of already installed plant distribution systems, equipment and components. The qualification of new components, equipment and distribution systems cannot be replicated for equipment that is already installed and operational in plants, as this process is neither feasible nor appropriate. For this reason, seismic safety experts have developed new procedures for the qualification of installed equipment: these procedures seek to demonstrate that installed equipment, through a process of comparison with new equipment, is apt for service. However, these procedures require large sets of criteria and qualification databases and call for the use of engineering judgement and experience, all of which open the door to wide margins of interpretation. In order to guarantee a sound technical basis for the qualification of in-plant equipment, currently applied to 70% to 80% of all plant equipment, the regulatory review of this type of qualification process calls for a detailed assessment of the technical procedures applied. Such an assessment is the first step towards eliminating the risk of large differences in qualification results between different plants, operators and countries, and guaranteeing the reliability of seismic re-evaluation programmes. Bearing this in mind, in 1999, the IAEA convened a seminar and technical meeting on seismic qualification under the auspices of the IAEA Technical Co-operation programme. Altogether 66 senior experts attended the

  4. Medicare program; replacement of reasonable charge methodology by fee schedules for parenteral and enteral nutrients, equipment, and supplies. Final rule.

    Science.gov (United States)

    2001-08-28

    This final rule implements fee schedules for payment of parenteral and enteral nutrition (PEN) items and services furnished under the prosthetic device benefit, defined in section 1861(s)(8) of the Social Security Act. The authority for establishing these fee schedules is provided by the Balanced Budget Act of 1997, which amended the Social Security Act at section 1842(s). Section 1842(s) of the Social Security Act specifies that statewide or other area wide fee schedules may be implemented for the following items and services still subject to the reasonable charge payment methodology: medical supplies; home dialysis supplies and equipment; therapeutic shoes; parenteral and enteral nutrients, equipment, and supplies; electromyogram devices; salivation devices; blood products; and transfusion medicine. This final rule describes changes made to the proposed fee schedule payment methodology for these items and services and provides that the fee schedules for PEN items and services are effective for all covered items and services furnished on or after January 1, 2002. Fee schedules will not be implemented for electromyogram devices and salivation devices at this time since these items are not covered by Medicare. In addition, fee schedules will not be implemented for medical supplies, home dialysis supplies and equipment, therapeutic shoes, blood products, and transfusion medicine at this time since the data required to establish these fee schedules are inadequate.

  5. Advanced qualification techniques

    International Nuclear Information System (INIS)

    Winokur, P.S.; Shaneyfelt, M.R.; Meisenheimer, T.L.; Fleetwood, D.M.

    1993-01-01

    This paper demonstrates use of the Qualified Manufacturers List (QML) methodology to qualify commercial and military microelectronics for use in space applications. QML ''builds in'' the hardness of product through statistical process control (SPC) of technology parameters relevant to the radiation response, test structure to integrated circuit (IC) correlations, and techniques for extrapolating laboratory test results to low-dose-rate space scenarios. Each of these elements is demonstrated and shown to be a cost-effective alternative to expensive end-of-line IC testing. Several examples of test structured-IC correlations are provided and recent work on complications arising from transistor scaling and geometry is discussed. The use of a 10-keV x-ray wafer-level test system to support SPC and establish ''process capability'' is illustrated and a comparison of 10-keV x-ray and Co 60 gamma irradiations is provided for a wide range of CMOS technologies. The x-ray tester is shown to be cost-effective and its use in lot acceptance/qualification is recommended. Finally, a comparison is provided between MIL-STD-883D, Test Method 1019.4, which governs the testing of packaged semiconductor microcircuits in the DoD, and ESA/SSC Basic Specification No. 22900, Europe's Total Dose Steady-State Irradiation Test Method. Test Method 1019.4 focuses on conservative estimates of MOS hardness for space and tactical applications, while Basic Specification 22900 focuses on improved simulation of low-dose-rate space environments

  6. Recent activities within Nuclear Electric related to the qualification of digital systems and the extension of maintenance intervals

    International Nuclear Information System (INIS)

    Holt, G.P.

    1993-01-01

    Nuclear Electric is pursuing a program of modernization and enhancement of existing control and safety (C ampersand I) systems to improve power plant availability and increase power output. This paper describes recent experience in qualifying digital systems for safety applications. Also, described is the work currently in hand to reduce the frequency of maintenance periods for safety C ampersand I equipment. The qualification of digital systems is shown to be a more rigorous and much more extensive (and thus costly) exercise than the qualification of conventional equipment. This is illustrated by brief references to two software-based safety systems, the Single Channel Trip System at the Dungeness open-quotes Bclose quotesAGR and the Primary Protection System for the new PWR at Sizewell open-quotes Bclose quotes. The emphasis of the paper is on the use of Application Specific Integrated Circuits (ASICs) in safety systems, to reduce, or eliminate dependence on software for the fulfillment of requirements which need implementations that are complex or of a high functional density. Recent experience in the development of a prototype safety system based on ASICs, The Gaseous Activity Monitor and Trip Equipment (GAM), is used to illustrate their possible benefits and potential problems. When using complex integrated circuits like microprocessors or ASICs in digital systems a difficulty arises in analyzing the failure modes of the system. Efforts to overcome this difficulty led to the development of a method for performing failure analyses based on functional blocks. The techniques and benefits of such an approach are outlined. Finally, efforts to reduce maintenance costs, yet at the same time enhance safety, are leading towards an extension of maintenance intervals, for some safety equipment, from 3 months to 4 months and also towards lengthening the period between AGR outages from 2 years to 3 years

  7. A quality assurance program for nuclear power reactor materials tests at the Ford nuclear reactor

    International Nuclear Information System (INIS)

    Burn, R.R.

    1989-01-01

    The University of Michigan Nuclear Reactor Laboratory Quality Assurance Program has been established to assure that materials testing services provided to electric utilities produce accurate results in accordance with industry standards, sound engineering practice, and customer requirements. The program was prepared to comply with applicable requirements of 10CFR50, Appendix B, of the Code of Federal Regulations and a standard of the American National Standards Institute (ANSI), N45.2. The paper discusses the quality assurance program applicability, organization, qualification and training of personnel, material identification and control, examination and testing, measuring and test equipment, nonconforming test equipment, records, audits, and distribution

  8. Design and qualification of a RTOS for safety class nuclear C and I applications

    International Nuclear Information System (INIS)

    Wakankar, A.; Khan, Arindam; Kalra, Mohit; Mitra, Raka; Aravamuthan, G.; Bhattacharjee, A.K.; Vaidya, U.W.; Mayya, Anuradha

    2014-01-01

    Real Time Operating System (RTOS) is a critical component of embedded systems. International standards such as IEC60880 used for development of Instrumentation and Control (I and C) system in nuclear power plants require rigorous qualification of all software components. In this paper, we describe our experience in the design and qualification of ESOS; an in-house configured RTOS from a commodity RTOS available with source code. The qualification activities include static and dynamic analysis, timing analysis and rigorous program analysis. We discuss how rigorous program analysis was used to uncover a subtle bug in the implementation. We also discuss the applications where this qualified RTOS has been successfully used. (author)

  9. A BENCHMARK PROGRAM FOR EVALUATION OF METHODS FOR COMPUTING SEISMIC RESPONSE OF COUPLED BUILDING-PIPING/EQUIPMENT WITH NON-CLASSICAL DAMPING

    International Nuclear Information System (INIS)

    Xu, J.; Degrassi, G.; Chokshi, N.

    2001-01-01

    Under the auspices of the US Nuclear Regulatory Commission (NRC), Brookhaven National Laboratory (BNL) developed a comprehensive program to evaluate state-of-the-art methods and computer programs for seismic analysis of typical coupled nuclear power plant (NPP) systems with nonclassical damping. In this program, four benchmark models of coupled building-piping/equipment systems with different damping characteristics were analyzed for a suite of earthquakes by program participants applying their uniquely developed methods and computer programs. This paper presents the results of their analyses, and their comparison to the benchmark solutions generated by BNL using time domain direct integration methods. The participant's analysis results established using complex modal time history methods showed good comparison with the BNL solutions, while the analyses produced with either complex-mode response spectrum methods or classical normal-mode response spectrum method, in general, produced more conservative results, when averaged over a suite of earthquakes. However, when coupling due to damping is significant, complex-mode response spectrum methods performed better than the classical normal-mode response spectrum method. Furthermore, as part of the program objectives, a parametric assessment is also presented in this paper, aimed at evaluation of the applicability of various analysis methods to problems with different dynamic characteristics unique to coupled NPP systems. It is believed that the findings and insights learned from this program will be useful in developing new acceptance criteria and providing guidance for future regulatory activities involving licensing applications of these alternate methods to coupled systems

  10. Procedure for qualify class 1E equipment for nuclear power generating stations; Kvalifikacija elektroopreme za stjecanje klase 1E u nuklearnim elektranama

    Energy Technology Data Exchange (ETDEWEB)

    Smiljanic, D [' Rade Koncar' Institut, Zagreb (Yugoslavia)

    1983-07-01

    This paper describes the basic requirements for qualifying Class 1E equipment and systems that are to be used in nuclear power generating stations. The requirements presented include the principles, procedures and methods of qualification. The qualification requirements will confirm the adequacy of the equipment design under normal, abnormal, design basis event, post design basis event and containment test conditions for the performance of Class 1 E functions. The presented methods of qualification are in accordance with IEEE Standards and other standards (IEC, JUS, DIN, etc,), and have the primary role to provide guidance for demonstrating the qualification of Class 1E equipment produced by 'Rade Koncar'.(author)

  11. Europeans come together on qualification

    International Nuclear Information System (INIS)

    Whittle, J.

    1996-01-01

    Utilities operating nuclear power plants in Europe have formed the European Network for Inspection Qualification (ENIQ) to produce a common approach to demonstrating that non-destructive testing is capable providing the information to ensure the absence of significant defects in nuclear plants. Major developments over recent months have included the issue by ENIQ of a formal document defining the methodology for the conduct of qualification which sets out the principles that detailed systems, within an individual country context, should embody. A pilot study on pipe welds typical of those in BWR recirculation loops is being conducted to explore the issues involved in the practical application of the methodology. In parallel with ENIQ, the European Nuclear Regulators Working Group has set up a Task Force in an attempt to define a common regulatory position on non-destructive testing qualifications and has produced its own document which is wider in scope than that of ENIQ. (UK)

  12. Qualification of C and I systems using new technology components

    International Nuclear Information System (INIS)

    Gossner, S.

    1986-01-01

    Whereas one may find an almost complete change-over to microprocessor based automation and supervision systems in numerous industrial fields, a similar development did not yet take place in C and I systems of West German nuclear power plants. Neglecting some unimportant exceptions C and I systems of West German nuclear power plants are fully conventional. This situation, however, will not last forever. There is a growing understanding that by means of microcomputer-based C and I equipment it will be possible: to solve many problems more exactly, e.g. calculations of reactor power, power distribution, water levels, DNBR; to reduce the number of detailed informations and alarms concentrated in control rooms and control stations and to condense these informations into easily to understand pictorial displays, e.g. surveillance or trend pictures on graphic CRT-display units; to reduce cabling amount by using sequential data transmission, e.g. by means of bus-systems. It's clear in the near future microprocessors will enter not only operational C and I equipment but C and I systems important to safety as well. Therefore it's high time to analyse existing design and qualification requirements, qualification methods and qualification procedures whether or not to be suitable and sufficient

  13. Large Bore Powder Gun Qualification (U)

    Energy Technology Data Exchange (ETDEWEB)

    Rabern, Donald A. [Los Alamos National Laboratory; Valdiviez, Robert [Los Alamos National Laboratory

    2012-04-02

    A Large Bore Powder Gun (LBPG) is being designed to enable experimentalists to characterize material behavior outside the capabilities of the NNSS JASPER and LANL TA-55 PF-4 guns. The combination of these three guns will create a capability to conduct impact experiments over a wide range of pressures and shock profiles. The Large Bore Powder Gun will be fielded at the Nevada National Security Site (NNSS) U1a Complex. The Complex is nearly 1000 ft below ground with dedicated drifts for testing, instrumentation, and post-shot entombment. To ensure the reliability, safety, and performance of the LBPG, a qualification plan has been established and documented here. Requirements for the LBPG have been established and documented in WE-14-TR-0065 U A, Large Bore Powder Gun Customer Requirements. The document includes the requirements for the physics experiments, the gun and confinement systems, and operations at NNSS. A detailed description of the requirements is established in that document and is referred to and quoted throughout this document. Two Gun and Confinement Systems will be fielded. The Prototype Gun will be used primarily to characterize the gun and confinement performance and be the primary platform for qualification actions. This gun will also be used to investigate and qualify target and diagnostic modifications through the life of the program (U1a.104 Drift). An identical gun, the Physics Gun, will be fielded for confirmatory and Pu experiments (U1a.102D Drift). Both guns will be qualified for operation. The Gun and Confinement System design will be qualified through analysis, inspection, and testing using the Prototype Gun for the majority of process. The Physics Gun will be qualified through inspection and a limited number of qualification tests to ensure performance and behavior equivalent to the Prototype gun. Figure 1.1 shows the partial configuration of U1a and the locations of the Prototype and Physics Gun/Confinement Systems.

  14. 5 CFR 319.302 - Individual qualifications.

    Science.gov (United States)

    2010-01-01

    ... 5 Administrative Personnel 1 2010-01-01 2010-01-01 false Individual qualifications. 319.302... Individual qualifications. Agency heads are delegated authority to approve the qualifications of individuals appointed to SL and ST positions. The agency head must determine that the individual meets the...

  15. Changing existing qualifications into outcomes-based qualifications ...

    African Journals Online (AJOL)

    Various workshops were facilitated to determine the outcomes of each level of our qualification, B Tech: Policing. This led to the formulation of a purpose statement, exit level outcomes and specific outcomes as well as assessment criteria and the critical outcomes embedded in each level identified. Using the specific ...

  16. Consenso e diferenças em equipes do Programa Saúde da Família Agreements and disagreements in the Family Health Care Program team

    Directory of Open Access Journals (Sweden)

    José Ivo dos Santos Pedrosa

    2001-06-01

    Full Text Available OBJETIVO: Identificar temáticas que promovam consenso e divergências entre médicos, enfermeiros e agentes que compõem a equipe do Programa Saúde da Família. MÉTODOS: Estudo qualitativo que utiliza grupos focais como técnica de pesquisa com agentes masculinos e femininos, médicos e enfermeiras da equipe do Programa Saúde da Família, em Teresina, PI. Foram realizadas sessões com os grupos, conduzidas por monitor e participação de observador, utilizando roteiro com as questões: inserção no programa; processo de capacitação; princípios do programa; relações com a formação e com o modelo assistencial predominante; relações entre membros da equipe e comunidade; serviços demandados e disponíveis; situação trabalhista e condições de trabalho; e fatores positivos e negativos. RESULTADOS: Temáticas gerais como trabalho na comunidade, cuidados preventivos e trabalho em equipe geraram consenso entre as três categorias de profissionais. Temas que reforçaram a divisão entre categorias foram salário, organização do processo de trabalho, relações com a comunidade, responsabilidades da equipe e estratégias de atendimento à demanda. Temas que promoveram o aparecimento de subgrupos em cada categoria foram: condições de trabalho, salário, relações com a comunidade e responsabilidades da equipe. CONCLUSÕES: Temas que evidenciaram diferenças em maior grau reforçaram as características corporativas de cada categoria, enquanto temas que promoveram o aparecimento de subgrupos foram discutidos a partir de referências externas, implicando a necessidade de definir especificidades do processo de trabalho no programa. As estratégias para atendimento às demandas da comunidade representaram temáticas emergenciais ao grupo de agentes, pois a eles coube a solução imediata para os problemas na relação comunidade e serviço.OBJECTIVE: To identify issues that promote agreement and disagreement among doctors, nurses, and

  17. Existe trabalho em equipe no Programa Saúde da Família? Is there teamwork in the Family Health Program?

    Directory of Open Access Journals (Sweden)

    Maria do Carmo Gomes Kell

    2010-06-01

    Full Text Available O objetivo do estudo foi conhecer como se desenvolve o trabalho em equipe no Programa Saúde da Família. Utilizou-se metodologia qualitativa. Foi realizado no Município de Santo Antonio do Descoberto (GO, com quatro equipes básicas completas há mais de seis meses. Foram feitos grupos focais, em duas etapas, a primeira com elementos de cada equipe individualmente e, posteriormente, com integrantes das quatro equipes. Para a análise, empregou-se a técnica de discurso do sujeito coletivo. Evidenciou-se que os sujeitos representam o trabalho em equipe como a união dos integrantes na busca de um objetivo comum, o processo de trabalho ocorre de forma parcelar, pois as funções se realizam de forma isolada ou compartilhada, mas não interativa ou integrada. A ausência de articulação das ações dificulta que as equipes encontrem espaços para a elaboração de projeto assistencial local que atenda as necessidades mais amplas da população.The objective of the study was to know how team work in the Family Health Program is developed. A qualitative methodology was used. The study was performed in the city of Santo Antonio do Descoberto, in the Brazilian state of Goiás, with four complete basic teams more than six months ago. Focal groups had been formed, in two stages: the first with elements of each team individually, and later, with integrants of the four teams. For the analysis it was used the Discourse of the Collective Subject technique. It was evidenced that the subjects represent the team work as the union of the integrant ones in the search of a common objective. The work process occurs in a fragmented way, once the functions are carried in either an isolated or shared form, but not interactive or integrated. The absence of articulation of the actions becomes difficult that the teams find spaces for the elaboration of a local assistance project that meet the most ample needs of the population.

  18. Environmental qualification test of electrical penetration for nuclear power stations

    International Nuclear Information System (INIS)

    Kooziro, Tetsuya; Nakagawa, Akitoshi; Toyoda, Shigeru; Uno, Shunpei

    1979-01-01

    Environmental qualification test was conducted according to IEEE Std. 323-1974 in order to evaluate the safety and reliability of electrical penetration of PWR type nuclear power station. Electrical penetration is the assemblies of electric cables attached to the containment vessel and penetrate through the vessel. Since it is a part of the vessel, it is deemed to be one of the primary safety equipments that are important for the safety and reliability of nuclear power stations. Environmental tests were conducted continuously as to heat cycle, vibration and LOCA with the full size specimens of bushing type, pigtail type and triaxial cable type and at the same time thermal life and irradiation tests were conducted on the insulation materials used, in order to obtain the comprehensive evaluation of their electrical and mechanical characteristics. As the result, they all satisfied the requirements for the circuits for actual use during and after various environmental qualification tests according to IEEE Std. 323. (author)

  19. The qualification of electrical components and instrumentations relevant to safety

    CERN Document Server

    Zambardi, F

    1989-01-01

    Systems and components relevant to safety of nuclear power plants must maintain their functional integrity in order to assure accident prevention and mitigation. Redundancy is utilized against random failures, nevertheless care must be taken to avoid common failures in redundant components. Main sources of degradation and common cause failures consist in the aging effects and in the changes of environmental conditions which occur during the plant life and the postulated accidents. These causes of degradation are expected to be especially significant for instrumentation and electrical equipment, which can have a primary role in safety systems. The qualification is the methodology by which component safety requirements can be met against the above mentioned causes of degradation. In this report the connection between the possible, plant conditions and the resulting degradation effects on components is preliminarily addressed. A general characterization of the qualification is then presented. Basis, methods and ...

  20. Nuclear power plant personnel entry level qualifications and training

    International Nuclear Information System (INIS)

    Jorgensen, C.C.; Haas, P.M.; Selby, D.L.; Lowry, J.C.

    1983-01-01

    This paper summarizes the early results and current status of a research program at ORNL which is intended to provide the methods and technical basis for NRC to initiate the use of the Systems Approach to Training (SAT) in the evaluation of training programs and entry level qualifications for NPP control room personnel. The program is an outgrowth of previous studies of simulator hardware and simulator training requirements under the Safety Related Operator Actions Program which recommended adaptation of a systems methodology to development and evaluation of NPP training programs

  1. Comparison of IEEE383-2003 and IEC60505-2004 standards for harmonization of environmental qualification procedure of electric cable

    International Nuclear Information System (INIS)

    Kim, Jong Seog; Jeong, Sun Chul; Park, Kyung Heum; Jang, Kyung Nam

    2010-01-01

    Needs for harmonization of international equipment qualification(EQ) standards have been raised several years due to purchasing problem of nuclear equipment supplied from abroad country. To meet the regulatory requirement of domestic nuclear power plant, manufacturers have to qualify their equipment in accordance with each standard such as IEEE, IEC and RCC-E. Double qualification increase the equipment cost, which result in high construction cost. Even the unification of each standard have been discussed several years, we have got the long way to go yet. Comparison and harmonization of each international standard will give help to purchase the equipment qualified by not endorsed standard. Environmental qualification, seismic qualification and EMI/EMC qualification are major targets for harmonization. Since concern about cable qualification of 60 years life has been raised recently, harmonization of cable qualification standard also needs to be discussed. KEPRI launched a project for harmonization of EQ relative standards such as IEEE, IEC and RCC-E. A study for harmonization of IEEE323 and IEC60780 is known in progress by IEEE committee. In this paper, harmonization of international standards for cable qualification will be discussed. IEEE383 standard is qualification standard for electric cable broadly used in Asian pacific area while IEC60505 is mostly used in European area. Since these two standards have different requirements for environmental qualification of cable, problem can be happened in the plant site when they purchase cable qualified by not endorsed standard. IEEE383-2003 and IEC60505-2004 is the latest version of each standard. Comparison results and recommendations for harmonization of these two standards are introduced herein

  2. Programa Saúde da Família: a experiência de equipe multiprofissional Family Health Program: the experience of a multiprofessional team

    Directory of Open Access Journals (Sweden)

    Elaine Machado de Oliveira

    2006-08-01

    Full Text Available OBJETIVO: O Programa Saúde da Família propõe uma nova dinâmica para estruturação dos serviços de saúde, assim como para a relação com a comunidade e para diversos níveis de assistência. O objetivo do estudo foi analisar o significado da experiência do trabalho em equipe para os profissionais do Programa Saúde da Família. MÉTODOS: O estudo foi realizado no município de Conchas, Estado de São Paulo no ano de 2004. A abordagem utilizada foi qualitativa, na vertente da fenomenologia, buscando a essência da realidade vivenciada por oito profissionais de duas equipes do Programa Saúde da Família. RESULTADOS: Os temas revelaram que o trabalho em equipe se caracteriza por dedicação durante as atividades diárias. É necessário haver interação entre todos os membros para ações integrais, embora haja diferenças de ideologias e condutas entre os profissionais. O contato próximo com as famílias permitiu melhor intervenção nos problemas e o trabalho integrado é fundamental para atuação eficaz e de qualidade. CONCLUSÕES: O fenômeno desvelado engendra nova perspectiva de atuação para os profissionais e possibilita a compreensão do trabalho em equipe multiprofissional.OBJECTIVE: The Family Health Program proposes a new dynamics for the structuring of health service, as well as for its relationship with the community in its different levels of care. The aim of the present study was to analyze the significance of teamwork for professionals working in the Family Health Program. METHODS: The study was carried out in the city of Conchas, Southeastern Brazil, in 2004. We used a qualitative approach based on phenomenology as an attempt to reveal the essence of the reality experienced by eight professionals from two Family Health Program teams. RESULTS: Themes revealed that teamwork is characterized by dedication to daily activities. Interaction among all members is required for integral action, although there are differences in

  3. Mutual Recogniton of Professional Qualifications

    DEFF Research Database (Denmark)

    Enemark, Stig; Plimmer, Francis

    The publication aims to review the concept of mutual recognition of qualifications within the world wide surveying community, and to develop a framework for the introduction of standards of global professional competence in this area. The publication also includes a number of case studies from...

  4. Helicopter-Ship Qualification Testing

    NARCIS (Netherlands)

    Hoencamp, A.

    2015-01-01

    The goal of this research project is to develop a novel test methodology which can be used for optimizing cost and time efficiency of helicopter-ship qualification testing without reducing safety. For this purpose, the so-called “SHOL-X” test methodology has been established, which includes the

  5. Personnel Officers: Judging Their Qualifications.

    Science.gov (United States)

    Webb, Gisela

    1988-01-01

    Discusses the backgrounds and qualifications appropriate for a library personnel administrator, including (1) a master's degree in library science; (2) library work experience; (3) additional training in administration, personnel management, organizational development, and psychology; and (4) personal attributes such as good communication skills,…

  6. 77 FR 59339 - Contractor Qualifications

    Science.gov (United States)

    2012-09-27

    ... DEPARTMENT OF DEFENSE Defense Acquisition Regulations System 48 CFR Part 209 Contractor Qualifications CFR Correction In Title 48 of the Code of Federal Regulations, Chapter 2 (Parts 201-299), revised as of October 1, 2011, on page 55, in section 209.104-70, paragraph (a) is amended by revising the...

  7. Equipment aging: an overview of status and research needs

    International Nuclear Information System (INIS)

    Carfagno, S.P.

    1982-01-01

    The problem of equipment aging in nuclear power generating stations is viewed from the standpoint of the qualification of safety-related equipment. A brief summary of developments related to equipment aging and qualification (in industry, the regulatory arena, and in the research area) is presented to focus on the current status of the problem. Several research topics are suggested for consideration as components of any general plan of research on plant aging. Among these is a topic concerned with an effort to establish the relative merit of different approaches to account for the functional degradation of equipment in terms of their cost and their contribution to assurance of public safety and a topic to investigate ways to improve the monitoring of functional degradation of equipment in service. Some factors to be considered in choosing among research topics and in establishing funding levels are mentioned

  8. Environmental impact of the programs of substitution of room type air conditioning equipment; Impacto ambiental de los programas de sustitucion de equipos de aire tipo cuarto

    Energy Technology Data Exchange (ETDEWEB)

    Alarcon Aleman, Jose Mauricio [OLADE, Quito (Ecuador)

    2002-09-01

    The present article approaches in a general way the relation that exists between the environment and the saving of electrical energy, especially in the Programs of Demand Side Management (DSM). In particular form the potential environmental impacts are described, derived of the use and the discard of the room type air conditioning equipment, goes deep into the characteristics of their cooling fluids, as well as in the relation that these keep with the protocols of Montreal and Kyoto. Finally, this article comments the incidence which have, the manufacturers as the institutions that implement DSM programs, on the environmental part of the programs of substitution of room type air conditioning equipment. In addition it is briefly described, the pilot program developed by Fideicomiso para el Ahorro de Energia Electrica (FIDE) as a successful case. [Spanish] En forma general, el presente articulo aborda la relacion que existe entre el medio ambiente y el ahorro de energia electrica, especialmente en los Programas de Administracion por el Lado de la Demanda (ALD). En forma particular se describen los impactos ambientales potenciales, derivados del uso y desecho de los equipos de aire acondicionado tipo cuarto, se ahonda en las caracteristicas de sus refrigerantes, asi como en la relacion que estos guardan con los protocolos de Montreal y Kioto. Finalmente, se comenta la incidencia que tienen, tanto los fabricantes como las instituciones que implementan programas de ALD, sobre la parte ambiental de los programas de sustitucion de equipos de aire acondicionado tipo cuarto. Ademas se describe brevemente, el programa piloto desarrollado por el Fideicomiso para el Ahorro de Energia Electrica (FIDE) como un caso exitoso.

  9. MOBI: a marine and earth science interpretation and qualification program for out-of-school environment and natural heritage interpreters and other science communicators in Germany

    Science.gov (United States)

    Schneider, S.; Ellger, C.

    2017-12-01

    As a contribution to Germany's "Science Year 2016*17 - Seas and Oceans", a large science outreach program organized and financed by the National Ministry for Education and Research, GeoUnion, the umbrella organization of Earth science associations and institutions in Germany, has conducted a series of advance level workshops for out-of-school educators and interpreters in Germany. The workshops were organized in co-operation with geoparks, biosphere reserve areas and other environmental management institutions all over Germany. The goal was to convey various perspectives of modern marine sciences to inland venues, linking important present-day marine themes with the presentation of marine phases in the geological history of the host region. The workshops were designed for park rangers, museum educationalists and other science communicators, initiating a broader impact on target groups such as school classes, (geo-)tourists and stakeholder groups. Our approach has been to combine lectures by top-level scientists (on both ocean literacy aspects and regional geology) with discussions and an on-the-spot learning-and-presenting module based on prepared text and visual material. Beyond earth science issues we have integrated economy, ecology, social sciences as well as arts and humanities aspects. One central topic was the role of the world ocean in climate change; other themes highlighted sea level rise, the thermohaline circulation, sea-floor spreading, coral reefs, over-fishing, various marine species and the problem of plastic waste in the ocean. We had anticipated that marine issues are actually very rarely discussed in inland Germany. A structured presentation of ocean literacy elements has proved to be a new range of topical issues from earth and environmental sciences highly appreciated by the participants.

  10. Measurement control program for nuclear material accounting

    International Nuclear Information System (INIS)

    Brouns, R.J.; Roberts, F.P.; Merrill, J.A.; Brown, W.B.

    1980-06-01

    A measurement control program for nuclear material accounting monitors and controls the quality of the measurments of special nuclear material that are involved in material balances. The quality is monitored by collecting data from which the current precision and accuracy of measurements can be evaluated. The quality is controlled by evaluations, reviews, and other administrative measures for control of selection or design of facilities, equipment and measurement methods and the training and qualification of personnel who perform SNM measurements. This report describes the most important elements of a program by which management can monitor and control measurement quality

  11. Equipment for hydraulic testing

    International Nuclear Information System (INIS)

    Jacobsson, L.; Norlander, H.

    1981-07-01

    Hydraulic testing in boreholes is one major task of the hydrogeological program in the Stripa Project. A new testing equipment for this purpose was constructed. It consists of a downhole part and a surface part. The downhole part consists of two packers enclosing two test-sections when inflated; one between the packers and one between the bottom packer and the bottom of the borehole. A probe for downhole electronics is also included in the downhole equipment together with electrical cable and nylon tubing. In order to perform shut-in and pulse tests with high accuracy a surface controlled downhole valve was constructed. The surface equipment consists of the data acquisition system, transducer amplifier and surface gauges. In the report detailed descriptions of each component in the whole testing equipment are given. (Auth.)

  12. Gas Reactor International Cooperative program. Pebble bed reactor plant: screening evaluation. Volume 3. Appendix A. Equipment list

    International Nuclear Information System (INIS)

    1979-11-01

    This report consists of three volumes which describe the design concepts and screening evaluation for a 3000 MW(t) Pebble Bed Reactor Multiplex Plant (PBR-MX). The Multiplex plant produces both electricity and transportable chemical energy via the thermochemical pipeline (TCP). The evaluation was limited to a direct cycle plant which has the steam generators and steam reformers in the primary circuit. Volume 1 reports the overall plant and reactor system and was prepared by the General Electric Company. Core scoping studies were performed which evaluated the effects of annular and cylindrical core configurations, radial blanket zones, burnup, and ball heavy metal loadings. The reactor system, including the PCRV, was investigated for both the annular and cylindrical core configurations. Volume 3 is an Appendix containing the equipment list for the plant and was also prepared by United Engineers and Constructors, Inc. It tabulates the major components of the plant and describes each in terms of quantity, type, orientation, etc., to provide a basis for cost estimation

  13. Imaging Sensor Flight and Test Equipment Software

    Science.gov (United States)

    Freestone, Kathleen; Simeone, Louis; Robertson, Byran; Frankford, Maytha; Trice, David; Wallace, Kevin; Wilkerson, DeLisa

    2007-01-01

    The Lightning Imaging Sensor (LIS) is one of the components onboard the Tropical Rainfall Measuring Mission (TRMM) satellite, and was designed to detect and locate lightning over the tropics. The LIS flight code was developed to run on a single onboard digital signal processor, and has operated the LIS instrument since 1997 when the TRMM satellite was launched. The software provides controller functions to the LIS Real-Time Event Processor (RTEP) and onboard heaters, collects the lightning event data from the RTEP, compresses and formats the data for downlink to the satellite, collects housekeeping data and formats the data for downlink to the satellite, provides command processing and interface to the spacecraft communications and data bus, and provides watchdog functions for error detection. The Special Test Equipment (STE) software was designed to operate specific test equipment used to support the LIS hardware through development, calibration, qualification, and integration with the TRMM spacecraft. The STE software provides the capability to control instrument activation, commanding (including both data formatting and user interfacing), data collection, decompression, and display and image simulation. The LIS STE code was developed for the DOS operating system in the C programming language. Because of the many unique data formats implemented by the flight instrument, the STE software was required to comprehend the same formats, and translate them for the test operator. The hardware interfaces to the LIS instrument using both commercial and custom computer boards, requiring that the STE code integrate this variety into a working system. In addition, the requirement to provide RTEP test capability dictated the need to provide simulations of background image data with short-duration lightning transients superimposed. This led to the development of unique code used to control the location, intensity, and variation above background for simulated lightning strikes

  14. Legacy program acquires special equipment for CRL spent fuel. Canadian arm of Rolls Royce delivers unique machines

    International Nuclear Information System (INIS)

    Boyd, F.

    2012-01-01

    Six years ago the federal government accepted its responsibility for the radioactive waste that has resulted from the six decades of nuclear research and development conducted by Atomic Energy of Canada Limited and its predecessor operator of the Chalk River Laboratories (CRL) the National Research Council (1944 - 1952). Nuclear research and development and, particularly, reactor operation at CRL has resulted in outdated and unused research facilities and buildings and a wide variety of buried and stored radioactive waste. In 2006 the federal government established the Nuclear Legacy Liabilities Program (NLLP) with an initial funding of $520 million. The mandate of the NLLP is to deal with the radioactive waste arising from the nuclear research and development program of AECL and also prototype reactors in which it was involved. The timeline for the NLLP extends several decades into the future. The NLLP is implemented through a partnership of Natural Resources Canada (NRCan) and AECL. NRCan is responsible for policy direction and oversight, while AECL is responsible for program implementation and all licences, facilities and lands. About 70 percent of the liabilities from AECL activities are at CRL. Other sites that will be restored under the NLLP are: the Whiteshell Laboratories and Underground Research Laboratory in Manitoba; NPD and Douglas Point reactors in Ontario; and the Gentilly 1 reactor in Quebec. (author)

  15. Reliability Evaluation of Concentrator Photovoltaic Modules per IEC Qualification Specifications

    Energy Technology Data Exchange (ETDEWEB)

    Tamizhmani, Govindasamy

    2012-12-05

    This project is related to the qualification testing of new generation CPV (concentrator photovoltaics) modules at lower testing costs and lower turnaround time. In this project, the first testing program was completed for two CPV manufacturers, the second testing program was completed for two manufacturers at 65% of the actual testing cost and at less than 3 months of testing turnaround time and the third testing program was completed for two manufacturers at 65% of the actual testing cost and at less than 3 months of testing turnaround time. Due to their financial situation and restructuring, Amonix (one of the CPV manufacturers) intermittently terminated the test programs.

  16. Standard guide for qualification of measurement methods by a laboratory within the nuclear industry

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2003-01-01

    1.1 This guide provides guidance for selecting, validating, and qualifying measurement methods when qualification is required for a specific program. The recommended practices presented in this guide provide a major part of a quality assurance program for the laboratory data (see Fig. 1). Qualification helps to assure that the data produced will meet established requirements. 1.2 The activities intended to assure the quality of analytical laboratory measurement data are diagrammed in Fig. 1. Discussion and guidance related to some of these activities appear in the following sections: Section Selection of Measurement Methods 5 Validation of Measurement Methods 6 Qualification of Measurement Methods 7 Control 8 Personnel Qualification 9 1.3 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 limitati...

  17. Development of spectral analysis math models and software program and spectral analyzer, digital converter interface equipment design

    Science.gov (United States)

    Hayden, W. L.; Robinson, L. H.

    1972-01-01

    Spectral analyses of angle-modulated communication systems is studied by: (1) performing a literature survey of candidate power spectrum computational techniques, determining the computational requirements, and formulating a mathematical model satisfying these requirements; (2) implementing the model on UNIVAC 1230 digital computer as the Spectral Analysis Program (SAP); and (3) developing the hardware specifications for a data acquisition system which will acquire an input modulating signal for SAP. The SAP computational technique uses extended fast Fourier transform and represents a generalized approach for simple and complex modulating signals.

  18. Qualification and certification in NDT

    International Nuclear Information System (INIS)

    Hassan Kavarodi Maracair

    2003-01-01

    Ruane-TATI Sdn Bhd was the first accredited training centre in Asia approved by The British Institute of Non Destructive Testing (BINDT) as per EN 473, ISO 9712 and EN 45013 requirements. Meanwhile, Ruane-TATI is also accredited by National Vocational Training Center ( MLVK ).This mean that Ruane-TATI is the first training and examination center that accredited by both international and national bodies in providing quality , qualification and certification for comprehensive training and examination in Inspection and Non Destructive Testing (NDT). There are several NDT examinations scheme available in Malaysia due to differences requirement from the industrials. This has put the difficulties to services company in upgrading their NDT technician qualifications. The intention of this paper is to discuss the basic different among the NDT examinations scheme used in Malaysia ( mostly offered by Ruane-TATI ) and the development of certain schemes in covering their schemes to more sectors and NDT methods. (Author)

  19. Qualification of high-density fuel manufacturing for research reactors at CNEA

    Energy Technology Data Exchange (ETDEWEB)

    Adelfang, P.; Alvarez, L.; Boero, N.; Calabrese, R.; De La Fuente, M.; Echenique, P.; Markiewicz, M.; Pasqualini, E.; Ruggirello, G.; Taboada, H. [CNEA, Buenos Aires (Argentina)

    2001-07-01

    CNEA, the National Atomic Energy Commission of Argentina, is at the present a qualified supplier of uranium oxide fuel for research reactors. A new objective in this field is to develop and qualify the manufacturing of LEU high-density fuel for this type of reactors. According with the international trend Silicide fuel and U-xMo fuel are included in our program as the most suitable options. The facilities to complete the qualification of high-density MTR fuels, like the manufacturing plant installations, the reactor, the pool side fuel examination station and the hot cells are fully operational and equipped to perform all the activities required within the program. The programs for both type of fuels include similar activities: development and set up of the fuel material manufacturing technology, set up of fuel plate manufacturing, fabrication and irradiation of miniplates, fabrication and irradiation of full scale fuel elements, post-irradiation examination and feedback for manufacturing improvements. For silicide fuels most of these steps have already been completed. For U-xMo fuel the activities also include the development of alternative ways to obtain U-xMo powder, feasibility studies for large-scale manufacturing and the economical assessment. Set up of U-xMo fuel plate manufacturing is also well advanced and the fabrication of the first full scale prototype is foreseen during this year. (author)

  20. Radiation Safety (Qualifications) Regulations 1980

    International Nuclear Information System (INIS)

    1980-01-01

    These Regulations, promulgated pursuant to the provisions of the Radiation Safety Act, 1975-1979, require persons engaged in activities involving radiation to pass a radiation safety examination or to possess an approved qualification in radiation. The National Health and Medical Research Council is authorised to exempt persons from compliance with these requirements or, conversely, to impose such requirements on persons other than those designated. (NEA) [fr

  1. 34 CFR 74.34 - Equipment.

    Science.gov (United States)

    2010-07-01

    ... as program income. (e) When acquiring replacement equipment, the recipient may use the equipment to... replacement equipment subject to the approval of the Secretary. (f) The recipient's property management... 34 Education 1 2010-07-01 2010-07-01 false Equipment. 74.34 Section 74.34 Education Office of the...

  2. Data base EQDB - data base of the qualified equipment's for NPP

    International Nuclear Information System (INIS)

    Rovny, K.

    2009-01-01

    In the contribution, there is presented the project of the data base for qualified equipment's for nuclear power plants. The data base is operated by the 'Certification body which certified the products - the chosen equipment's for nuclear power plants', reg. No. P-028, at VUJE, Inc. Trnava. Data base will serve to the designers, the operators of the nuclear power plants and the workers from Nuclear regulatory authority of the Slovak Republic as a source of information about the state of concrete type equipment's qualification. In the first part of the contribution, there is information about the legislation and technical requirements for equipment's qualification, the way of demonstration and importance of the qualification for the operator. In the next part, there is presented the own structure of data base and the works with own data base regarding the examples of concrete equipment's. The data base will be accessible after the free registration on address WWW.EQDB.sk from 1.5.2009

  3. Rest-lifetime evaluation of equipment and facilities of NPP Kozloduy 3 and 4 and development of an ageing management program

    International Nuclear Information System (INIS)

    Erve, M.; Schmidt, J.; Kastner, B.; Gledatchev, I.; Sabinov, S.; Stoev, M.; Korneev, V.; Strombach, Y.

    2001-01-01

    The task indicated in the title is part of a comprehensive upgrading program for Units 3 and 4 of the Kozloduy plant executed in a Consortium between Framatome ANP (a Framatome and Siemens company) and the Russian company Atomstroyexport. It comprises an evaluation of the residual service life of components/systems/plants subject to acceptance by international experts, identifying the need for further investigations/calculations in certain cases, and finding solutions for improvements that achieve a consensus of safety and economy. The initial results are: Walkdowns revealed no clear knock-out point for the plants, however there are preliminary hints for necessary further improvements. Investigations of templates taken from the RPV of Unit 1 were started: the results are still preliminary, but can be considered very positive; their transfer to the RPV of Unit 3 would mean that the latest safety analyses of the Unit 3 RPV are conservative. The general work program was successfully applied on the batteries as a pattern for the electrical equipment: parameters for the computer database and proposals for an effective aging management program were addressed. (author)

  4. Personal protective equipment use among students with special health care needs reporting injuries in school-sponsored vocational, career, and technical education programs in New Jersey.

    Science.gov (United States)

    Rubenstein, Eric; Shendell, Derek; Eggert, Brain C; Marcella, Stephen W

    2014-01-01

    Students with special health care needs (SHCNs) and individualized education plans (IEPs) may be injured more often in vocational, career, and technical education (CTE) programs. No research to date considers personal protective equipment (PPE) use among students with SHCNs in school-based programs reporting injuries to agencies. Data from 1999 to 2011 on PPE use among injured students in CTE programs in public schools and private secondary schools for the disabled were analyzed; students with SHCNs were distinguished by IEP status within New Jersey Safe Schools surveilance data. Among students with IEPs using PPE, 36% of injuries occurred to body parts PPE was meant to protect. Likely injury types were cuts-lacerations and burns for students with IEPs using PPE and cuts-lacerations and sprains for students with IEPs not using PPE. Females with IEPs using PPE were injured less often than males across ages. Results suggested students with SHCNs with IEPs need further job-related training with increased emphasis on properly selecting and fitting PPE.

  5. The IRIS Education and Outreach Program: Providing access to data and equipment for educational and public use

    Science.gov (United States)

    Taber, J.; Toigo, M.; Bravo, T. K.; Hubenthal, M.; McQuillan, P. J.; Welti, R.

    2009-12-01

    The IRIS Education and Outreach Program has been an integral part of IRIS for the past 10 years and during that time has worked to advance awareness and understanding of seismology and earth science while inspiring careers in geophysics. The focus on seismology and the use of seismic data has allowed the IRIS E&O program to develop and disseminate a unique suite of products and services for a wide range of audiences. One result of that effort has been increased access to the IRIS Data Management System by non-specialist audiences and simplified use of location and waveform data. The Seismic Monitor was one of the first Web-based tools for observing near-real-time seismicity. It continues to be the most popular IRIS web page, and thus it presents aspects of seismology to a very wide audience. For individuals interested in more detailed ground motion information, waveforms can be easily viewed using the Rapid Earthquake Viewer, developed by the University of South Carolina in collaboration with IRIS E&O. The Seismographs in Schools program gives schools the opportunity to apply for a low-cost educational seismograph and to receive training for its use in the classroom. To provide better service to the community, a new Seismographs in Schools website was developed in the past year with enhanced functions to help teachers improve their teaching of seismology. The site encourages schools to make use of seismic data and communicate with other educational seismology users throughout the world. Users can view near-real-time displays of other participating schools, upload and download data, and use the “find a teacher” tool to contact nearby schools that also may be operating seismographs. In order to promote and maintain program participation and communication, the site features a discussion forum to encourage and support the growing global community of educational seismograph users. Any data that is submitted to the Seismographs in Schools Website is also accessible

  6. Building Skills and Qualifications among SME Employees. Leonardo da Vinci Good Practices Series.

    Science.gov (United States)

    Commission of the European Communities, Brussels (Belgium). Directorate-General for Education and Culture.

    This document profiles 10 European programs that exemplify good practice in building skills and qualifications among employees of small and medium enterprises (SMEs). The programs profiled are as follows: (1) TRICTSME (a program providing World Wide Web-based information and communication technologies training for SMEs in manufacturing); (2)…

  7. DOE handbook: Guide to good practices for training and qualification of chemical operators

    International Nuclear Information System (INIS)

    1996-03-01

    The purpose of this Handbook is to provide contractor training organizations with information that can be used as a reference to refine existing chemical operator training programs, or develop new training programs where no program exists. This guide, used in conjunction with facility-specific job analyses, will provide a framework for training and qualification programs for chemical operators at DOE reactor and nonreactor facilities. Recommendations for qualification are made in four areas: education, experience, physical attributes, and training. Contents include: initial qualification; administrative training; industrial safety training; specialized skills training; on-the-job training; trainee evaluation; continuing training; training effectiveness evaluation; and program records. Two appendices describe Fundamentals training and Process operations. This handbook covers chemical operators in transportation of fuels and wastes, spent fuel receiving and storage, fuel disassembly, fuel reprocessing, and both liquid and solid low-level waste processing

  8. Equipment cost optimization

    International Nuclear Information System (INIS)

    Ribeiro, E.M.; Farias, M.A.; Dreyer, S.R.B.

    1995-01-01

    Considering the importance of the cost of material and equipment in the overall cost profile of an oil company, which in the case of Petrobras, represents approximately 23% of the total operational cost or 10% of the sales, an organization for the optimization of such costs has been established within Petrobras. Programs are developed aiming at: optimization of life-cycle cost of material and equipment; optimization of industrial processes costs through material development. This paper describes the methodology used in the management of the development programs and presents some examples of concluded and ongoing programs, which are conducted in permanent cooperation with suppliers, technical laboratories and research institutions and have been showing relevant results

  9. Qualification testing of flat-plate photovoltaic modules

    Science.gov (United States)

    Hoffman, A. R.; Griffith, J. S.; Ross, R. G., Jr.

    1982-01-01

    The placement of photovoltaic modules in various applications, in climates and locations throughout the world, results in different degrees and combinations of environmental and electrical stress. Early detection of module reliability deficiencies via laboratory testing is necessary for achieving long, satisfactory field service. This overview paper describes qualification testing techniques being used in the US Department of Energy's flat-plate terrestrial photovoltaic development program in terms of their significance, rationale for specified levels and durations, and test results.

  10. [Hydrotherapy equipment].

    Science.gov (United States)

    Tsibikov, V B; Ragozin, S I; Mikheeva, L V

    1985-01-01

    A flow-chart is developed demonstrating the relation between medical and prophylactic institutions within the organizational structure of the rehabilitation system and main types of rehabilitation procedures. In order to ascertain the priority in equipping rehabilitation services with adequate hardware the special priority criterion is introduced. The highest priority is assigned to balneotherapeutic and fangotherapeutic services. Based on the operation-by-operation analysis of clinical processes related to service and performance of balneologic procedures the preliminary set of clinical devices designed for baths, basins and showers in hospitals and rehabilitation departments is defined in a generalized form.

  11. Seismic qualification using digital signal processing/modal testing and finite element techniques

    International Nuclear Information System (INIS)

    Steedman, J.B.; Edelstein, A.

    1983-01-01

    A systematic procedure in which digital signal processing, modal testing and finite element techniques can be used to seismically qualify Class IE equipment for use in nuclear generating stations is presented. A new method was also developed in which measured transmissibility functions and Fourier transformation techniques were combined to compute instrument response spectra. As an illustrative example of the qualification method, the paper follows the qualification of a safety related Class IE Heating, Ventilating, and Air Conditioning (HVAC) Control Panel subjected to both seismic and hydrodynamic loading conditions

  12. Qualification of a production and packaging hot cell for sodium pertechnetate Tc 99m

    International Nuclear Information System (INIS)

    Cavero, Luis; Robles, Anita; Miranda, Jesus; Martinez, Ramos; Paragulla, Wilson; Moore, Mariel; Herrera, Jorge; Ocana, Elias; Portilla, Arturo; Otero, Manuel; Novoa, Carlos; Koga, Roberto

    2014-01-01

    It was designed and implemented a protocol for a hot cell of production and packaging of sodium pertechnetate Tc 99m, in a two-step process: installation qualification (IQ) and operation qualification (OQ). In the IQ design specifications and user requirements and associated equipment and materials by traceable documentation was verified. In the OQ scheduled for operation and control sequences it was verified plus operational tests recommended by the World Health Organization (WHO) and ISO 14644-1 and 3 were performed to clean areas. The results showed that the hot cell complies with the classification for Grades C and A for the preparation and packaging of Tc 99m. (authors).

  13. Monitoring equipment environment during nuclear plant operation at Salem and Hope Creek generating stations

    International Nuclear Information System (INIS)

    Blum, A.; Smith, R.J.

    1991-01-01

    Monitoring of environmental parameters has become a significant issue for operating nuclear power plants. While the long-term benefits of plant life extension programs are being pursued with comprehensive environmental monitoring programs, the potential effect of local hot spots at various plant locations needs to be evaluated for its effect on equipment degradation and shortening of equipment qualified life. A significant benefit can be experienced from temperature monitoring when a margin exists between the design versus actual operating temperature. This margin can be translated into longer equipment qualified life and significant reduction in maintenance activities. At PSE and G, the immediate need for monitoring environmental parameters is being accomplished via the use of a Logic Beach Bitlogger. The Bitlogger is a portable data loggings system consisting of a system base, input modules and a communication software package. Thermocouples are installed on selected electrical equipment and cables are run from the thermocouples to the input module of the Bitlogger. Temperature readings are taken at selected intervals, stored in memory, and downloaded periodically to a PC software program, i.e., Lotus. The data is formatted into tabular or graphical documents. Because of their versatility, Bitloggers are being used differently at the authors Nuclear facility. At the Salem Station (2 Units-4 loop Westinghouse PWR), a battery powered, fully portable, calibrated Bitlogger is located in an accessible area inside Containment where it monitors the temperature of various electrical equipment within the Pressurizer Enclosure. It is planned that close monitoring of the local hot spot temperatures in this area will allow them to adjust and reconcile the environmental qualification of the equipment

  14. ENIQ: European Network for Inspection Qualification

    International Nuclear Information System (INIS)

    Champigny, F.; Crutzen, S.; Lemaitre, P.

    1995-01-01

    Many countries are currently considering their own approach to inspection qualification and are carefully assessing experience to date. ENIQ, which stands for European Network for Inspection Qualification, groups the major part of the utilities in Western Europe. The general objective of ENIQ is to coordinate and manage at European level expertise and resources for the assessment and qualification of NDE inspection techniques and procedures, primarily for nuclear components. Also non-nuclear heavy duty components will be considered. Within ENIQ there is a growing consensus of opinion on the general principles of a European approach towards inspection qualification. In this paper the main activities, organization and actual status of ENIQ will be discussed

  15. Australian Qualifications Framework Lower-Level Qualifications: Pathways to Where for Young People?

    Science.gov (United States)

    Stanwick, John

    2005-01-01

    This study investigates where certificate I and II qualifications lead young people aged 15-24 years in terms of employment and further study. A prime motivation for young people undertaking these qualifications is to facilitate transition into the labour market. These qualifications are aimed at developing basic vocational skills or preparatory…

  16. ATLAS DBM Module Qualification

    Energy Technology Data Exchange (ETDEWEB)

    Soha, Aria [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Gorisek, Andrej [J. Stefan Inst., Ljubljana (Slovenia); Zavrtanik, Marko [J. Stefan Inst., Ljubljana (Slovenia); Sokhranyi, Grygorii [J. Stefan Inst., Ljubljana (Slovenia); McGoldrick, Garrin [Univ. of Toronto, ON (Canada); Cerv, Matevz [European Organization for Nuclear Research (CERN), Geneva (Switzerland)

    2014-06-18

    This is a technical scope of work (TSW) between the Fermi National Accelerator Laboratory (Fermilab) and the experimenters of Jozef Stefan Institute, CERN, and University of Toronto who have committed to participate in beam tests to be carried out during the 2014 Fermilab Test Beam Facility program. Chemical Vapour Deposition (CVD) diamond has a number of properties that make it attractive for high energy physics detector applications. Its large band-gap (5.5 eV) and large displacement energy (42 eV/atom) make it a material that is inherently radiation tolerant with very low leakage currents and high thermal conductivity. CVD diamond is being investigated by the RD42 Collaboration for use very close to LHC interaction regions, where the most extreme radiation conditions are found. This document builds on that work and proposes a highly spatially segmented diamond-based luminosity monitor to complement the time-segmented ATLAS Beam Conditions Monitor (BCM) so that, when Minimum Bias Trigger Scintillators (MTBS) and LUCID (LUminosity measurement using a Cherenkov Integrating Detector) have difficulty functioning, the ATLAS luminosity measurement is not compromised.

  17. Recommendations for the elaboration of a training program and personnel qualification of the regulatory body; Recomendaciones para la elaboracion de un programa de capacitacion y cualificacion de personal del organo regulador

    Energy Technology Data Exchange (ETDEWEB)

    Medina Gironzini, E., E-mail: medina@ipen.gob.pe [Instituto Peruano de Energia Nuclear (IPEN), Lima (Peru); Bonacossa de Almeida, C., E-mail: cbonacos@ird.gov.br [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Jimenez Rojas, M., E-mail: mjimenez@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS), Mexico City (Mexico); Pacheco Jimenez, R., E-mail: r.pacheco.mjimenez@iaea.org [International Atomic Energy Agency (IAEA), Vienna (Austria); Prendes Alonso, M.; Tomas Zerquera, J., E-mail: prendes@cphr.edu.cu, E-mail: jtomas@cphr.edu.cu [Centro de Proteccion e Higiene de las Radiaciones (CPHR), La Habana (Cuba)

    2013-07-01

    In this work are defined training methods and provides details on the qualifications of staff and the use of the method of the four quadrants where competencies are established: legal framework and regulatory responsibilities, technical disciplines, regulatory procedures and personal attributes. It is the first time that will make these recommendations in the region and is expected to be very useful for the regulator institutions.

  18. Preserving EQ as per CSA N290.13: EQ of equipment for CANDU NPP

    International Nuclear Information System (INIS)

    Bordeleau, H.

    2006-01-01

    EQ is basically a Quality Assurance process that ensures that required safety related equipment will performed their safety functions during accident generating harsh environmental condition. As any good Quality Assurance Program, EQ activities have to be imbedded in the normal tasks of the people at the plant in such a way that it is not an extra concern but part of the things to be assessed and done on a regular basis so that the EQ Status of the equipment will not be compromised. The experience shows us that even with brand new plants there are discrepancies between equipment designed to be installed and that installed (wrong model or wrong instrument). Improper installation was also found. To eliminate these mistakes it is recommended to have a thorough initial inspection during construction or commissioning and later at regular intervals during operation. To avoid new mistakes during maintenance, crews have to be properly qualified and trained on completed procedure with appropriate work report that will required to be scrutinized for possible common cause failure and OPEX report. Procurement and handling of equipment and spare parts require a thorough revision of procurement and storage practices to guarantee proper storage, availability and identification of equipment for EQ replacement. A shelf life program for degradable material shall be implemented. Condition monitoring program could be use to extend life of equipment or as a qualification methods, caution should be use to look very precisely to the critical parameters that need to be monitored and to carefully tailor the monitoring program. EQ program should also consider barriers, they are not EQ equipment; it is usually made out of non-ageing material like metal or concrete. But there could be sealing material used in conjunction with the barriers and these may need special care. The impact of EQ parameters changes related to services conditions, new technical data or condition monitoring has to be

  19. Data center equipment location and monitoring system

    DEFF Research Database (Denmark)

    2011-01-01

    A data center equipment location system includes both hardware and software to provide for location, monitoring, security and identification of servers and other equipment in equipment racks. The system provides a wired alternative to the wireless RFID tag system by using electronic ID tags...... connected to each piece of equipment, each electronic ID tag connected directly by wires to a equipment rack controller on the equipment rack. The equipment rack controllers then link over a local area network to a central control computer. The central control computer provides an operator interface......, and runs a software application program that communicates with the equipment rack controllers. The software application program of the central control computer stores IDs of the equipment rack controllers and each of its connected electronic ID tags in a database.; The software application program...

  20. Advantages of a program of quality control in the nuclear medicine equipment; Ventajas de un programa de control de calidad en los equipos de medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Trujillo Z, F.E.; Argumosa, E. [Departamento de Medicina Nuclear del Instituto Nacional de Cancerologia, Tlalpan, Mexico D.F. (Mexico); Herrera R, M.R. [Hospital Infantil de Mexico ' Federico Gomez' , Mexico D.F. (Mexico)

    2007-07-01

    In Nuclear Medicine more 90% of the entirety of the carried out procedures its are with diagnostic ends where it is acquired one or several images. This makes indispensable to have an appropriate operation of the dedicated equipment to produce images and also of those non former images, as the activity caliper, to assure an appropriate quality diagnoses not from the images and the correct dose administration to the patient. In this work the main calibrations that should be carried out and an example of the program of quality control of a gamma camera mark Siemens and model E.CAM are presented. Considerations that should take as for the radiological protection are exposed. Comments on the parameters that correct the required calibrations and the images taken place by an operation or inadequate calibrations are included. In conclusion, the necessity of a program that it contains as minimum the quality control of the gamma cameras and of the activity caliper, having as main advantages a good image quality diagnoses and to minimize the dose imparted the patient are exposed. (Author)

  1. ENERGY STAR Certified Imaging Equipment

    Data.gov (United States)

    U.S. Environmental Protection Agency — Certified models meet all ENERGY STAR requirements as listed in the Version 2.0 ENERGY STAR Program Requirements for Imaging Equipment that are effective as of...

  2. Prioritizing equipment for replacement.

    Science.gov (United States)

    Capuano, Mike

    2010-01-01

    It is suggested that clinical engineers take the lead in formulating evaluation processes to recommend equipment replacement. Their skill, knowledge, and experience, combined with access to equipment databases, make them a logical choice. Based on ideas from Fennigkoh's scheme, elements such as age, vendor support, accumulated maintenance cost, and function/risk were used.6 Other more subjective criteria such as cost benefits and efficacy of newer technology were not used. The element of downtime was also omitted due to the data element not being available. The resulting Periop Master Equipment List and its rationale was presented to the Perioperative Services Program Council. They deemed the criteria to be robust and provided overwhelming acceptance of the list. It was quickly put to use to estimate required capital funding, justify items already thought to need replacement, and identify high-priority ranked items for replacement. Incorporating prioritization criteria into an existing equipment database would be ideal. Some commercially available systems do have the basic elements of this. Maintaining replacement data can be labor-intensive regardless of the method used. There is usually little time to perform the tasks necessary for prioritizing equipment. However, where appropriate, a clinical engineering department might be able to conduct such an exercise as shown in the following case study.

  3. Space qualification of an experimental two-phase flow thermal management system

    International Nuclear Information System (INIS)

    Koonmen, J.P.; Carswell, L.C.; Kvansnak, M.A.

    1991-01-01

    The Weapons Laboratory will launch a space experiment in March 1991 to investigate the effects of extended microgravity on two-phase (liquid/vapor) flow. The qualification process for the experimental flight system hardware differs significantly from the process used for complex, high cost, long life space systems. Some development, qualification, and acceptance tests normally included in the test program of an operational space system were omitted because of the low program cost and low consequence of experiment failure. Key environment and functional qualification tests were performed, however, in an effort to reduce the risk of failure inherent in any space mission. The environmental qualification program included short duration vacuum chamber tests, reduced gravity missions onboard a National Aeronautics and Space Administration (NASA) test aircraft, and a complete series of shock and vibration tests. The functional qualification program centered on thermal-hydraulic system performance tests and a complete check-out of the unique telemetry system used to retrieve the experimental data from the payload. The test program also contains a number of acceptance and prelaunch validation tests to be performed as final verification of payloads readiness for spaceflight

  4. Cryogenic equipment

    International Nuclear Information System (INIS)

    Leger, L.; Javellaud, J.; Caro, C.; Gilguy, R.; Testard, O.

    1966-06-01

    The cryostats presented here were built from standard parts; this makes it possible to construct a great variety of apparatus at minimum cost. The liquid nitrogen and helium reservoirs were designed so as to reduce losses to a minimum, and so as to make the cryostats as autonomous as possible. The experimental enclosure which is generally placed in the lower part of the apparatus requires a separate study in every case. Furthermore, complete assemblies such as transfer rods, isolated traps and high vacuum valves, were designed with a similar regard for the economic aspects and for the need for standardization. This equipment thus satisfies a great variety of experimental needs; it is readily adaptable and the consumptions of helium and liquid nitrogen are very low. (authors) [fr

  5. Computer program for the calculation of stresses in rotary equipment discs; Programas de computo para el calculo de esfuerzos en discos de equipo rotatorio

    Energy Technology Data Exchange (ETDEWEB)

    Gutierrez Delgado, Wilson; Kubiak, Janusz; Serrano Romero, Luis Enrique [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

    1990-12-31

    In the preliminary design and diagnosis of rotary machines is very common to utilize simple calculation methods for the mechanical and thermal stresses, dynamic and thermodynamic analysis and flow of fluids in this machines (Gutierrez et al., 1989). The analysis with these methods provides the necessary results for the project initial stage of the machine. Later on, more complex tools are employed to refine the design of some machine components. In the Gutierrez report et al., (1989) 34 programs were developed for the preliminary design and diagnosis of rotating equipment; in this article, one of them is presented in which a method for the analysis of mechanical and thermal stresses is applied in discs of uniform or variable thickness that are normally found in turbomachines and rotary equipment. [Espanol] En el diseno preliminar y diagnostico de maquinas rotatorias es muy comun emplear metodos de calculo sencillos para el analisis de esfuerzos mecanicos y termicos, analisis dinamico y termodinamico y de flujo de fluidos en estas maquinas (Gutierrez et al., 1989). El analisis con estos metodos proporcionan los resultados necesarios para la etapa del proyecto inicial de la maquina. Posteriormente, para refinar el diseno de algunos componentes de la maquina, se aplican las herramientas mas complejas. En el informe de Gutierrez et al., (1989) se desarrollan 34 programas para el diseno preliminar y diagnostico de equipo rotatorio; en este articulo, se presenta uno de ellos, en el que se emplea un metodo para el analisis de esfuerzos mecanicos y termicos en discos de espesor constante o variable que se encuentran comunmente en turbomaquinas y en equipos rotatorios.

  6. Computer program for the calculation of stresses in rotary equipment discs; Programas de computo para el calculo de esfuerzos en discos de equipo rotatorio

    Energy Technology Data Exchange (ETDEWEB)

    Gutierrez Delgado, Wilson; Kubiak, Janusz; Serrano Romero, Luis Enrique [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

    1991-12-31

    In the preliminary design and diagnosis of rotary machines is very common to utilize simple calculation methods for the mechanical and thermal stresses, dynamic and thermodynamic analysis and flow of fluids in this machines (Gutierrez et al., 1989). The analysis with these methods provides the necessary results for the project initial stage of the machine. Later on, more complex tools are employed to refine the design of some machine components. In the Gutierrez report et al., (1989) 34 programs were developed for the preliminary design and diagnosis of rotating equipment; in this article, one of them is presented in which a method for the analysis of mechanical and thermal stresses is applied in discs of uniform or variable thickness that are normally found in turbomachines and rotary equipment. [Espanol] En el diseno preliminar y diagnostico de maquinas rotatorias es muy comun emplear metodos de calculo sencillos para el analisis de esfuerzos mecanicos y termicos, analisis dinamico y termodinamico y de flujo de fluidos en estas maquinas (Gutierrez et al., 1989). El analisis con estos metodos proporcionan los resultados necesarios para la etapa del proyecto inicial de la maquina. Posteriormente, para refinar el diseno de algunos componentes de la maquina, se aplican las herramientas mas complejas. En el informe de Gutierrez et al., (1989) se desarrollan 34 programas para el diseno preliminar y diagnostico de equipo rotatorio; en este articulo, se presenta uno de ellos, en el que se emplea un metodo para el analisis de esfuerzos mecanicos y termicos en discos de espesor constante o variable que se encuentran comunmente en turbomaquinas y en equipos rotatorios.

  7. Follow-up of the evolution of the characteristics and performance of the equipments tested during a KALI campaign

    International Nuclear Information System (INIS)

    Rouaud, J.

    1985-01-01

    One of the four parts of the K1 qualification of the 1E equipments concerns the design basis accidents. The KALI loops allows to create the thermodynamic conditions of these accidents. This paper presents the PROCESS II which concerns the installation of the equipment in conditions representative of those met in nuclear power plants, the control assurance before, during and after the thermodynamic test. A list of qualification tests carried out on the KALI loop is finally given [fr

  8. Software qualification in safety applications

    International Nuclear Information System (INIS)

    Lawrence, J.D.

    2000-01-01

    The developers of safety-critical instrumentation and control systems must qualify the design of the components used, including the software in the embedded computer systems, in order to ensure that the component can be trusted to perform its safety function under the full range of operating conditions. There are well known ways to qualify analog systems using the facts that: (1) they are built from standard modules with known properties; (2) design documents are available and described in a well understood language; (3) the performance of the component is constrained by physics; and (4) physics models exist to predict the performance. These properties are not generally available for qualifying software, and one must fall back on extensive testing and qualification of the design process. Neither of these is completely satisfactory. The research reported here is exploring an alternative approach that is intended to permit qualification for an important subset of instrumentation software. The research goal is to determine if a combination of static analysis and limited testing can be used to qualify a class of simple, but practical, computer-based instrumentation components for safety application. These components are of roughly the complexity of a motion detector alarm controller. This goal is accomplished by identifying design constraints that enable meaningful analysis and testing. Once such design constraints are identified, digital systems can be designed to allow for analysis and testing, or existing systems may be tested for conformance to the design constraints as a first step in a qualification process. This will considerably reduce the cost and monetary risk involved in qualifying commercial components for safety-critical service

  9. Hybrid Qualifications Country report Denmark

    DEFF Research Database (Denmark)

    Jørgensen, Christian Helms

    2010-01-01

    The report explores the institutional and functional relations between the higher education (tertiary sector) and vocational education (higher secondary education) and the labour market. In the report are included descriptions of the history, funding, outcomes, institutional realisation and term ...... and range of hybrid qualifications in the national system. In addition some recommendations for constructive further developments are given.......The report explores the institutional and functional relations between the higher education (tertiary sector) and vocational education (higher secondary education) and the labour market. In the report are included descriptions of the history, funding, outcomes, institutional realisation and term...

  10. The qualification of reactor operators

    International Nuclear Information System (INIS)

    Lima, J.M. de; Soares, H.V.

    1981-01-01

    The qualification and performance of nuclear power personnel have an important influence on the availability and safety operation of these plants. This paper describes the Brazilian rules and norms established by the CNEN-Brazilian Atomic Energy Comission, as well as policy of other countries concerning training requirements and experiences of nuclear power reactor operators. Some coments are made about the im pact of the march 1979 Three Mile Island accident on upgrading the reactor training requirements in U.S.A. and its international implication. (Author) [pt

  11. Appearance, discrimination, and reaction qualifications

    OpenAIRE

    Mason, Andrew

    2016-01-01

    When are selectors for advantaged social positions morally justified in giving weight to the appearance of the candidates? In order to address this issue adequately, we need to know when a person’s appearance can be a legitimate qualification for a position. Some of the hardest cases are jobs that involve interacting with clients or customers who prefer to deal with good-looking employees or who respond more favourably to them. But there is also a wide range of difficult cases in which an unc...

  12. Commercial waste and spent fuel packaging program. Annual report

    International Nuclear Information System (INIS)

    Hakl, A.R.

    1981-10-01

    This document is a report of activities performed by Westinghouse Advanced Energy Systems Division - Nevada Operations in meeting subtask objectives described in the Nevada Nuclear Waste Storage Investigations (NNWSI) Project Plan and revised planning documentation for Fiscal Year (FY) 1981. Major activities included: completion of the first fuel exchange in the Spent Fuel Test - Climax program; plasma arc welder development; modification and qualification of a canister cutter; installation, and activation of a remote area monitor, constant air monitor and an alpha/beta/gamma counting system; qualification of grapples required to handle pressurized water reactor or boiling water reactor fuel and high level waste (HLW) logs; data acquisition from the 3 kilowatt soil temperature test, 2 kw fuel temperature test, and 2 kw drywell test; calorimetry of the fuel assembly used in the fuel temperature test; evaluation of moisture accumulation in the drywells and recommendations for proposed changes; revision of safety assessment document to include HLW log operations; preparation of quality assurance plan and procedures; development and qualification of all equipment and procedures to receive, handle and encapsulate both the HLW log and spent fuel for the basalt waste isolation program/near surface test facility program; preliminary studies of both the requirements to perform waste packaging for the test and evaluation facility and a cask storage program for the DOE Interim Spent Fuel Management program; and remote handling operations on radioactive source calibration in support of other contractors

  13. Review of qualifications for fuel assembly fabrication

    International Nuclear Information System (INIS)

    Slabu, Dan; Zemek, Martin; Hellwig, Christian

    2013-01-01

    The required quality of nuclear fuel in industrial production can only be assured by applying processes in fabrication and inspection, which are well mastered and have been proven by an appropriate qualification. The present contribution shows the understanding and experiences of Axpo with respect to qualifications in the frame of nuclear fuel manufacturing and reflects some related expectations of the operator. (orig.)

  14. Qualification tests for a dosimetry system

    International Nuclear Information System (INIS)

    Anon.

    2005-01-01

    The report of qualification tests for personnel dosemeters is detailed. Qualification test for the energy response and the incidence angle is given. The procedure of test is resumed. Different coefficients of conversion used in these tests are given in tables. (N.C.)

  15. 48 CFR 1553.209 - Contractor qualifications.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 6 2010-10-01 2010-10-01 true Contractor qualifications. 1553.209 Section 1553.209 Federal Acquisition Regulations System ENVIRONMENTAL PROTECTION AGENCY CLAUSES AND FORMS FORMS Prescription of Forms 1553.209 Contractor qualifications. ...

  16. 48 CFR 253.209 - Contractor qualifications.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 3 2010-10-01 2010-10-01 false Contractor qualifications. 253.209 Section 253.209 Federal Acquisition Regulations System DEFENSE ACQUISITION REGULATIONS SYSTEM, DEPARTMENT OF DEFENSE CLAUSES AND FORMS FORMS Prescription of Forms 253.209 Contractor qualifications. ...

  17. 48 CFR 53.209 - Contractor qualifications.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 2 2010-10-01 2010-10-01 false Contractor qualifications. 53.209 Section 53.209 Federal Acquisition Regulations System FEDERAL ACQUISITION REGULATION (CONTINUED) CLAUSES AND FORMS FORMS Prescription of Forms 53.209 Contractor qualifications. ...

  18. From qualification design to training design using ECVET principles

    International Nuclear Information System (INIS)

    Ceclan, Mihail; Wastin, Franck

    2017-01-01

    The Joint Research Centre of European Commission was designated in 2009 as Operating agent of European Human Resources Observatory - in Nuclear (EHRO@N). EHRO@N identified the nuclear sector's major challenges: to fill@in the 30 % gap between HR demand and supply in decommissioning and to adapt nuclear E and T system to comply more to the labour market demands. The process of nuclear training system adaptation to the labour market needs is based on the design of the flexible qualifications (unit based qualifications) using European Credit system for Vocational Education and Training (ECVET) principles. The process of ECVET implementation in the nuclear energy sector is ongoing since 2011 and is based on the strategy and road map developed by EHRO-N. The current paper presents the latest developments on the designing of training programs based on exit outcomes.

  19. From qualification design to training design using ECVET principles

    Energy Technology Data Exchange (ETDEWEB)

    Ceclan, Mihail; Wastin, Franck [European Commission Joint Research Centre, Petten (Netherlands). Directorate Nuclear Safety and Security

    2017-05-15

    The Joint Research Centre of European Commission was designated in 2009 as Operating agent of European Human Resources Observatory - in Nuclear (EHRO@N). EHRO@N identified the nuclear sector's major challenges: to fill@in the 30 % gap between HR demand and supply in decommissioning and to adapt nuclear E and T system to comply more to the labour market demands. The process of nuclear training system adaptation to the labour market needs is based on the design of the flexible qualifications (unit based qualifications) using European Credit system for Vocational Education and Training (ECVET) principles. The process of ECVET implementation in the nuclear energy sector is ongoing since 2011 and is based on the strategy and road map developed by EHRO-N. The current paper presents the latest developments on the designing of training programs based on exit outcomes.

  20. THE PROFESSIONAL QUALIFICATION SOLIDARY EXTENSION PROJECT AT ELECTRONICS: TECHNICAL AUXILIAR

    Directory of Open Access Journals (Sweden)

    Glaucio Lopes Ramos

    2009-10-01

    Full Text Available This paper has the objective to present the extension course “professional qualification solidary extension project at electronics: technical auxiliar” in the Electrical Engineering course in the University Center of Belo Horizonte, as a professional qualification activity that make possible to young, adults and elderly people from poor communities the social inclusion and an opportunity to improve their access to the labor market. The course is part of extension program of Uni-BH, UniTrabalho e Renda, that is offered since 2006. The responsible for the course are professors and students of the Electrical Engineering course, and an electricity project is also offered. This paper presents the results of an evaluation that is made for the students at the beginning and at the end of the course and showed that the concepts had been assimilated by the students and the expectation of them related to the insertion at labor market is also improved.