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Sample records for qualification criteria status

  1. Seismic qualification of piping systems based on strain criteria

    International Nuclear Information System (INIS)

    Peters, K.; Rangette, A.

    1988-01-01

    Typical LMFBR piping is characterized by elevated temperature and low pressure levels. Taking into account operational conditions only these characteristics demand for and allow flexible piping design. The overestimation of the damage potential of seismic loading by e.g. improper failure criteria usually contradicts operational needs producing the known result of excessive ''snubberism'' and reduction of operational margins. As a matter of fact, due to its transiency seismic loading is essentially secondary provoking the natural design requirement ductility instead of stiffness and rigidity - i.e. exclusion of failure by strain control instead of stress control - and thus avoiding the LMFBR typical competition between operational needs and seismic qualification. The design requirement ductility needs judgement mechanisms, i.e. suitable load descriptions, allowed strain levels and strain evaluation tools. A simplified method for strain range estimation and the underlying basic ideas are roughly outlined. The status of verification and experience gained so far is described. The results achieved suggest that the qualification of piping based on ductility requirement controlled by strain criteria is not out of reach. (author)

  2. Qualification criteria for persons responsible for radiation protection

    International Nuclear Information System (INIS)

    Wehner, G

    1980-01-01

    A survey of the qualification criteria included in the German atomic law (Atomic Energy Act, Radiological Protection Ordinance and X-ray Protection Ordinance) for persons responsible for radiation protection is given. Especially the various activities for which a health physics officer is required, the range of qualification in each case and the way the qualification has to be proved, are pointed out. Also the different guides that are issued to complete the legal requirements are mentioned. The definitions of the term qualification for health physics given in the different guides are cited and it is shown, that the qualification of a healt physics officer has to be based on the three criteria (I) vocational training. (II) professional experience and (III) the necessary knowledge in radiation protection. (orig./HP) [de

  3. Qualification criteria verification for aisi-4340 steel suspension lug

    International Nuclear Information System (INIS)

    Riaz, M.A.; Alam, M.

    2005-01-01

    All external loads carried underneath an aircraft are mounted onto it through mechanism generally known as suspension system. The externally mounted attachments like bombs, missiles and fuel tanks etc. experience enormous aerodynamic and inertial forces in the flights. These forces are transferred to the interface point of suspension system, known as 'Suspension Lug'. Thus lugs are considered critical component and have extremely stringent qualification criteria standards used in the aviation industry in USA, Europe, Russia, etc. Different standards prevail in different parts of the world about qualification and testing of these lugs. As Pakistan is entering into aviation industry, therefore there is a need to fulfill the requirements of these standards, to suit Pakistani environment. The suspension lug under study is 2000 Ibs. load class made from AISI-4340 Steel having good mechanical properties as per required standard. The manufacturing processes included forging, machining and vacuum heat treatment. The prototypes of suspension lugs were manufactured in the local industry and subjected to the required mechanical tests such as tensile testing at 5 to 35 degree angles. Impact testing at cryogenic temperatures of -50 to -70 degree C, and breaking load testing were performed. The acceptable results were obtained and mechanical testing for qualification of lugs was finalized and standardized. The options were compared with practical viability, utilization of product and cost effectiveness. (author)

  4. LTP fibre injector qualification and status

    International Nuclear Information System (INIS)

    Bogenstahl, J; Cunningham, L; Fitzsimons, E D; Hough, J; Killow, C J; Perreur-Lloyd, M; Robertson, D; Rowan, S; Ward, H

    2009-01-01

    This paper presents the current state of the LISA Technology Package (LTP) fibre injector qualification project in terms of vibration and shock tests. The fibre injector is a custom built part and therefore must undergo a full space qualification process. The mounting structure and method for sinusoidal vibration and random vibration tests as well as shock tests will be presented. Furthermore a proposal will be presented to use the fibre injector pair qualification model to build an optical prototype bench. The optical prototype bench is a full-scale model of the flight model. It will be used for development and rehearsal of all the assembly stages of the flight model and will provide an on-ground simulator for investigation as an updated engineering model.

  5. ENIQ: European Network for Inspection Qualification: Status report

    International Nuclear Information System (INIS)

    Champigny, F.; Sandberg, U.; Crutzen, S.; Lemaitre, P.

    1998-01-01

    The European Network for Inspection Qualification (ENIQ) groups the major part of the nuclear power plant operators in the European Union (and Switzerland). The main objective of ENIQ is to co-ordinate and manage at European level expertise and resources for the qualification of NDE inspection systems, primarily for nuclear components. In this paper the main activities, organisation and actual status of ENIQ are discussed. (author)

  6. Qualification criteria to certify a package for air transport of plutonium

    International Nuclear Information System (INIS)

    1977-12-01

    The document describes qualification criteria developed by the U.S. Nuclear Regulatory Commission to certify a package for air transport of plutonium. Included in the document is a discussion of aircraft accident conditions and a summary of the technical basis for the qualification criteria. The criteria require prototype packages to be subjected to various individual and sequential tests that simulate the conditions produced in severe aircraft accidents. Specific post-test acceptance standards are prescribed for each of the three safety functions of a package. The qualification criteria also prescribe certain operational controls to be exercised during transport

  7. 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)

  8. An analysis of the qualification criteria for small radioactive material shipping packages

    Energy Technology Data Exchange (ETDEWEB)

    McClure, J.D.

    1983-05-01

    The RAM package design certification process has two important elements, testing and acceptance. These terms sound very similar but they have specific meanings. Qualification testing in the context of this study is the imposition of simulated accident test conditions upon the candidate package design. (Normal transportation environments may also be included.) Following qualification testing, the acceptance criteria provide the performance levels which, if demonstrated, indicate the ability of the RAM package to sustain the severity of the qualification testing sequence and yet maintain specified levels of package integrity. This study has used Severities of Transportation Accidents as a data base to examine the regulatory test criteria which are required to be met by small packages containing Type B quantities of radioactive material (RAM). The basic findings indicate that the present regulatory test standards provide significantly higher levels of protection for the surface transportation modes (truck, rail) than for RAM packages shipped by aircraft. It should also be noted that various risk assessment studies have shown that the risk to the public due to severe transport accidents by surface and air transport modes is very low. A key element in this study was the quantification of the severity of the transportation accident environment and the severity of the present qualification test standards (called qualification test standards in this document) so that a direct comparison could be made between them to assess the effectiveness of the existing qualification test standards. The manner in which this was accomplished is described.

  9. An analysis of the qualification criteria for small radioactive material shipping packages

    International Nuclear Information System (INIS)

    McClure, J.D.

    1983-05-01

    The RAM package design certification process has two important elements, testing and acceptance. These terms sound very similar but they have specific meanings. Qualification testing in the context of this study is the imposition of simulated accident test conditions upon the candidate package design. (Normal transportation environments may also be included.) Following qualification testing, the acceptance criteria provide the performance levels which, if demonstrated, indicate the ability of the RAM package to sustain the severity of the qualification testing sequence and yet maintain specified levels of package integrity. This study has used Severities of Transportation Accidents as a data base to examine the regulatory test criteria which are required to be met by small packages containing Type B quantities of radioactive material (RAM). The basic findings indicate that the present regulatory test standards provide significantly higher levels of protection for the surface transportation modes (truck, rail) than for RAM packages shipped by aircraft. It should also be noted that various risk assessment studies have shown that the risk to the public due to severe transport accidents by surface and air transport modes is very low. A key element in this study was the quantification of the severity of the transportation accident environment and the severity of the present qualification test standards (called qualification test standards in this document) so that a direct comparison could be made between them to assess the effectiveness of the existing qualification test standards. The manner in which this was accomplished is described

  10. 10 CFR 50.76 - Licensee's change of status; financial qualifications.

    Science.gov (United States)

    2010-01-01

    ... the financial qualifications information that would be required for obtaining an initial operating license as specified in § 50.33(f)(2). The financial qualifications information must address the first... 10 Energy 1 2010-01-01 2010-01-01 false Licensee's change of status; financial qualifications. 50...

  11. Status of the beryllium tile bonding qualification activities for the manufacturing of the ITER first wall

    International Nuclear Information System (INIS)

    Mitteau, Raphaël; Eaton, R.; Perez, G.; Zacchia, F.; Banetta, S.; Bellin, B.; Gervash, A.; Glazunov, D.; Chen, J.

    2015-01-01

    The preparation of the manufacturing of the ITER first wall involves a qualification stage. The qualification aims at demonstrating that manufacturers can deliver the needed reliability and quality for the beryllium to copper bond, before the manufacturing can commence. The qualification is done on semi-prototype, containing relevant features relative to the beryllium armour (about 1/6 of the panel size). The qualification is done by the participating parties, firstly by a manufacturing semi-prototype and then by testing it under heat flux. One semi-prototype is manufactured and is being tested, and further from other manufacturers are still to come. The qualification programme is accompanied by bond defect investigations, which aim at defining defect acceptance criteria. Qualification and defect acceptance programme are supported by thermal and stress analyses, with good agreement regarding the thermal results, and some insights about the governing factors to bond damage.

  12. Status of the beryllium tile bonding qualification activities for the manufacturing of the ITER first wall

    Energy Technology Data Exchange (ETDEWEB)

    Mitteau, Raphaël, E-mail: Raphael.mitteau@iter.org [ITER Organization, Route de Vinon-sur-Verdon, CS 90 046, 13067 St. Paul Lez Durance Cedex (France); Eaton, R.; Perez, G. [ITER Organization, Route de Vinon-sur-Verdon, CS 90 046, 13067 St. Paul Lez Durance Cedex (France); Zacchia, F.; Banetta, S.; Bellin, B. [Fusion for Energy, Josep Pla 2, Torres Diagonal Litoral B3, 08019 Barcelona (Spain); Gervash, A.; Glazunov, D. [Efremov Research Institute, 189631 St. Petersburg (Russian Federation); Chen, J. [Southwestern Institute of Physics, Huangjing Road, Chengdu 610225 (China)

    2015-10-15

    The preparation of the manufacturing of the ITER first wall involves a qualification stage. The qualification aims at demonstrating that manufacturers can deliver the needed reliability and quality for the beryllium to copper bond, before the manufacturing can commence. The qualification is done on semi-prototype, containing relevant features relative to the beryllium armour (about 1/6 of the panel size). The qualification is done by the participating parties, firstly by a manufacturing semi-prototype and then by testing it under heat flux. One semi-prototype is manufactured and is being tested, and further from other manufacturers are still to come. The qualification programme is accompanied by bond defect investigations, which aim at defining defect acceptance criteria. Qualification and defect acceptance programme are supported by thermal and stress analyses, with good agreement regarding the thermal results, and some insights about the governing factors to bond damage.

  13. 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)

  14. What are the qualifications and selection criteria for women to be appointed to society journal editorial boards?

    Science.gov (United States)

    Tomizawa, Yasuko

    2014-02-01

    Japan ranks extremely low in global ranking of gender equality. It is not easy for female doctors to acquire leadership positions in member societies of the Japanese Association of Medical Science (JAMS). Very few women are included on editorial boards of English medical journals in Japan. Furthermore, until last year, there had been no female editors in English language journals of surgical societies. The qualifications and criteria for selecting editorial board members of medical journals should be clarified. Medical journals in Japan would gain diversity by including women on editorial boards in the same proportion as women membership in the corresponding medical societies.

  15. 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

  16. 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

  17. Qualifications of and acceptance criteria for transporting special form radioactive material

    International Nuclear Information System (INIS)

    Hovingh, J.

    1991-01-01

    A special form radioactive material is a radioactive material that is in an inert, insoluble, indispersible form such that even in the event of an accident, it will not be dispersed into the environment in a way that could have an adverse impact on public health and safety. Methods of qualifying a special form radioactive material are discussed. Interpretation of acceptance criteria are proposed for the transportation of Type B quantities of a special form radioactive material. 11 refs

  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. Program criteria for subseabed disposal of radioactive waste: site qualification plan

    International Nuclear Information System (INIS)

    Laine, E.P.; Anderson, D.R.; Hollister, C.D.

    1982-05-01

    This document describes the evolving methodology which is being used to identify, and study sites in subseabed geological formations which may be candidates for use as repositories for high-level nuclear waste. Two primary criteria guide all phases of this work: the stability and barrier criteria. The stability criterion defines areas of the seabed that are unlikely to be disturbed by tectonic forces and oceanographic changes durig the lifetime of a waste repository. The barrier criterion defines those subseabed geological formations most likely to form an effective barrier to the release of radionuclides. Because of the large area of the oceans, a phased approach has been adopted through which successively smaller areas of the sea floor are studied in ever greater detail. The first phase, which is complete, has identified abyssal clay deposits that are remote from tectonic boundaries and continental margins as being the regions (>10 5 km 2 ) on the sea floor within which acceptable sites might be most readily identified. The second phase involves downgrading less desirable areas (>10 4 km 2 ) within these regions, using archived seismic reflection profiling, sediment cores, and oceanographic data. This winnowing process identifies locations about one degree square (greater than or equal to 10 4 km 2 ) for more detailed field studies during the first part of the third phase. From these locations candidate sites (less than or equal to 10 4 km 2 ) will be chosen based on detailed geological and geophysical surveying. In the second part of the third phase, detailed monitoring of the candidate sites will begin to determine long-term baseline conditions. After monitoring is underway, a pilot repository will be established using waste canisters. Based on this work, a site selection/rejection report will be written. The fourth and last phase will involve extended monitoring of oceanographic conditions at each repository

  20. ON-GOING STATUS OF KJRR FUEL (U-7MO) QUALIFICATION

    Energy Technology Data Exchange (ETDEWEB)

    Yim, J. S.; Tahk, Y. W.; Oh, J. Y.; Kim, H. J.; Kong, E. H.; Lee, B. H.; Park, J. M.; Jeong, Y. J.; Lee, K. H.; Kim, S. H.; Lee, C. T.; Beasley, A. A.; Choi, Y. J.; Crawford, D. S.; Nielsen, J. W.; Woolstenhulme, N. E.

    2017-03-01

    In order to cope with global shortage of Mo-99 supplies and with growing demand of neutron transmutation doping, KJRR construction plan has been launched since April 2012 to provide self-sufficiency of domestic RI demand, and to extend Si doping capacity for power device market growth. Through comprehensive surveillance of the fuels in-reactor behavior, KAERI has selected the fuel meat of U-7%Mo dispersion in an aluminum matrix with 5wt%Si for the KJRR fuel. As part of the efforts for fuel licensing and qualification of the KJRR fuel, an LTA irradiation test at the ATR started from November 2015 was successfully completed by reaching at 219 EFPD in the end of February 2017. Together with the results of HAMP-1 already completed irradiation and PIE, the successful irradiation of the LTA also demonstrates the fuel integrity under more rigorous conditions than the KJRR operation conditions. This paper updates the current status of the KJRR U7Mo (8 g-U/cm3) LTA irradiation and PIE plan up to date as of February 2017.

  1. 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.

  2. Status on the Finnish activities regarding qualification of programmable automation systems

    International Nuclear Information System (INIS)

    Juslin, K.

    1995-01-01

    The research work on qualification of programmable automation system is described which describe the development of methods, tools and practices for the evaluation and licensing of safety critical programmable automation systems. 26 refs

  3. Status report on preparation of IAEA guidelines for qualification of research reactor fuels

    International Nuclear Information System (INIS)

    Snelgrove, J.L.

    2007-01-01

    The International Atomic Energy Agency, through a consultancy, is preparing a document describing good practices for the qualification of research reactor fuel. The rationale for the preparation of the document and the document's organization and content are discussed. It is anticipated that the consultants will present a final draft to the IAEA by mid-December for editing and publication in 2008.

  4. Radiological procedures: Quality criteria and dose optimisation: French status

    International Nuclear Information System (INIS)

    Grenier, Ph.; Marshall-Depommier, E.; Bourguignon, M.; Beauvais-March, H.; Valero, M.; Lacronique, J.F.; Frijal, G.

    2001-01-01

    The Council Directive 97/43/Euratom of June 30 1997 on health protection of individuals against the dangers of ionising radiation in relation to medical exposure has come into force on May, 13 th 2000. French health directorate has entrusted the 'Office de Protection contre les Rayonnements Ionisants (OPRI)' together with the 'Societe Francaise de Radiologie' (SFR) to implement article 6 related to radiological procedures, in order to bring into operation the principle of optimisation. The most frequent diagnostic radiology and interventional procedures (120 protocols) have been standardised in writing. Corresponding patient dosimetry has been determined from measurements on site, calculations and literature review. The criteria for optimisation have been highlighted for each protocols. With the help of the French Society of Medical Physicists (SFPM), measurements are being collected on a large scale in France. Then, knowing more precisely the patient dosimetry of each protocol, referral criteria will be reviewed and prioritised to implement the principle of justification. The authors will present and explain the chosen methodology (methodology of the Accreditation and Evaluation in Health Agency: ANAES) for completing this two years workload program, and will demonstrate clinical examples as well. (author)

  5. Diagnostic accuracy of the Salzburg EEG criteria for non-convulsive status epilepticus

    DEFF Research Database (Denmark)

    Leitinger, Markus; Trinka, Eugen; Gardella, Elena

    2016-01-01

    Background Several EEG criteria have been proposed for diagnosis of non-convulsive status epilepticus (NCSE), but none have been clinically validated. We aimed to assess the diagnostic accuracy of the EEG criteria proposed by a panel of experts at the fourth London–Innsbruck Colloquium on Status...... Epilepticus in Salzburg, 2013 (henceforth called the Salzburg criteria). Methods We did a retrospective, diagnostic accuracy study using EEG recordings from patients admitted for neurological symptoms or signs to three centres in two countries (Danish Epilepsy Centre, Dianalund, Denmark; Aarhus University...

  6. Evaluation of ISDP Batch 2 Qualification Compliance to 512-S, DWPF, Tank Farm, and Saltstone Waste Acceptance Criteria

    Energy Technology Data Exchange (ETDEWEB)

    Shafer, A.

    2010-05-05

    The purpose of this report is to document the acceptability of the second macrobatch (Salt Batch 2) of Tank 49H waste to H Tank Farm, DWPF, and Saltstone for operation of the Interim Salt Disposition Project (ISDP). Tank 49 feed meets the Waste Acceptance Criteria (WAC) requirements specified by References 11, 12, and 13. Salt Batch 2 material is qualified and ready to be processed through ARP/MCU to the final disposal facilities.

  7. Assessing health status and quality-of-life instruments: attributes and review criteria.

    Science.gov (United States)

    Aaronson, Neil; Alonso, Jordi; Burnam, Audrey; Lohr, Kathleen N; Patrick, Donald L; Perrin, Edward; Stein, Ruth E

    2002-05-01

    The field of health status and quality of life (QoL) measurement - as a formal discipline with a cohesive theoretical framework, accepted methods, and diverse applications--has been evolving for the better part of 30 years. To identify health status and QoL instruments and review them against rigorous criteria as a precursor to creating an instrument library for later dissemination, the Medical Outcomes Trust in 1994 created an independently functioning Scientific Advisory Committee (SAC). In the mid-1990s, the SAC defined a set of attributes and criteria to carry out instrument assessments; 5 years later, it updated and revised these materials to take account of the expanding theories and technologies upon which such instruments were being developed. This paper offers the SAC's current conceptualization of eight key attributes of health status and QoL instruments (i.e., conceptual and measurement model; reliability; validity; responsiveness; interpretability; respondent and administrative burden; alternate forms; and cultural and language adaptations) and the criteria by which instruments would be reviewed on each of those attributes. These are suggested guidelines for the field to consider and debate; as measurement techniques become both more familiar and more sophisticated, we expect that experts will wish to update and refine these criteria accordingly.

  8. 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

  9. Salzburg Consensus Criteria for Non-Convulsive Status Epilepticus--approach to clinical application.

    Science.gov (United States)

    Leitinger, M; Beniczky, S; Rohracher, A; Gardella, E; Kalss, G; Qerama, E; Höfler, J; Hess Lindberg-Larsen, A; Kuchukhidze, G; Dobesberger, J; Langthaler, P B; Trinka, E

    2015-08-01

    Salzburg Consensus Criteria for diagnosis of Non-Convulsive Status Epilepticus (SCNC) were proposed at the 4th London-Innsbruck Colloquium on status epilepticus in Salzburg (2013). We retrospectively analyzed the EEGs of 50 consecutive nonhypoxic patients with diagnoses of nonconvulsive status epilepticus (NCSE) at discharge and 50 consecutive controls with abnormal EEGs in a large university hospital in Austria. We implemented the American Clinical Neurophysiology Society's Standardized Critical Care EEG Terminology, 2012 version (ACNS criteria) to increase the test performance of SCNC. In patients without preexisting epileptic encephalopathy, the following criteria were applied: (1) more than 25 epileptiform discharges (ED) per 10-second epoch, i.e., >2.5/s and (2) patients with EDs ≤ 2.5/s or rhythmic delta/theta activity (RDT) exceeding 0.5/s AND at least one of the additional criteria: (2a) clinical and EEG improvements from antiepileptic drugs (AEDs), (2b) subtle clinical phenomena, or (2c) typical spatiotemporal evolution. In case of fluctuation without evolution or EEG improvement without clinical improvement, "possible NCSE" was diagnosed. For identification of RDT, the following criteria were compared: (test condition A) continuous delta-theta activity without further rules, (B) ACNS criterion for rhythmic delta activity (RDA), and (C) ACNS criteria for RDA and fluctuation. False positive rate in controls dropped from 28% (condition A) to 2% (B) (p = 0.00039) and finally to 0% (C) (p = 0.000042). Application of test condition C in the group with NCSE gives one false negative (2%). Various EEG patterns were found in patients with NCSE: (1) 8.2%, (2a) 2%, (2b) 12.2%, and (2c) 32.7%. Possible NCSE was diagnosed based on fluctuations in 57.1% and EEG improvement without clinical improvement in 14.2%. The modified SCNC with refined definitions including the ACNS terminology leads to clinically relevant and statistically significant reduction of false

  10. 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

  11. Restraint status improves the predictive value of motor vehicle crash criteria for pediatric trauma team activation.

    Science.gov (United States)

    Bozeman, Andrew P; Dassinger, Melvin S; Recicar, John F; Smith, Samuel D; Rettiganti, Mallikarjuna R; Nick, Todd G; Maxson, Robert T

    2012-12-01

    Most trauma centers incorporate mechanistic criteria (MC) into their algorithm for trauma team activation (TTA). We hypothesized that characteristics of the crash are less reliable than restraint status in predicting significant injury and the need for TTA. We identified 271 patients (age, <15 y) admitted with a diagnosis of motor vehicle crash. Mechanistic criteria and restraint status of each patient were recorded. Both MC and MC plus restraint status were evaluated as separate measures for appropriately predicting TTA based on treatment outcomes and injury scores. Improper restraint alone predicted a need for TTA with an odds ratios of 2.69 (P = .002). MC plus improper restraint predicted the need for TTA with an odds ratio of 2.52 (P = .002). In contrast, the odds ratio when using MC alone was 1.65 (P = .16). When the 5 MC were evaluated individually as predictive of TTA, ejection, death of occupant, and intrusion more than 18 inches were statistically significant. Improper restraint is an independent predictor of necessitating TTA in this single-institution study. Copyright © 2012 Elsevier Inc. All rights reserved.

  12. Adjusting a cancer mortality-prediction model for disease status-related eligibility criteria

    Directory of Open Access Journals (Sweden)

    Kimmel Marek

    2011-05-01

    Full Text Available Abstract Background Volunteering participants in disease studies tend to be healthier than the general population partially due to specific enrollment criteria. Using modeling to accurately predict outcomes of cohort studies enrolling volunteers requires adjusting for the bias introduced in this way. Here we propose a new method to account for the effect of a specific form of healthy volunteer bias resulting from imposing disease status-related eligibility criteria, on disease-specific mortality, by explicitly modeling the length of the time interval between the moment when the subject becomes ineligible for the study, and the outcome. Methods Using survival time data from 1190 newly diagnosed lung cancer patients at MD Anderson Cancer Center, we model the time from clinical lung cancer diagnosis to death using an exponential distribution to approximate the length of this interval for a study where lung cancer death serves as the outcome. Incorporating this interval into our previously developed lung cancer risk model, we adjust for the effect of disease status-related eligibility criteria in predicting the number of lung cancer deaths in the control arm of CARET. The effect of the adjustment using the MD Anderson-derived approximation is compared to that based on SEER data. Results Using the adjustment developed in conjunction with our existing lung cancer model, we are able to accurately predict the number of lung cancer deaths observed in the control arm of CARET. Conclusions The resulting adjustment was accurate in predicting the lower rates of disease observed in the early years while still maintaining reasonable prediction ability in the later years of the trial. This method could be used to adjust for, or predict the duration and relative effect of any possible biases related to disease-specific eligibility criteria in modeling studies of volunteer-based cohorts.

  13. How different do visuo-tactile criteria assess caries lesions activity status on occlusal surfaces?

    DEFF Research Database (Denmark)

    Floriano, I; Bonini, G C; Matos, R

    2015-01-01

    the International Caries Detection and Assessment System with an additional criteria--Lesion Activity Assessment (ICDAS + LAA), and a reference examiner classified lesions regarding plaque stagnation, colour, lustre, cavities, depth and texture. Logistic regressions were used to test associations. For analyses, we...... lesions present lustre. CONCLUSION: Most clinical signs associated with active caries lesions were similar, but texture and severity tend to have a greater importance when using ICDAS + LAA for distinguishing caries activity status. Attention should be given to differences due to texture and lustre when...

  14. Communicating Conservation Status: How Different Statistical Assessment Criteria Affect Perceptions of Extinction Risk.

    Science.gov (United States)

    Song, Hwanseok; Schuldt, Jonathon P

    2017-09-01

    Although alternative forms of statistical and verbal information are routinely used to convey species' extinction risk to policymakers and the public, little is known about their effects on audience information processing and risk perceptions. To address this gap in literature, we report on an experiment that was designed to explore how perceptions of extinction risk differ as a function of five different assessment benchmarks (Criteria A-E) used by scientists to classify species within IUCN Red List risk levels (e.g., Critically Endangered, Vulnerable), as well as the role of key individual differences in these effects (e.g., rational and experiential thinking styles, environmental concern). Despite their normative equivalence within the IUCN classification system, results revealed divergent effects of specific assessment criteria: on average, describing extinction risk in terms of proportional population decline over time (Criterion A) and number of remaining individuals (Criterion D) evoked the highest level of perceived risk, whereas the single-event probability of a species becoming extinct (Criterion E) engendered the least perceived risk. Furthermore, participants scoring high in rationality (analytic thinking) were less prone to exhibit these biases compared to those low in rationality. Our findings suggest that despite their equivalence in the eyes of scientific experts, IUCN criteria are indeed capable of engendering different levels of risk perception among lay audiences, effects that carry direct and important implications for those tasked with communicating about conservation status to diverse publics. © 2016 Society for Risk Analysis.

  15. Participant roles of bullying in adolescence: Status characteristics, social behavior, and assignment criteria.

    Science.gov (United States)

    Pouwels, J Loes; Lansu, Tessa A M; Cillessen, Antonius H N

    2016-01-01

    This study had three goals. First, we examined the prevalence of the participant roles of bullying in middle adolescence and possible gender differences therein. Second, we examined the behavioral and status characteristics associated with the participant roles in middle adolescence. Third, we compared two sets of criteria for assigning students to the participant roles of bullying. Participants were 1,638 adolescents (50.9% boys, M(age)  = 16.38 years, SD =.80) who completed the shortened participant role questionnaire and peer nominations for peer status and behavioral characteristics. Adolescents were assigned to the participant roles according to the relative criteria of Salmivalli, Lagerspetz, Björkqvist, Österman, and Kaukiainen (1996). Next, the students in each role were divided in two subgroups based on an additional absolute criterion: the Relative Only Criterion subgroup (nominated by less than 10% of their classmates) and the Absolute & Relative Criterion subgroup (nominated by at least 10% of their classmates). Adolescents who bullied or reinforced or assisted bullies were highly popular and disliked and scored high on peer-valued characteristics. Adolescents who were victimized held the weakest social position in the peer group. Adolescents who defended victims were liked and prosocial, but average in popularity and peer-valued characteristics. Outsiders held a socially weak position in the peer group, but were less disliked, less aggressive, and more prosocial than victims. The behavior and status profiles of adolescents in the participant roles were more extreme for the Absolute & Relative Criterion subgroup than for the Relative Only Criterion subgroup. © 2015 Wiley Periodicals, Inc.

  16. 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...

  17. Status, experience and future prospects for the development of probabilistic safety criteria

    International Nuclear Information System (INIS)

    1989-09-01

    During 27-31 January 1986 the IAEA held a Technical Committee Meeting on ''Status, Experience, and Future Prospects for the Development of Probabilistic Safety Criteria''. Participation included representation of essentially all countries with major developments in the area as well as the Nuclear Energy Agency of the OECD and CEC. Though it has to be recognized that in such a short time period it is impossible to resolve or even analyse all aspects of this complex issue, the present situation, the main problems and the directions for future work clearly emerged. This report was prepared by the members of the Technical Committee based on the opinions expressed and on the information available at the time of the meeting. The report also contains 20 papers presented at the meeting by participants. A separate abstract was prepared for each of these 20 papers. Refs, figs and tabs

  18. Global Trend In The Qualifications Of Medical Educators | Issa ...

    African Journals Online (AJOL)

    NPMCN) or its equivalents is the highest educational and professional qualification of clinical Medical Educators in Nigeria while PhD is the acceptable highest qualification for their basic medical sciences counterparts. This had been the status ...

  19. Does the evidence for an inverse relationship between serum vitamin D status and breast cancer risk satisfy the Hill criteria?

    OpenAIRE

    Mohr, Sharif B.; Gorham, Edward D.; Alcaraz, John E.; Kane, Christopher I.; Macera, Caroline A.; Parsons, J. Kellogg; Wingard, Deborah L.; Garland, Cedric F.

    2012-01-01

    A wide range of epidemiologic and laboratory studies combined provide compelling evidence of a protective role of vitamin D on risk of breast cancer. This review evaluates the scientific evidence for such a role in the context of the A.B. Hill criteria for causality, in order to assess the presence of a causal, inverse relationship, between vitamin D status and breast cancer risk. After evaluation of this evidence in the context of Hill’s criteria, it was found that the criteria for a causal ...

  20. Conservation Status of the Australian Humpback Dolphin (Sousa sahulensis) Using the IUCN Red List Criteria.

    Science.gov (United States)

    Parra, Guido J; Cagnazzi, Daniele

    2016-01-01

    Australian humpback dolphins (Sousa sahulensis) were recently described as a new species endemic to northern Australia and potentially southern New Guinea. We assessed the species conservation status against IUCN Red List Criteria using available information on their biology, ecology and threatening processes. Knowledge of population sizes and trends across the species range is lacking. Recent genetic studies indicate Australian humpback dolphins live in small and relatively isolated populations with limited gene flow among them. The available abundance estimates range from 14 to 207 individuals and no population studied to date is estimated to contain more than 104 mature individuals. The Potential Biological Removal method indicates populations are vulnerable to even low rates of anthropogenic mortality. Habitat degradation and loss is ongoing and expected to increase across the species range in Australia, and a continuing decline in the number of mature individuals is anticipated. Considering the available evidence and following a precautionary approach, we considered this species as Vulnerable under IUCN criterion C2a(i) because the total number of mature individuals is plausibly fewer than 10,000, an inferred continuing decline due to cumulative impacts, and each of the populations studied to date is estimated to contain fewer than 1000 mature individuals. Ongoing research efforts and recently developed research strategies and priorities will provide valuable information towards the future conservation and management of Australian humpback dolphins. © 2016 Elsevier Ltd. All rights reserved.

  1. Status policy and criteria for the remediation of sites with radioactive residues in China

    International Nuclear Information System (INIS)

    Yamin, Z.

    1999-01-01

    This paper introduces the status policy and criteria for remediation of sites with radioactive residues in China. We deal with the sites in difference patterns according to their circumstances. For the sites related with the decommissioning of the nuclear fuel cycle facilities, the programs for environmental restoration must be reviewed and approved by the State Environmental Protection Administration (SEPA). And the radioactive waste resulting from these facilities should be collected and eventually disposed of at the regional disposal repositories built by the country. For the sites related with use of radionuclides in medicine, research and industry, as well as the small scale extraction and processing of materials containing natural radionuclides, the provincial environmental authority is responsible for approving the restoration projects. These radioactive wastes should finally be sent to the special radioactive waste repositories built by the provincial environmental authorities. So far 21 waste repositories have been built in some provinces. More then 10 sites with radioactive residues have been restored. The standards for general public dose limit and soil residual radionuclides content have been established. (author)

  2. The application of strength and power related field tests in older adults : criteria, current status and a future perspective

    NARCIS (Netherlands)

    Regterschot, G. Ruben H.; Morat, Tobias; Folkersma, Marjanne; Zijlstra, Wiebren

    2015-01-01

    Leg muscle strength (LMS) and leg muscle power (LMP) are determinants of aspects of functional status and important parameters for measuring intervention effects in older adults. Field tests are often used for the evaluation of LMS and LMP in older persons. However, criteria important for the

  3. 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 ...

  4. 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

  5. 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.

  6. 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

  7. 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

  8. 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.

  9. 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

  10. Stack Flow Rate Changes and the ANSI/N13.1-1999 Qualification Criteria: Application to the Hanford Canister Storage Building Stack

    Energy Technology Data Exchange (ETDEWEB)

    Flaherty, Julia E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Glissmeyer, John A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2016-02-29

    The Canister Storage Building (CSB), located in the 200-East Area of the Hanford Site, is a 42,000 square foot facility used to store spent nuclear fuel from past activities at the Hanford Site. Because the facility has the potential to emit radionuclides into the environment, its ventilation exhaust stack has been equipped with an air monitoring system. Subpart H of the National Emissions Standards for Hazardous Air Pollutants requires that a sampling probe be located in the exhaust stack in accordance with criteria established by the American National Standards Institute/Health Physics Society Standard N13.1-1999, Sampling and Monitoring Releases of Airborne Radioactive Substances from the Stack and Ducts of Nuclear Facilities.

  11. 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

  12. Participant roles of bullying in adolescence: Status characteristics, social behavior, and assignment criteria

    NARCIS (Netherlands)

    Pouwels, J.L.; Lansu, T.A.M.; Cillessen, A.H.N.

    2016-01-01

    This study had three goals. First, we examined the prevalence of the participant roles of bullying in middle adolescence and possible gender differences therein. Second, we examined the behavioral and status characteristics associated with the participant roles in middle adolescence. Third, we

  13. Seismic qualification of existing nuclear installations in India - a proposal

    International Nuclear Information System (INIS)

    Basu, P.C.

    2001-01-01

    In India, the work toward seismic qualification of existing nuclear facilities has been started. Preliminary work is being undertaken with respect to identifying the facilities which would be taken up for seismic qualification, approach and methodology for re-evaluation for seismic safety, acceptance criteria, etc. Work has also been started for framing up the criteria and methodology of the seismic qualification of these facilities. Present paper contains the proposal in this respect. This proposal is on similar lines of the present practice of seismic qualification of NPP, as summarized in the Appendix, but has been modified to suit the special requirements of Indian nuclear installations. (author)

  14. Current status of the quantification of roughness and the peak shear strength criteria for rock joints

    Energy Technology Data Exchange (ETDEWEB)

    Park, Byoung Yoon; Kang, Chul Hyung

    1999-04-01

    In order to understand the effects of spent nuclear fuel on the hydraulic behaviour of the rock mass it is necessary to have knowledge about the relationship between the stresses and hydraulic properties of the fractures. The roughness of a fracture surface govern the dilation of the fracture and the displacement of the fracture surface under shear stress. The peak shear strength and hydraulic flow properties of fractures depend very much on the surface roughness. This report describes different methods and techniques used in the characterization of rock joint surfaces and their applications in rock mechanics. Joint roughness is an important factor in the shear resistance of a joint. The joint shear strength shows anisotropic properties due to roughness variation with the shearing direction in direct shear tests. Various shear strength criteria are described in this report. (author)

  15. Status report on developments and cooperation on risk-informed inservice-inspection and non-destructive testing (NDT) qualification in OECD-NEA member countries - CSNI integrity and ageing working group

    International Nuclear Information System (INIS)

    Skanberg, Lars

    2005-01-01

    During the last decades the nuclear industry has experienced service degradation of many components, both in primary systems and in secondary systems. Several inspection failures have also occurred over the years. This degradation and inspection history as well as the economical and political factors have consequently set up a pressure for more efficient and cost-effective in-service inspection programmes to ensure that there are adequate safety margins so that anticipated degradations of components do not lead to failures that cause accidents or even unplanned shutdowns with adverse effects on power production reliability. In this situation, nuclear regulators as well as nuclear utilities in many countries have developed and implement risk-informed inspection approaches together with more stringent requirements of demonstrating the performance of the NDT systems that are to be used for inspection of safety related components which are susceptible to different kind of degradation mechanisms. In December 2000, the Committee on Nuclear Regulatory Activities (CNRA) and the Committee on the Safety of Nuclear Installations (CSNI) agreed to prepare a state-of-the art report addressing the present situation and regulatory aspects in NEA member countries on: - Risk based / risk informed in-service inspections developments, - Qualification of NDT system to be used for the inspections. The CSNI gave mandate to the CSNI working group on the Integrity of Components and Structures (IAGE) to prepare the report. Practices and status in NEA member countries were collected in 2003 through a questionnaire. Results have been compiled in the report NEA/CSNI/R(2005)3. To complete the technical information, a CSNI Workshop was held from 13 to 14 April 2004 in Stockholm, Sweden hosted by the Swedish Nuclear Power Inspectorate. The Workshop gathered 54 participants from 17 countries including the EC, the IAEA and the main organisations worldwide developing RI-ISI methodologies. Papers

  16. Data Qualification Report For DTN: MO0012RIB00065.002, Parameter Values For Transfer Coefficients

    International Nuclear Information System (INIS)

    C.H. Tung

    2001-01-01

    A data-qualification evaluation was conducted on Reference Information Base (RIB) data set MOO0 12RIB00065.002, ''Parameter Values for Transfer Coefficients''. The corroborating data method was used to evaluate the data. This method was selected because it closely matches the literature-review method followed to select parameter values. Five criteria were considered when the corroborating method was used: adequacy of the corroborative literature, sufficiency of value-selection criteria, implementation of the selection criteria, documentation of the process, and whether the analysis was conducted in accordance with applicable quality assurance (QA) procedures. Three criteria were used when a literature review was not conducted: appropriate logic used to select parameters, documentation of the process, and whether the analysis was conducted in accordance with applicable QA procedures. The RIB data item, the associated Analysis and Model Report (AMR), the corroborative literature, and the results of an audit revision O/ICN--0 of the AMR were examined. All calculations and the selection process for all values were repeated and confirmed. The qualification team concluded: (1) A sufficient quantity of corroborative literature was reviewed and no additional literature was identified that should have been considered. (2) The selection criteria were sufficient and resulted in valid parameter values. (3) The process was well defined, adequately documented in the AMR, and correctly followed. (4) The analysis was developed in accordance with applicable QA procedures. No negative findings were documented that resulted in questions about the quality of the data. The qualification team therefore recommends that the qualification status of RIB data set MO0012RIB00065.002 be changed to qualified

  17. Selection, qualification and training of personnel for nuclear power plants

    International Nuclear Information System (INIS)

    Anon.

    1981-01-01

    This standard provides criteria for the selection, qualification and training of personnel for stationary nuclear power plants. Qualifications, responsibilities, and training of personnel in operating and support organizations appropriate for the safe and efficient operation of nuclear power plants are addressed

  18. 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...

  19. Nutrient Status and Criteria Development for the Saint John River, Canada, Using a Weight of Evidence Approach

    Science.gov (United States)

    Culp, J. M.; Luiker, E. A.; Noel, L.; Curry, A. R.; Hryn, D.; Heard, K.

    2005-05-01

    The Saint John River is the largest in Maine/New Brunswick (673 km in length, draining 55,000 km2) with a history of natural resource use and nutrient effluent release to the watershed since the late 17th century. Our objective was to obtain a basic understanding of the contemporary nutrient conditions of the non-tidal portion of the river in relation to historical conditions, and to consider how the contemporary river is affected by point and non-point source nutrient loadings. The study included review of historical provincial and federal water quality databases dating back to the 1960s. Current water quality monitoring programs have focused on nitrogen (nitrite, nitrate, ammonia, TKN), phosphorus (total, dissolved, and soluble reactive phosphorus), DIC/DOC, and biomass of periphyton and phytoplankton. To determine nutrient limitation, nutrient diffusing substrate studies were conducted in river reaches of known nutrient enrichment. Oxygen stable isotopes were also used to provide information on the photosynthesis to respiration ratio. A weight of evidence approach combining the results of these studies was used to determine trophic status of river reaches and to highlight areas of eutrophication. From this information nutrient criteria for the Saint John River will be proposed.

  20. 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

  1. 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

  2. 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

  3. 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

  4. 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.

  5. 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.

  6. 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...

  7. What is the evidence status of Appropriate Use Criteria (AUC)? Insight from a matching exercise with the guidelines for echocardiography.

    Science.gov (United States)

    Fonseca, R; Negishi, K; Marwick, T H

    2015-08-01

    There is interest in adapting the American Appropriate Use Criteria (AUC) for transthoracic echocardiography to Australian practice. We matched 90 of 98 AUC with the guidelines (53 appropriate, 12 sometimes appropriate, 25 rarely appropriate), but eight lacked any match. Among the matched criteria, 76 (82%) indications were concordant with the guidelines. A stronger evidence base would be desirable to settle these discrepancies before Australian adoption of AUC. © 2015 Royal Australasian College of Physicians.

  8. 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.

  9. 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

  10. Juvenile idiopathic arthritis in adulthood: fulfilment of classification criteria for adult rheumatic diseases, long-term outcomes and predictors of inactive disease, functional status and damage.

    Science.gov (United States)

    Oliveira-Ramos, Filipa; Eusébio, Mónica; M Martins, Fernando; Mourão, Ana Filipa; Furtado, Carolina; Campanilho-Marques, Raquel; Cordeiro, Inês; Ferreira, Joana; Cerqueira, Marcos; Figueira, Ricardo; Brito, Iva; Canhão, Helena; Santos, Maria José; Melo-Gomes, José A; Fonseca, João Eurico

    2016-01-01

    To determine how adult juvenile idiopathic arthritis (JIA) patients fulfil classification criteria for adult rheumatic diseases, evaluate their outcomes and determine clinical predictors of inactive disease, functional status and damage. Patients with JIA registered on the Rheumatic Diseases Portuguese Register (Reuma.pt) older than 18 years and with more than 5 years of disease duration were included. Data regarding sociodemographic features, fulfilment of adult classification criteria, Health Assessment Questionnaire, Juvenile Arthritis Damage Index-articular (JADI-A) and Juvenile Arthritis Damage Index-extra-articular (JADI-E) damage index and disease activity were analysed. 426 patients were included. Most of patients with systemic JIA fulfilled criteria for Adult Still's disease. 95.6% of the patients with rheumatoid factor (RF)-positive polyarthritis and 57.1% of the patients with RF-negative polyarthritis matched criteria for rheumatoid arthritis (RA). 38.9% of the patients with extended oligoarthritis were classified as RA while 34.8% of the patients with persistent oligoarthritis were classified as spondyloarthritis. Patients with enthesitis-related arthritis fulfilled criteria for spondyloarthritis in 94.7%. Patients with psoriatic arthritis maintained this classification. Patients with inactive disease had lower disease duration, lower diagnosis delay and corticosteroids exposure. Longer disease duration was associated with higher HAQ, JADI-A and JADI-E. Higher JADI-A was also associated with biological treatment and retirement due to JIA disability and higher JADI-E with corticosteroids exposure. Younger age at disease onset was predictive of higher HAQ, JADI-A and JADI-E and decreased the chance of inactive disease. Most of the included patients fulfilled classification criteria for adult rheumatic diseases, maintain active disease and have functional impairment. Younger age at disease onset was predictive of higher disability and decreased the

  11. 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).

  12. 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).

  13. The Autism Mental Status Exam: Sensitivity and Specificity Using DSM-5 Criteria for Autism Spectrum Disorder in Verbally Fluent Adults

    Science.gov (United States)

    Grodberg, David; Weinger, Paige M.; Halpern, Danielle; Parides, Michael; Kolevzon, Alexander; Buxbaum, Joseph D.

    2014-01-01

    The phenotypic heterogeneity of adults suspected of autism spectrum disorder (ASD) requires a standardized diagnostic approach that is feasible in all clinical settings. The autism mental status exam (AMSE) is an eight-item observational assessment that structures the observation and documentation of social, communicative and behavioral signs and…

  14. 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

  15. 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

  16. Methodology for LOCA analysis and its qualification procedures for PWR reload licensing

    International Nuclear Information System (INIS)

    Serrano, M.A.B.

    1986-01-01

    The methodology for LOCA analysis developed by FURNAS and its qualification procedure for PWR reload licensing are presented. Digital computer codes developed by NRC and published collectively as the WREM package were modified to get versions that comply to each requirement of Brazilian Licensing Criteria. This metodology is applied to Angra-1 basic case to conclude the qualification process. (Author) [pt

  17. Code qualification of structural materials for AFCI advanced recycling reactors.

    Energy Technology Data Exchange (ETDEWEB)

    Natesan, K.; Li, M.; Majumdar, S.; Nanstad, R.K.; Sham, T.-L. (Nuclear Engineering Division); (ORNL)

    2012-05-31

    ) and the Power Reactor Innovative Small Module (PRISM), the NRC/Advisory Committee on Reactor Safeguards (ACRS) raised numerous safety-related issues regarding elevated-temperature structural integrity criteria. Most of these issues remained unresolved today. These critical licensing reviews provide a basis for the evaluation of underlying technical issues for future advanced sodium-cooled reactors. Major materials performance issues and high temperature design methodology issues pertinent to the ARR are addressed in the report. The report is organized as follows: the ARR reference design concepts proposed by the Argonne National Laboratory and four industrial consortia were reviewed first, followed by a summary of the major code qualification and licensing issues for the ARR structural materials. The available database is presented for the ASME Code-qualified structural alloys (e.g. 304, 316 stainless steels, 2.25Cr-1Mo, and mod.9Cr-1Mo), including physical properties, tensile properties, impact properties and fracture toughness, creep, fatigue, creep-fatigue interaction, microstructural stability during long-term thermal aging, material degradation in sodium environments and effects of neutron irradiation for both base metals and weld metals. An assessment of modified versions of Type 316 SS, i.e. Type 316LN and its Japanese version, 316FR, was conducted to provide a perspective for codification of 316LN or 316FR in Subsection NH. Current status and data availability of four new advanced alloys, i.e. NF616, NF616+TMT, NF709, and HT-UPS, are also addressed to identify the R&D needs for their code qualification for ARR applications. For both conventional and new alloys, issues related to high temperature design methodology are described to address the needs for improvements for the ARR design and licensing. Assessments have shown that there are significant data gaps for the full qualification and licensing of the ARR structural materials. Development and evaluation of

  18. Clinical Neuropathology practice news 1-2014: Pyrosequencing meets clinical and analytical performance criteria for routine testing of MGMT promoter methylation status in glioblastoma

    Science.gov (United States)

    Preusser, Matthias; Berghoff, Anna S.; Manzl, Claudia; Filipits, Martin; Weinhäusel, Andreas; Pulverer, Walter; Dieckmann, Karin; Widhalm, Georg; Wöhrer, Adelheid; Knosp, Engelbert; Marosi, Christine; Hainfellner, Johannes A.

    2014-01-01

    Testing of the MGMT promoter methylation status in glioblastoma is relevant for clinical decision making and research applications. Two recent and independent phase III therapy trials confirmed a prognostic and predictive value of the MGMT promoter methylation status in elderly glioblastoma patients. Several methods for MGMT promoter methylation testing have been proposed, but seem to be of limited test reliability. Therefore, and also due to feasibility reasons, translation of MGMT methylation testing into routine use has been protracted so far. Pyrosequencing after prior DNA bisulfite modification has emerged as a reliable, accurate, fast and easy-to-use method for MGMT promoter methylation testing in tumor tissues (including formalin-fixed and paraffin-embedded samples). We performed an intra- and inter-laboratory ring trial which demonstrates a high analytical performance of this technique. Thus, pyrosequencing-based assessment of MGMT promoter methylation status in glioblastoma meets the criteria of high analytical test performance and can be recommended for clinical application, provided that strict quality control is performed. Our article summarizes clinical indications, practical instructions and open issues for MGMT promoter methylation testing in glioblastoma using pyrosequencing. PMID:24359605

  19. 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

  20. 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...

  1. 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

  2. 77 FR 48587 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2012-08-14

    ...-0217] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor Carrier... individuals for exemption from the prohibition against persons with insulin-treated diabetes mellitus (ITDM... drivers with diabetes mellitus, and be consistent with the criteria described in section 4018 of the...

  3. 77 FR 59447 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2012-09-27

    ...-0281] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor Carrier... individuals for exemption from the prohibition against persons with insulin-treated diabetes mellitus (ITDM... drivers with diabetes mellitus, and be consistent with the criteria described in section 4018 of the...

  4. 77 FR 18302 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2012-03-27

    ...-0043] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor Carrier... individuals for exemption from the prohibition against persons with insulin-treated diabetes mellitus (ITDM... for individual assessment of drivers with diabetes mellitus, and be consistent with the criteria...

  5. Legal status and source of offenders' firearms in states with the least stringent criteria for gun ownership.

    Science.gov (United States)

    Vittes, Katherine A; Vernick, Jon S; Webster, Daniel W

    2013-02-01

    Gun possession by high-risk individuals presents a serious threat to public safety. U.S. federal law establishes minimum criteria for legal purchase and possession of firearms; many states have laws disqualifying additional categories for illegal possession. We used data from a national survey of state prison inmates to calculate: 1) the proportion of offenders, incarcerated for crimes committed with firearms in 13 states with the least restrictive firearm purchase and possession laws, who would have been prohibited if their states had stricter gun laws; and 2) the source of gun acquisition for offenders who were and were not legally permitted to purchase and possess firearms. Nearly three of ten gun offenders (73 of 253 or 28.9%) were legal gun possessors but would have been prohibited from purchasing or possessing firearms when committing their most recent offense if their states had stricter prohibitions. Offenders who were already prohibited under current law acquired their gun from a licensed dealer, where a background check is required, five times less often than offenders who were not prohibited (3.9% vs. 19.9%; χ(2)=13.31; p≤0.001). Nearly all (96.1%) offenders who were legally prohibited, acquired their gun from a supplier not required to conduct a background check. Stricter gun ownership laws would have made firearm possession illegal for many state prison inmates who used a gun to commit a crime. Requiring all gun sales to be subject to a background check would make it more difficult for these offenders to obtain guns.

  6. Instructor qualification for radiation safety training at a national laboratory

    International Nuclear Information System (INIS)

    Trinoskey, P.A.

    1994-10-01

    Prior to 1993, Health Physics Training (HPT) was conducted by the Lawrence Livermore National Laboratory (LLNL) health physics group. The job requirements specified a Masters Degree and experience. In fact, the majority of Health Physicists in the group were certified by the American Board of Health Physics. Under those circumstances, it was assumed that individuals in the group were technically qualified and the HPT instructor qualification stated that. In late 1993, the Health Physics Group at the LLNL was restructured and the training function was assigned to the training group. Additional requirements for training were mandated by the Department of Energy (DOE), which would necessitate increasing the existing training staff. With the need to hire, and the policy of reassignment of employees during downsizing, it was imperative that formal qualification standards be developed for technical knowledge. Qualification standards were in place for instructional capability. In drafting the new training qualifications for instructors, the requirements of a Certified Health Physicists had to be modified due to supply and demand. Additionally, for many of the performance-based training courses, registration by the National Registry of Radiation Protection Technologists is more desirable. Flexibility in qualification requirements has been incorporated to meet the reality of ongoing training and the compensation for desirable skills of individuals who may not meet all the criteria. The qualification requirements for an instructor rely on entry-level requirements and emphasis on goals (preferred) and continuing development of technical and instructional capabilities

  7. Cancer Incidence in Five Continents: Inclusion criteria, highlights from Volume X and the global status of cancer registration.

    Science.gov (United States)

    Bray, F; Ferlay, J; Laversanne, M; Brewster, D H; Gombe Mbalawa, C; Kohler, B; Piñeros, M; Steliarova-Foucher, E; Swaminathan, R; Antoni, S; Soerjomataram, I; Forman, D

    2015-11-01

    Cancer Incidence in Five Continents (CI5), a longstanding collaboration between the International Agency for Research on Cancer and the International Association of Cancer Registries, serves as a unique source of cancer incidence data from high-quality population-based cancer registries around the world. The recent publication of Volume X comprises cancer incidence data from 290 registries covering 424 populations in 68 countries for the registration period 2003-2007. In this article, we assess the status of population-based cancer registries worldwide, describe the techniques used in CI5 to evaluate their quality and highlight the notable variation in the incidence rates of selected cancers contained within Volume X of CI5. We also discuss the Global Initiative for Cancer Registry Development as an international partnership that aims to reduce the disparities in availability of cancer incidence data for cancer control action, particularly in economically transitioning countries, already experiencing a rapid rise in the number of cancer patients annually. © 2015 UICC.

  8. Phase angle and World Health Organization criteria for the assessment of nutritional status in children with osteogenesis imperfecta.

    Science.gov (United States)

    Pileggi, Vicky Nogueira; Scalize, Antonio Rodolpho Hakime; Camelo Junior, José Simon

    2016-12-01

    To compare the phase angle of patients with osteogenesis imperfecta treated at a tertiary university hospital with patients in a control group of healthy children, and to assess the nutritional status of these patients through the body mass index proposed by the World Health Organization. Cross-sectional study carried out in a university hospital that included seven patients with osteogenesis imperfecta and a control group of 17 healthy children of the same gender and age. Weight and height were measured and bioelectrical impedance was performed. Subsequently, the phase angle was calculated based on resistance and reactance values. The phase angle of the group of children with osteogenesis imperfecta was significantly lower than that of the control group (posteogenesis imperfecta have a nutritional risk detected by the phase angle, which is a useful tool for nutritional screening. The calculation result could help in the diet therapy of patients with osteogenesis imperfecta. Copyright © 2016 Sociedade de Pediatria de São Paulo. Publicado por Elsevier Editora Ltda. All rights reserved.

  9. 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.

  10. 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

  11. 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

  12. 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.

  13. Qualification testing and electrical measurement experience: A manufacturer's view

    Science.gov (United States)

    Arnett, J. C.; Cooley, J. E.; Wingert, T. L.

    1983-11-01

    ARCO Solar's experiences as a participant in an industry-utility-government environmental qualification team examining photovoltaic devices are discussed. Included is an assessment of the applicability, completeness and appropriateness of the testing procedures and of the acceptance criteria for megawatt-sized procurements for utilities. Like the stand-alone users, the utility industry is interested in obtaining low costs, but additional concerns exist related to reliability and durability, safety, grounding and overall system criteria including performance prediction (related to output power acceptance testing), power quality and dispatchability. For purposes of this first major purchase of photovoltaic modules and panels by the utility industry, there was a carry-over of the JPL specifications. The need exists for futher development, assessement, and selection of qualification and testing standards and evaluation criteria specifically addressing these additional concerns for utility-connected PV power-plant applications.

  14. 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.

  15. Re-assessment of the Conservation Status of the Indo-Pacific Humpback Dolphin (Sousa chinensis) Using the IUCN Red List Criteria.

    Science.gov (United States)

    Jefferson, Thomas A; Smith, Brian D

    2016-01-01

    The IUCN Red List designation of the Indo-Pacific humpback dolphin (Sousa chinensis) is re-assessed in light of its newly recognized taxonomic status (it has recently been separated into three species) and findings that humpback dolphins along the coast of Bangladesh, and possibly eastern India, are phylogenetically distinct from other members of the Sousa genus. Sousa chinensis is found in Southeast/South Asia (in both the Indian and Pacific oceans), from at least the southeastern Bay of Bengal east to central China, and then south to the Indo-Malay Archipelago. There are no global population estimates, and the sum of available abundance estimates add up to about 5700 individuals, although only a portion of the range has been covered by surveys. This species occurs in shallow (Indo-Pacific humpback dolphins to stop apparent declines, and to lower the species' extinction risk. Sousa chinensis meets the IUCN Red List requirements for Vulnerable (under criteria A4cd), with fisheries bycatch and habitat loss/degradation being the main pervasive threats. © 2016 Elsevier Ltd. All rights reserved.

  16. 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

  17. 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

  18. 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.

  19. 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

  20. Requirements for qualification of manufacture of the ITER Central Solenoid and Correction Coils

    Energy Technology Data Exchange (ETDEWEB)

    Libeyre, Paul, E-mail: paul.libeyre@iter.org [ITER Organization, Route de Vinon sur Verdon, 13115 St Paul lez Durance (France); Li, Hongwei [ITER China, 15B Fuxing Road, Beijing 100862 (China); Reiersen, Wayne [US ITER Project Office, 1055 Commerce Park Dr., Oak Ridge, TN 37831 (United States); Dolgetta, Nello; Jong, Cornelis; Lyraud, Charles; Mitchell, Neil; Laurenti, Adamo [ITER Organization, Route de Vinon sur Verdon, 13115 St Paul lez Durance (France); Sgobba, Stefano [CERN, CH-1211 Genève 23 (Switzerland); Turck, Bernard [ITER Organization, Route de Vinon sur Verdon, 13115 St Paul lez Durance (France); Martovetsky, Nicolai; Everitt, David; Freudenberg, K.; Litherland, Steve; Rosenblad, Peter [US ITER Project Office, 1055 Commerce Park Dr., Oak Ridge, TN 37831 (United States); Smith, John; Spitzer, Jeff [General Atomics, P.O. Box 85608, San Diego, CA 92186-5608 (United States); Wei, Jing; Dong, Xiaoyu; Fang, Chao [ASIPP, Shushan Hu Road 350, Hefei, Anhui 230031 (China); and others

    2015-10-15

    Highlights: • A manufacturing line is installed for the ITER Correction Coils. • A manufacturing line is under installation for the ITER Central Solenoid. • Qualification of the manufacturing procedures has started for both manufacturing lines and acceptance criteria set. • Winding procedure of Correction Coils is qualified. - Abstract: The manufacturing line of the ITER Correction Coils (CC) at ASIPP in Hefei (China) was completed in 2013 and the manufacturing line of the ITER Central Solenoid (CS) modules is under installation at General Atomic premises in Poway (USA). In both cases, before starting production of the first coils, qualification of the manufacturing procedures is achieved by the construction of a set of mock-ups and prototypes to demonstrate that design requirements defined by the ITER Organization are effectively met. For each qualification item, the corresponding mock-ups are presented with the tests to be performed and the related acceptance criteria. The first qualification results are discussed.

  1. Development and Qualification of ATV Propulsion Assemblies

    Science.gov (United States)

    Riehle, M.; Jost, R.

    2002-01-01

    In the frame of the development and operation of the International Space Station ISS, the European Space Agency ESA is not only contributing experiments and a laboratory module but also logistics capacity. This purpose of supplying the ISS shall be covered by an unmanned, Automated Transfer Vehicle (ATV) that will be launched for the first time in 2004 by Ariane 5. The development of the ATV is in close conjunction to the future Ariane 5 launch capacity of about 20 tons injected into low earth orbit. Thus this unmanned transporter will be a quite large space craft that is subjected to fulfil several mission objectives apart of only delivering cargo such as multiple automatic docking/de-docking, re-boost services and re-fuelling. For those reasons and due to its dimensions the propulsion sub-system is one of the most sophisticated in the field of space propulsion. Even safety issues of manned space flight have to be applied since the pressurised cargo section is part of the ISS when docked to the manned modules. This leads to by far the largest but also the most sophisticated propulsion system ever built in Europe. Astrium as one of the major partners of this european project is responsible for this major system that will be described in the paper. Focusing on the major core assemblies such as multi thruster platforms, pressure control system incl. safety and redundancy mechanisms as well as tanks and other components that completes a propulsion system. System Design and Qualification Starting from the basic criteria the paper will present the major performance requirements such as pressures, thrust levels and other parameters that led to the selection of major components of the system such as thrusters, valves, tanks, etc. Some of the component could be selected from off the shelve, whereas other core components such as the 200N Attitude Control and Braking Thrusters or Propellant Tanks had to be newly developed. The stepwise approach of development and careful

  2. 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.

  3. Randomized trial of bioelectrical impedance analysis versus clinical criteria for guiding ultrafiltration in hemodialysis patients: effects on blood pressure, hydration status, and arterial stiffness.

    Science.gov (United States)

    Onofriescu, Mihai; Mardare, Nicoleta Genoveva; Segall, Liviu; Voroneanu, Luminiţa; Cuşai, Claudiu; Hogaş, Simona; Ardeleanu, Serban; Nistor, Ionuţ; Prisadă, Octavian Viorel; Sascău, Radu; Covic, Adrian

    2012-04-01

    Chronic fluid overload is common in maintenance hemodialysis (HD) patients and is associated with severe cardiovascular complications, such as arterial hypertension, left ventricular hypertrophy, congestive heart failure, and arrhythmia. Therefore, a crucial target of HD is to achieve the so-called dry weight; however, the best way to assess fluid status and dry weight is still unclear. Dry weight is currently determined in most dialysis units on a clinical basis, and it is commonly defined as the lowest body weight a patient can tolerate without developing intra-dialytic or inter-dialytic hypotension or other symptoms of dehydration. One of the most promising methods that have emerged in recent years is bioelectrical impedance analysis (BIA), which estimates body composition, including hydration status, by measuring the body's resistance and reactance to electrical current. Our objective was to study the effect BIA-guided versus clinical-guided ultrafiltration on various cardiovascular disease risk factors and markers in HD patients. We included 135 HD patients from a single center in a prospective study, aiming to compare the long-term (12 months) effect of BIA-based versus clinical-based assessment of dry weight on blood pressure (BP), pulse wave velocity (PWV), and serum N-terminal fragment of B-type natriuretic peptide (NT-proBNP). The body composition was measured using the portable whole-body multifrequency BIA device, Body Composition Monitor-BCM(®) (Fresenius Medical Care, Bad Homburg, Germany). In the "clinical" group there were no changes in BP, body mass index (BMI), and body fluids. The PWV increased from 7.9 ± 2.5 to 9.2 ± 3.6 m/s (P = 0.002), whereas serum NT-proBNP decreased from 5,238 to 3,883 pg/ml (P = 0.05). In the "BIA" group, BMI and body volumes also did not change; however, there was a significant decrease in both systolic BP, from 144.6 ± 14.7 to 135.3 ± 17.8 mmHg (P < 0.001), and diastolic BP, from 79.5 ± 9.7 to 73.2 ± 11.1 mmHg (P

  4. Excellence in fleet combat replacement squadrons: predicting carrier qualification success

    OpenAIRE

    Smith, Martin P.

    1988-01-01

    This thesis presents a two-part analysis of excellence criteria for fleet combat replacement squadrons. Part one focuses on the qualitative issues and management techniques identified in outstanding fleet combat replacement squadrons. Part two develops and presents a regression model for predicting a fleet replacement squadron pilot's carrier qualification grade. The model was derived using standard linear regression techniques and the SPSSx software package of the Naval Postgraduate School. ...

  5. 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

  6. 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

  7. 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

  8. 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)

  9. 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

  10. 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)

  11. 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...

  12. 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...

  13. 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

  14. 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,…

  15. 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...

  16. 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

  17. 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)

  18. 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

  19. Long term (>1 year) postpartum glucose tolerance status among Indian women with history of Gestational Diabetes Mellitus (GDM) diagnosed by IADPSG criteria.

    Science.gov (United States)

    Goyal, Alpesh; Gupta, Yashdeep; Kalaivani, Mani; Sankar, M Jeeva; Kachhawa, Garima; Bhatla, Neerja; Gupta, Nandita; Tandon, Nikhil

    2018-05-24

    To determine prevalence of long term dysglycemia and its risk factors among women with history of GDM diagnosed using IADPSG criteria at a tertiary care hospital in North India. Women with GDM diagnosed between 2012 and 2016 were invited. Socio-demographic, anthropometric, medical data were collected and 75 gm OGTT with serum insulin estimation, HbA1c and fasting lipid profile were done at the hospital visit. Women (N = 267) were tested at 32.5 (±4.6) years of age and at a median (q 25- q 75 ) of 20 (12-44) months following the index delivery. Dysglycemia was found in 57.7% by ADA criteria [Diabetes in 10.5% and prediabetes in 47.2%]. Risk factors for cardiovascular disease were significantly more prevalent among these women. On multivariable analysis, HOMA-IR correlated positively, while insulinogenic index correlated negatively with postpartum dysglycemia. This is possibly the first long term (>1 year) glucose tolerance outcome study in South Asian women with history of GDM diagnosed by IADPSG criteria, which demonstrates significantly elevated risk of postpartum dysglycemia. While the IADPSG criteria identify women with a lower future conversion to diabetes compared with previous criteria, prediabetes conversion remains high, thereby offering an opportunity to intervene early and prevent progression to future diabetes. Copyright © 2018 Elsevier B.V. All rights reserved.

  20. 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

  1. Criteria CSR

    OpenAIRE

    Vovk, V.; Zateyshikova, O.

    2014-01-01

    In the article the theoretical aspects regarding criteria for assessing CSR proposed by A. Carroll, including: economic, legal, ethical, philanthropic. Based on this, it is proposed to characterize these criteria with respect to the interested parties (stakeholders), including: investors, shareholders suppliers, customers, employees, society and the state. This will make a qualitative assessment of the presence and depth using social responsibility in the company, as well as determine the ext...

  2. 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.

  3. 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

  4. 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

  5. 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

  6. 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)

  7. Does Sufficient Evidence Exist to Support a Causal Association between Vitamin D Status and Cardiovascular Disease Risk? An Assessment Using Hill’s Criteria for Causality

    OpenAIRE

    Weyland, Patricia G.; Grant, William B.; Howie-Esquivel, Jill

    2014-01-01

    Serum 25-hydroxyvitamin D (25(OH)D) levels have been found to be inversely associated with both prevalent and incident cardiovascular disease (CVD) risk factors; dyslipidemia, hypertension and diabetes mellitus. This review looks for evidence of a causal association between low 25(OH)D levels and increased CVD risk. We evaluated journal articles in light of Hill’s criteria for causality in a biological system. The results of our assessment are as follows. Strength of association: many randomi...

  8. 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

  9. 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)

  10. 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

  11. 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…

  12. A growth analysis of teacher qualifications and students' global self-esteem

    DEFF Research Database (Denmark)

    Kristensen, Rune Müller

    2017-01-01

    , educational degree and employment status have a minor but significant effect on students’ GSE. Some of these effects differ between boys and girls, showing that boys react positively to teachers with high levels of content knowledge, while girls react positively to teachers with a higher degree of pedagogical...... teacher qualifications in terms of certification, educational degree and employment status affect students’ development in GSE. Effects of teacher qualifications influence on students’ development in GSE over time is modelled using growth curve analysis. Results show that elements in teacher certification......There is an increased focus on students’ non-academic outcomes of schooling and its long-term impact on the adolescents’ later life. Teachers are viewed as the most significant factor in schools for improving student learning and development. Little is known on effects of teacher qualifications...

  13. The Changing Distribution of Teacher Qualifications Across Schools: A Statewide Perspective Post-NCLB

    Directory of Open Access Journals (Sweden)

    Karen J. DeAngelis

    2010-11-01

    Full Text Available A number of recent policy initiatives, including NCLB's highly qualified teacher provisions, have sought to improve the qualifications of teachers and their distribution across schools. Little is known, however, about the impact of these policies. In this study, we use population data on teachers and schools in Illinois to examine changes in the level and distribution of teacher qualifications from 2001 to 2006. We find that schools in Chicago, especially those serving the highest percentages of low-income and minority students, experienced the greatest improvements in teacher qualifications during the period. In addition, high-poverty schools in most other locales in the state registered small to moderate improvements, which narrowed the gap in teacher qualifications between high- and low-poverty schools across Illinois. Improvements in the certification status of experienced teachers and the recruitment of new teachers with stronger academic qualifications both contributed to these gains. The results reveal a tradeoff for disadvantaged schools seeking to improve both teacher qualifications and teacher experience levels, thereby calling into question the near-term feasibility of NCLB provisions that aim to simultaneously eliminate inequities across schools in both.       

  14. Training, education and qualification of NPP operating personnel in the Netherlands

    International Nuclear Information System (INIS)

    de Vrey, G.A.

    1987-01-01

    This paper outlines the organization and the requirements of the training, education and qualification of NPP operating personnel in the Netherlands. It describes the implementation of a formally required scheme of personnel qualification after TMI, and the current practice as developed by the training staff of both Dutch nuclear power plants. Attention is given to the specific circumstances and problems in the Netherlands, and the resulting program. The licensing criteria for control room operating personnel are discussed, including the level of government involvement. Measures are described to improve the approach to training of NPP personnel involved in safety relevant activities. Finally, some ideas are given for strategies to cope with adverse stress situations

  15. Does Sufficient Evidence Exist to Support a Causal Association between Vitamin D Status and Cardiovascular Disease Risk? An Assessment Using Hill’s Criteria for Causality

    Directory of Open Access Journals (Sweden)

    Patricia G. Weyland

    2014-09-01

    Full Text Available Serum 25-hydroxyvitamin D (25(OHD levels have been found to be inversely associated with both prevalent and incident cardiovascular disease (CVD risk factors; dyslipidemia, hypertension and diabetes mellitus. This review looks for evidence of a causal association between low 25(OHD levels and increased CVD risk. We evaluated journal articles in light of Hill’s criteria for causality in a biological system. The results of our assessment are as follows. Strength of association: many randomized controlled trials (RCTs, prospective and cross-sectional studies found statistically significant inverse associations between 25(OHD levels and CVD risk factors. Consistency of observed association: most studies found statistically significant inverse associations between 25(OHD levels and CVD risk factors in various populations, locations and circumstances. Temporality of association: many RCTs and prospective studies found statistically significant inverse associations between 25(OHD levels and CVD risk factors. Biological gradient (dose-response curve: most studies assessing 25(OHD levels and CVD risk found an inverse association exhibiting a linear biological gradient. Plausibility of biology: several plausible cellular-level causative mechanisms and biological pathways may lead from a low 25(OHD level to increased risk for CVD with mediators, such as dyslipidemia, hypertension and diabetes mellitus. Experimental evidence: some well-designed RCTs found increased CVD risk factors with decreasing 25(OHD levels. Analogy: the association between serum 25(OHD levels and CVD risk is analogous to that between 25(OHD levels and the risk of overall cancer, periodontal disease, multiple sclerosis and breast cancer. Conclusion: all relevant Hill criteria for a causal association in a biological system are satisfied to indicate a low 25(OHD level as a CVD risk factor.

  16. 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

  17. 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...

  18. 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

  19. 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...

  20. The qualification of U3O8 as research reactor fuel

    International Nuclear Information System (INIS)

    Krull, W.

    1983-01-01

    This report summarizes the today knowledge of the qualification status of U 3 O 8 as low enriched ( 3 O 8 is so far qualified to start testing of ten (10) fuel elements with an U-density of 3.1 g U/cc in the FRG-2 research reactor. (orig.) [de

  1. The Development of a GaAs MMIC Reliability and Space Qualification Guide

    Science.gov (United States)

    Ponchak, G.; Kayali, S.; Huang, H-C.

    1994-01-01

    This paper discusses the need for a space qualification guide, provides a brief description of some common GaAs failure mechanisms, the approach that the NASA MMIC Reliability Assurance Program is following to develop the guide, and the status of the program.

  2. 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.)

  3. 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.)

  4. 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. ...

  5. 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. ...

  6. 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. ...

  7. High Temperature Materials Interim Data Qualification Report FY 2011

    International Nuclear Information System (INIS)

    Lybeck, Nancy

    2011-01-01

    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 Next Generation Nuclear Plant (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 fiscal year (FY) 2011 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 the Nuclear Quality Assurance (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 seven test series within the High Temperature Materials data stream have been entered into the NDMAS vault, including tensile tests, creep tests, and cyclic tests. Of the 5,603,682 records currently in the vault, 4,480,444 have been capture passed, and capture testing is in process for the remaining 1,123,238.

  8. 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

  9. Methods Data Qualification Interim Report

    International Nuclear Information System (INIS)

    Alessi, R. Sam; Grimmett, Tami; Vang, Leng; McGrath, Dave

    2010-01-01

    The overall goal of the Next Generation Nuclear Plant (NGNP) Data Management and Analysis System (NDMAS) is to maintain data provenance for all NGNP data including the Methods component of NGNP data. Multiple means are available to access data stored in NDMAS. A web portal environment allows users to access data, view the results of qualification tests and view graphs and charts of various attributes of the data. NDMAS also has methods for the management of the data output from VHTR simulation models and data generated from experiments designed to verify and validate the simulation codes. These simulation models represent the outcome of mathematical representation of VHTR components and systems. The methods data management approaches described herein will handle data that arise from experiment, simulation, and external sources for the main purpose of facilitating parameter estimation and model verification and validation (V and V). A model integration environment entitled ModelCenter is used to automate the storing of data from simulation model runs to the NDMAS repository. This approach does not adversely change the why computational scientists conduct their work. The method is to be used mainly to store the results of model runs that need to be preserved for auditing purposes or for display to the NDMAS web portal. This interim report demonstrates the currently development of NDMAS for Methods data and discusses data and its qualification that is currently part of NDMAS.

  10. Commercial Parts Technology Qualification Processes

    Science.gov (United States)

    Cooper, Mark S.

    2013-01-01

    Many high-reliability systems, including space systems, use selected commercial parts (including Plastic Encapsulated Microelectronics or PEMs) for unique functionality, small size, low weight, high mechanical shock resistance, and other factors. Predominantly this usage is subjected to certain 100% tests (typically called screens) and certain destructive tests usually (but not always) performed on the flight lot (typically called qualification tests). Frequently used approaches include those documented in EEE-INST-002 and JPL DocID62212 (which are sometimes modified by the particular aerospace space systems manufacturer). In this study, approaches from these documents and several space systems manufacturers are compared to approaches from a launch systems manufacturer (SpaceX), an implantable medical electronics manufacturer (Medtronics), and a high-reliability transport system process (automotive systems). In the conclusions section, these processes are outlined for all of these cases and presented in tabular form. Then some simple comparisons are made. In this introduction section, the PEM technology qualification process is described, as documented in EEE-INST-002 (written by the Goddard Space Flight Center, GSFC), as well as the somewhat modified approach employed at the Jet Propulsion Laboratory (JPL). Approaches used at several major NASA contractors are also described

  11. Methods Data Qualification Interim Report

    Energy Technology Data Exchange (ETDEWEB)

    R. Sam Alessi; Tami Grimmett; Leng Vang; Dave McGrath

    2010-09-01

    The overall goal of the Next Generation Nuclear Plant (NGNP) Data Management and Analysis System (NDMAS) is to maintain data provenance for all NGNP data including the Methods component of NGNP data. Multiple means are available to access data stored in NDMAS. A web portal environment allows users to access data, view the results of qualification tests and view graphs and charts of various attributes of the data. NDMAS also has methods for the management of the data output from VHTR simulation models and data generated from experiments designed to verify and validate the simulation codes. These simulation models represent the outcome of mathematical representation of VHTR components and systems. The methods data management approaches described herein will handle data that arise from experiment, simulation, and external sources for the main purpose of facilitating parameter estimation and model verification and validation (V&V). A model integration environment entitled ModelCenter is used to automate the storing of data from simulation model runs to the NDMAS repository. This approach does not adversely change the why computational scientists conduct their work. The method is to be used mainly to store the results of model runs that need to be preserved for auditing purposes or for display to the NDMAS web portal. This interim report demonstrates the currently development of NDMAS for Methods data and discusses data and its qualification that is currently part of NDMAS.

  12. Development of habitat suitability criteria for Neotropical stream fishes and an assessment of their transferability to streams with different conservation status

    Directory of Open Access Journals (Sweden)

    Fabrício Barreto Teresa

    Full Text Available We assessed the preference of 10 fish species for depth and velocity conditions in forested streams from southeastern Brazil using habitat suitability criteria (HSC curves. We also tested whether preference patterns observed in forested streams can be transferred to deforested streams. We used data from fish sampled in 62 five-meter sites in three forested streams to construct preference curves. Astyanax altiparanae, A. fasciatus, Knodus moenkhausii, and Piabina argentea showed a preference for deep slow habitats, whereas Aspidoras fuscoguttatus, Characidium zebra, Cetopsorhamdia iheringi, Pseudopimelodus pulcher, and Hypostomus nigromaculatus showed an opposite pattern: preference for shallow fast habitats. Hypostomus ancistroides showed a multimodal pattern of preference for depth and velocity. To evaluate whether patterns observed in forested streams may be transferred to deforested streams, we sampled 64 five-meters sites in three deforested streams using the same methodology. The preference for velocity was more consistent than for depth, as success in the transferability criterion was 86% and 29% of species, respectively. This indicates that velocity is a good predictor of species abundance in streams, regardless of their condition

  13. Project for qualification of the Kozloduy confinement system

    International Nuclear Information System (INIS)

    Montes Rodriguez, J.L.

    1993-01-01

    One of the projects awarded to Empresarios Agrupados within the Six-Month WANO Programme for Kozloduy NPP, financed through the European Community's PHARE Programme, relates to the first tasks of plant confinement system qualification. Development of this project - the results of which will serve as a reference for other power plants with VVER-440/230 models - aroused considerable interest in the Bulgarian nuclear community as well as in international entities which render assistance to Eastern power plants. In fact, this is one of the few projects in the programme which takes into account hardware-oriented activities to be carried out urgently in the plant. The VVER-440/230 confinement system performs functions parallel to the containment system of Western PWR reactors. However, it differs significantly in its criteria and operation details. These important differences form the basis for a rational and prudent application of the essence of Western codes and standards relating to the qualification of these systems. The criteria which are developed to make this application viable constitute the most challenging and, at the same time, most risky part of this job. The project will be in its final stages when the 18th Annual Meeting of the Spanish Nuclear Society is held; it is therefore likely that this paper will advance the results and conclusions expected. (author)

  14. 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

  15. Development of habitat suitability criteria for Neotropical stream fishes and an assessment of their transferability to streams with different conservation status

    Directory of Open Access Journals (Sweden)

    Fabrício Barreto Teresa

    Full Text Available We assessed the preference of 10 fish species for depth and velocity conditions in forested streams from southeastern Brazil using habitat suitability criteria (HSC curves. We also tested whether preference patterns observed in forested streams can be transferred to deforested streams. We used data from fish sampled in 62 five-meter sites in three forested streams to construct preference curves. Astyanax altiparanae, A. fasciatus, Knodus moenkhausii, and Piabina argentea showed a preference for deep slow habitats, whereas Aspidoras fuscoguttatus, Characidium zebra, Cetopsorhamdia iheringi, Pseudopimelodus pulcher, and Hypostomus nigromaculatus showed an opposite pattern: preference for shallow fast habitats. Hypostomus ancistroides showed a multimodal pattern of preference for depth and velocity. To evaluate whether patterns observed in forested streams may be transferred to deforested streams, we sampled 64 five-meters sites in three deforested streams using the same methodology. The preference for velocity was more consistent than for depth, as success in the transferability criterion was 86% and 29% of species, respectively. This indicates that velocity is a good predictor of species abundance in streams, regardless of their conditionNeste estudo avaliamos a preferência de 10 espécies de peixes por condições de profundidade e fluxo em riachos florestados do sudeste do Brasil por meio do critério de adequabilidade de habitat (habitat suitability criteria - curvas HSC. Testamos também se os padrões de preferência observados nos riachos florestados podem ser transferidos para riachos desmatados. Foram realizadas amostragens da ictiofauna em 62 trechos de cinco metros de extensão em três riachos florestados para a construção das curvas de preferência. Astyanax altiparanae, A. fasciatus, Knodus moenkhausii e Piabina argentea apresentaram preferência por habitats lentos e profundos, enquanto Aspidoras fuscoguttatus, Characidium zebra

  16. Status of the German AF-programme. Considerations with respect to INFCE recommendations and criteria[AF = Anreicherungsreduzierung in Forschungsreaktoren (Enrichment reduction in research reactors)

    Energy Technology Data Exchange (ETDEWEB)

    Thamm, Gerd H [Kernforschungsanlage Juelich GmbH, Research Reactor Division, Juelich (Germany)

    1983-09-01

    As is generally known, the INFCE studies carried out on a worldwide scale from 1977 to 1979 for research reactors using primarily highly enriched uranium (HEU 80% to 93% U-235) have led to the important recommendation that an effective reduction in the proliferation of weapons-usable nuclear material can be achieved by converting the fuel cycles from HEU to low-enriched uranium (LEU, U-235 enrichment 20%). Further recommendations made by INFCE to the effect of restricting or markedly reducing the stockpiles of HEU materials and diminishing the production of fissile materials due to irradiation in research reactors, however, have been given secondary attention in the course of development as compared to the first recommendation mentioned above. As a result of the INFCE studies, national programmes were initiated in various countries aiming at enrichment reduction in research reactors. Essential work in this connection was commenced above all in the USA (RERTR programme), in France, Japan and in the Federal Republic of Germany (AF programme). Added to this was an IAEA support programme intended primarily for developing and threshold countries. Essential conditions in the form of criteria were elaborated by the INFCE Working Group 8C in connection with the recommendation for enrichment reduction in research reactors. These criteria are: 1. The safety margins and fuel reliability should not be reduced by a conversion from HEU to LEU cycles. 2. Losses in reactor performance (e.g. the ratio of neutron flux available for experiments) to reactor power should not be more than marginal. 3. The cost of conversion for research reactors should be kept as low as possible. 4. Any increase in operating costs after conversion should not be more than marginal. The first three criteria mentioned have been given particular attention and have a good chance of being complied with in the current worldwide development activities for a conversion of research reactors to LEU fuel cycle

  17. Process qualification and control in electron beams--requirements, methods, new concepts and challenges

    International Nuclear Information System (INIS)

    Mittendorfer, J.; Gratzl, F.; Hanis, D.

    2004-01-01

    In this paper the status of process qualification and control in electron beam irradiation is analyzed in terms of requirements, concepts, methods and challenges for a state-of-the-art process control concept for medical device sterilization. Aspects from process qualification to routine process control are described together with the associated process variables. As a case study the 10 MeV beams at Mediscan GmbH are considered. Process control concepts like statistical process control (SPC) and a new concept to determine process capability is briefly discussed

  18. 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)

  19. 5 CFR 302.403 - Qualifications for promotion.

    Science.gov (United States)

    2010-01-01

    ... 5 Administrative Personnel 1 2010-01-01 2010-01-01 false Qualifications for promotion. 302.403... EMPLOYMENT IN THE EXCEPTED SERVICE Selection and Appointment; Reappointment; and Qualifications for Promotion § 302.403 Qualifications for promotion. In determining qualifications for promotion with respect to an...

  20. 49 CFR 180.507 - Qualification of tank cars.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 2 2010-10-01 2010-10-01 false Qualification of tank cars. 180.507 Section 180... QUALIFICATION AND MAINTENANCE OF PACKAGINGS Qualification and Maintenance of Tank Cars § 180.507 Qualification of tank cars. (a) Each tank car marked as meeting a “DOT” specification or any other tank car used...

  1. 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

  2. VHDL basics applied design by SIPAC qualification system

    International Nuclear Information System (INIS)

    Park, In Ha; Mun, Da Cheol; Lee, Gwang Yeob

    2005-12-01

    This book has six chapters, which are about Flowrian of SIPAC qualification system including internet CAD system and remote server service, logic circuit on design and qualification of device such as gate circuit, multiplex and decoder, order logic circuit with D type flip-flop design and qualification and Rom and RAM's design and qualification, finite state machine such as odd checker, sequence detector, test clock generator and traffic light controller, design and qualification about data path, design of application circuit. It has two appendixes on install and the way to use SIPAC qualification system and remote service for SIPAC qualification system.

  3. 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

  4. 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.

  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. QUALIFICATIONS FRAMEWORK DEVELOPMENT AND QUALIFICATIONS RATING IN THE LAND MANAGEMENT SPHERE

    Directory of Open Access Journals (Sweden)

    A. A. Myrasheva

    2014-01-01

    Full Text Available The aim of the research is to observe the existing approaches to qualifications framework development in the sphere of land management, cadastres and real estate management, as well as the qualifications framework adaptation to European system. The relevance of the issue is related to the specific professional and institutional problems facing Russian educational establishments engaged in personnel training in the given sphere. The authors demonstrate the qualifications framework development in the land management sector regarding it as a key mechanism of educational mobility and the router for knowledge acquisition and updates. The qualifications framework is referred to as a systematic and structured description of recognized qualifications. The accepted worldwide methodology of organizing the educational process and quality control system is given. The emphasis is on the need to comply the qualifications framework with the Russian State Educational Standards.

  7. Earthquake experience suggests new approach to seismic criteria

    International Nuclear Information System (INIS)

    Knox, R.

    1983-01-01

    Progress in seismic qualification of nuclear power plants as reviewed at the 4th Pacific Basin Nuclear Conference in Vancouver, September 1983, is discussed. The lack of experience of earthquakes in existing nuclear plants can be compensated by the growing experience of actual earthquake effects in conventional power plants and similar installations. A survey of the effects on four power stations, with a total of twenty generating units, in the area strongly shaken by the San Fernando earthquake in California in 1971 is reported. The Canadian approach to seismic qualification, international criteria, Canadian/Korean experience, safety related equipment, the Tadotsu test facility and seismic tests are discussed. (U.K.)

  8. Towards harmonized qualifications for radiation exposed personnel

    International Nuclear Information System (INIS)

    Briso, Hugo A.

    2008-01-01

    The accelerated process of globalization affecting mankind doesn't exclude safety matters. Indeed, some trans national corporations are increasingly offering specialized engineering services such as industrial radiography or well lodging. As well, a growing scientific exchange involves the mobility of nuclear researchers in different areas, for instance radiochemistry, nuclear medicine and radiotherapy. Such a breakdown in the technological frontiers must necessarily be reflected by the regulatory solutions. Particularly, diverse levels of theoretical-practical training for radiation exposed personnel coexist in the Latin-American Region, being an especially sensitive problem for radiation protection matters. The spectrum goes from post-graduate courses required for radiation protection officers in some countries, while in others only basic recommendations are required for the operating personnel. Another scheme consists of medium level course for the operating personnel, while radiation protection officers don't have special requirements. Many educational private institutions teach non standardized courses which only give broad concepts of radiation protection. On the other hand, usually nothing is said about the operational training, or else its certification is entrusted to the employer itself. In some countries multiple Regulatory Authorities apply dissimilar criteria to assess safety matters, including the evaluation of workers applications. The necessary regional integration makes indispensable to establish common standards for granting authorizations. Having similar or homogeneous requirements for the universe of radiation exposed personnel, i.e. source operators, radiation protection officers, qualified experts and technical support people would be easier for the Regulatory Authorities to have common methodologies of evaluation for the applicants. An IAEA supported technical cooperation project related to this paper seeks to establish standardized

  9. Subseabed disposal: systematic application of the site qualification plan

    International Nuclear Information System (INIS)

    Shephard, L.E.; Damuth, J.E.; Hayes, D.B.; Heath, G.R.; Laine, E.P.; Leinen, M.; Tucholke, B.E.

    1982-01-01

    Two criteria, geologic stability and barrier effectiveness, form the basis of the Subseabed Disposal Program's site qualification plan to evaluate the ocean basins and identify those regions having characteristics most favorable for containment of radioactive waste. Stability criteria are used to define those regions least likely to be disturbed by tectonic forces or oceanographic changes during the lifetime of a waste repository. Barrier criteria define those lithologies most likely to form an effective barrier to the release of radionuclides. Two north Pacific regions and three north Atlantic regions (PAC I and II and ATL I, II, and III, respectively) have thus far been selected for further investigation based on the site qualification plan. The PAC I region, centered on the Shatsky Rise in the northwest Pacific, has been subdivided into areas and locations on the basis of an exhaustive review of data available in the archives of national and international agencies and institutions. Results from three locations surveyed and sampled within the PAC I region (VEMA cruise 36-12) suggest some variability in seismic reflector character and lithology, attributable partially to the effects of the North Pacific current. PAC II, located northeast of Hawaii, represents a generic study region characteristic of the Pacific pelagic, abyssal hill environment. Seismic reflection surveys and sampling indicate uniform sediment properties and processes, both laterally and vertically, within the PAC II region. Initial investigation of Regions ATL I, II, and III, located within the distal Nares abyssal plain, the distal Sohm abyssal plain, and the Cape Verde region, respectively, suggests certain smaller areas within these regions warrant more detailed study

  10. 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

  11. Visas and qualifications: Syrian refugees in Brazil

    Directory of Open Access Journals (Sweden)

    Gilberto M A Rodrigues

    2017-10-01

    Full Text Available Brazil’s humanitarian visa programme for Syrian refugees and its efforts to recognise their qualifications could offer lessons for refugee protection and integration across the region.

  12. Qualification of anticorrosive coatings in nuclear vessels

    International Nuclear Information System (INIS)

    Perez Flores, C.

    1985-01-01

    Test qualifications of the behavior of anticorrosive coating systems used in nuclear vessels in service and under the accident conditions of radiation decontamination, steam chemical resistance, thermal conductivity, weathering accelerated aging are presented and discussed. (author)

  13. Sport Management Interns--Selection Qualifications.

    Science.gov (United States)

    Cuneen, Jacquelyn; Sidwell, M. Joy

    1993-01-01

    Examines and rates the background qualifications and qualities, identified by sport management practitioners through an examination of paper credentials, that are desired in interviewees vying for selection into sport management internship positions. (GLR)

  14. Appointment, qualifications and responsibilities of ventilation officers

    International Nuclear Information System (INIS)

    1981-01-01

    The Code provides for the appointment of a ventilation officer when required by the appropriate authority. This guideline offers comment on the appointment, qualifications, training and responsibilities of that person

  15. Qualification and testing of CT systems

    DEFF Research Database (Denmark)

    Bartscher, Markus; Neuschaefer-Rube, Ulrich; Illemann, Jens

    2018-01-01

    This chapter focuses on system verification and conformance to specifications. System qualification is carried out to ensure that the system and itscomponents achieve the best performance—usually corresponding to the specificationsmade by the manufacturer. Acceptance and reverification testing ar...

  16. Emergency Management. Functional Area Qualification Standard

    National Research Council Canada - National Science Library

    2004-01-01

    .... In support of this goal, the competency requirements defined in the Technical Qualification Standards should be aligned with and integrated into the recruitment and staffing processes for technical positions...

  17. Materials qualification for nuclear power plants

    International Nuclear Information System (INIS)

    Braconi, F.

    1987-01-01

    The supply of materials to be used in the fabrication of components submitted to pressure destined to Atucha II nuclear power plant must fulfill the quality assurance requirements in accordance with the international standards. With the aim of promoting the national participation in CNA II, ENACE had the need to adapt these requirements to the national industry conditions and to the availability of official entities' qualification and inspection. As a uniform and normalized assessment for the qualification of materials did not exist in the country, ENACE had to develop a materials suppliers qualification system. This paper presents a suppliers qualification procedure, its application limits and the alternative procedures for the acceptance of individual stock and for the stock materials purchase. (Author)

  18. 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

  19. 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

  20. Qualification of safety-related valve actuators

    International Nuclear Information System (INIS)

    Anon.

    1981-01-01

    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. It 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 all safety-related functions of power-driven valve actuators

  1. Assessing mathematics within advanced school science qualifications

    OpenAIRE

    McAlinden, Mary; Noyes, Andrew

    2017-01-01

    Following sustained discussion regarding the relationship between advanced mathematics and science learning in England, the government has pursued a reform agenda in which mathematics is embedded in national, high stakes A-level science qualifications and their assessments for 18-year-olds. For example, A-level Chemistry must incorporate the assessment of relevant mathematics for at least 20% of the qualification. Other sciences have different mandated percentages. This embedding policy is ru...

  2. Neutron absorber qualification and acceptance testing from the designer's perspective

    International Nuclear Information System (INIS)

    Bracey, W.; Chiocca, R.

    2004-01-01

    Starting in the mid 1990's, the USNRC began to require less than 100% credit for the 10B present in fixed neutron absorbers spent fuel transport packages. The current practice in the US is to use only 75% of the specified 10B in criticality safety calculations unless extensive acceptance testing demonstrates both the presence of the 10B and uniformity of its distribution. In practice, the NRC has accepted no more than 90% credit for 10B in recent years, while other national competent authorities continue to accept 100%. More recently, with the introduction of new neutron absorber materials, particularly aluminum / boron carbide metal matrix composites, the NRC has also expressed expectations for qualification testing, based in large part on Transnuclear's successful application to use a new composite material in the TN-68 storage / transport cask. The difficulty is that adding more boron than is really necessary to a metal has some negative effects on the material, reducing the ductility and the thermal conductivity, and increasing the cost. Excessive testing requirements can have the undesired effect of keeping superior materials out of spent fuel package designs, without a corresponding justification based on public safety. In European countries and especially in France, 100% credit has been accepted up to now with materials controls specified in the Safety Analysis Report (SAR): Manufacturing process approved by qualification testing Materials manufacturing controlled under a Quality Assurance system. During fabrication, acceptance testing directly on products or on representative samples. Acceptance criteria taking into account a statistical uncertainty corresponding to 3σ. The original and current bases for the reduced 10 B credit, the design requirements for neutron absorber materials, and the experience of Transnuclear and Cogema Logistics with neutron absorber testing are examined. Guidelines for qualification and acceptance testing and process controls

  3. 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

  4. 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

  5. Qualification tests for shift personnel in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Fechner, J B [Bundesministerium des Innern, Bonn (Germany, F.R.)

    1978-02-01

    The selection of personnel for training as shift supervisors or reactor operators so far used to be made by a plant operator mainly on the basis of such criteria as examinations, diplomas and other documents verifying the educational background, the type of activity exercised, and professional success. In addition, there are the opininons of trainers and supervisors based on personal observation of future shift personnel on training for specific plants at a training center, at the manufacturer's, the operator's or in activities in the construction and commissioning of the respective nuclear power plant. In the course of this phase, which normally takes several years, supervisors asses not only the professional capabilities of a trainee, but also bis psychic and physical performance and aptitude, e.g., with respect to decision making, leadership qualifications or behavior unter stress. The advisability of introducing psychological aptitude tests was also studied. However, a decision was recently taken to defer such psychological tests for the time being. Yet, nuclear power plant operators are required to submit a statement to their responsible authorities about industrial medical checkups and qualification assessments by supervisors.

  6. Qualification tests for shift personnel in nuclear power plants

    International Nuclear Information System (INIS)

    Fechner, J.B.

    1978-01-01

    The selection of personnel for training as shift supervisors or reactor operators so far used to be made by a plant operator mainly on the basis of such criteria as examinations, diplomas and other documents verifying the educational background, the type of activity exercised, and professional success. In addition, there are the opininons of trainers and supervisors based on personal observation of future shift personnel on training for specific plants at a training center, at the manufacturer's, the operator's or in activities in the construction and commissioning of the respective nuclear power plant. In the course of this phase, which normally takes several years, supervisors asses not only the professional capabilities of a trainee, but also bis psychic and physical performance and aptitude, e.g., with respect to decision making, leadership qualifications or behavior unter stress. The advisability of introducing psychological aptitude tests was also studied. However, a decision was recently taken to defer such psychological tests for the time being. Yet, nuclear power plant operators are required to submit a statement to their responsible authorities about industrial medical checkups and qualification assessments by supervisors. (orig.) [de

  7. Techniques and tools for software qualification in KNICS

    International Nuclear Information System (INIS)

    Cha, Kyung H.; Lee, Yeong J.; Cheon, Se W.; Kim, Jang Y.; Lee, Jang S.; Kwon, Kee C.

    2004-01-01

    This paper describes techniques and tools for qualifying safety software in Korea Nuclear Instrumentation and Control System (KNICS). Safety software are developed and applied for a Reactor Protection System (RPS), an Engineered Safety Features and Component Control System (ESF-CCS), and a safety Programmable Logic Controller (PLC) in the KNICS. Requirements and design specifications of safety software are written by both natural language and formal specification languages. Statechart is used for formal specification of software of the ESF-CCS and the safety PLC while NuSCR is used for formal specification of them of the RPS. pSET (POSCON Software Engineering Tool) as a software development tool has been developed and utilized for the IEC61131-3 based PLC programming. The qualification of the safety software consists of software verification and validation (V and V) through software life cycle, software safety analysis, and software configuration management, software quality assurance, and COTS (Commercial-Off-The-Shelf) dedication. The criteria and requirements for qualifying the safety software have been established with them in Software Review Plan (SRP)/Branch Technical Positions (BTP)-14, IEEE Std. 7-4.3.2-1998, NUREG/CR-6463, IEEE Std. 1012-1998, and so on. Figure 1 summarizes qualification techniques and tools for the safety software

  8. Round table discussion " Development of qualification framework in meteorology (TEMPUS QUALIMET)"

    Science.gov (United States)

    Bashmakova, I.; Belotserkovsky, A.; Karlin, L.; Petrosyan, A.; Serditova, N.; Zilitinkevich, S.

    2010-09-01

    The international consortium has started implementing a project aimed at the development of unified framework of qualifications in meteorology (QualiMet), setting a system of recognition and award of qualifications up to Doctoral level based on standards of knowledge, skill and competence acquired by learners is underway. The QualiMet has the following specific objectives: 1. To develop standards of knowledge, skills and competence for all qualifications up to Doctoral level needed in all possible occupations meteorology learner can undertake, by July 2011 2. To develop reciprocally recognized rubrics, criteria, methods and tools for assessing the compliance with the developed standards (quality assurance), by July 2012 3. To set the network of Centers of Excellence as the primary designer of sample education programs and learning experiences, both in brick-and-mortar and distant setting of delivery, leading to achievement of the developed standards, by December 2012 4. To set a system of mutual international recognition and award of qualifications in meteorology based on the developed procedures and establishment of self-regulatory public organization, by December 2012 The main beneficiaries of the project are: 1. Meteorology learners from the consortium countries. They will be able to make informed decisions about available qualification choices and progression options and provided an opportunity for students and graduates to participate in the system of international continuous education. 2. Meteorology employers from the consortium countries, They will be able to specify the level of knowledge, skill and competence required for occupational roles, evaluate qualifications presented, connect training and development with business needs. 3. Students and academic staff of all the consortium members, who will gain the increased mobility and exchange the fluxes of culturally and institutionally diversified lecturers and qualified specialists

  9. 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)

  10. AGC-3 Experiment Irradiation Monitoring Data Qualification Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Hull, Laurence C. [Idaho National Lab. (INL), Idaho Falls, ID (United States). VHTR Technology Development Office

    2014-08-01

    The Graphite Technology Development Program will run a series of six experiments to quantify the effects of irradiation on nuclear-grade graphite. The third experiment, Advanced Graphite Creep 3 (AGC-3), began with Advanced Test Reactor (ATR) Cycle 152B on November 27, 2012, and ended with ATR Cycle 155B on April 23, 2014. This report documents qualification of AGC-3 experiment irradiation monitoring data for use by the Very High Temperature Reactor (VHTR) Technology Development Office (TDO) Program for research and development activities required to design and license the first VHTR nuclear plant. Qualified data meet the requirements for data collection and use as described in the experiment planning and quality assurance documents. Failed data do not meet the requirements. Trend data may not meet the requirements, but may still provide some useable information. The report documents qualification of AGC-3 experiment irradiation monitoring data following MCP-2691. This report also documents whether AGC-3 experiment irradiation monitoring data meet the requirements for data collection as specified in technical and functional requirements documents and quality assurance (QA) plans. Data handling is described showing how data are passed from the data collection experiment to the Nuclear Data Management and Analysis System (NDMAS) team. The data structure is described, including data batches, components, attributes, and response variables. The description of the approach to data qualification includes the steps taken to qualify the data and the specific tests used to verify that the data meet requirements. Finally, the current status of the data received by NDMAS from the AGC-3 experiment is presented with summarized information on test results and resolutions. This report addresses all of the irradiation monitoring data collected during the AGC-3 experiment.

  11. Fiber Laser Component Testing for Space Qualification Protocol Development

    Science.gov (United States)

    Falvey, S.; Buelow, M.; Nelson, B.; Starcher, Y.; Thienel, L.; Rhodes, C.; Tull, Jackson; Drape, T.; Westfall, C.

    A test protocol for the space qualifying of Ytterbium-doped diode-pumped fiber laser (DPFL) components was developed under the Bright Light effort, sponsored by AFRL/VSE. A literature search was performed and summarized in an AMOS 2005 conference paper that formed the building blocks for the development of the test protocol. The test protocol was developed from the experience of the Bright Light team, the information in the literature search, and the results of a study of the Telcordia standards. Based on this protocol developed, test procedures and acceptance criteria for a series of vibration, thermal/vacuum, and radiation exposure tests were developed for selected fiber laser components. Northrop Grumman led the effort in vibration and thermal testing of these components at the Aerospace Engineering Facility on Kirtland Air Force Base, NM. The results of the tests conducted have been evaluated. This paper discusses the vibration and thermal testing that was executed to validate the test protocol. The lessons learned will aid in future assessments and definition of space qualification protocols. Components representative of major items within a Ytterbium-doped diode-pumped fiber laser were selected for testing; including fibers, isolators, combiners, fiber Bragg gratings, and laser diodes. Selection of the components was based on guidelines to test multiple models of typical fiber laser components. A goal of the effort was to test two models (i.e. different manufacturers) of each type of article selected, representing different technologies for the same type of device. The test articles did not include subsystems or systems. These components and parts may not be available commercial-off-the-shelf (COTS), and, in fact, many are custom articles, or newly developed by the manufacturer. The primary goal for this effort is a completed taxonomy that lists all relevant laser components, modules, subsystems, and interfaces, and cites the documentation for space

  12. Development and qualification of functional materials for the EU Test Blanket Modules: Strategy and R and D activities

    Energy Technology Data Exchange (ETDEWEB)

    Zmitko, M., E-mail: milan.zmitko@f4e.europa.eu [Fusion for Energy (F4E), 08019 Barcelona (Spain); Poitevin, Y. [Fusion for Energy (F4E), 08019 Barcelona (Spain); Boccaccini, L., E-mail: lorenzo.boccaccini@inr.fzk.de [Institut Fuer Neutronenphysik und Reaktortechnik, FZK, D-76021 Karlsruhe (Germany); Salavy, J.-F., E-mail: jfsalavy@cea.fr [CEA/Saclay, DEN/DM2S, F-91191 Gif-sur-Yvette (France); Knitter, R., E-mail: regina.knitter@imf.fzk.de [Institut Fuer Materialforschung III, FZK, D-76021 Karlsruhe (Germany); Moeslang, A., E-mail: anton.moeslang@imf.fzk.de [Institut Fuer Materialforschung I, FZK, D-76021 Karlsruhe (Germany); Magielsen, A.J., E-mail: magielsen@nrg.eu [NRG Petten, 1755 ZG Petten (Netherlands); Hegeman, J.B.J. [NRG Petten, 1755 ZG Petten (Netherlands); Laesser, R. [Fusion for Energy (F4E), 08019 Barcelona (Spain)

    2011-10-01

    Europe has developed two reference tritium breeder blankets concepts for a DEMO fusion reactor: the Helium-Cooled Lithium-Lead and the Helium-Cooled Pebble-Bed. Both will be tested in ITER under the form of Test Blanket Modules (TBMs). The paper reviews the current status of development and qualification of the EU TBMs functional materials; i.e. ceramic solid breeder materials, beryllium/beryllides multiplier materials and Lithium-Lead liquid metal breeder material Pb-15.7Li. For each functional material the main functional/performance requirements with key qualification issues, current status of the R and D activities and the EU development strategy are presented. In the development strategy major steps considered are listed pointing out importance of the 'Development/qualification/procurement plan', currently under elaboration, for definition of a roadmap of further activities aiming at delivery of qualified functional materials to be used in the European TBMs in ITER.

  13. 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

  14. Orion European Service Module (ESM) Development, Integration and Qualification Status

    Science.gov (United States)

    Berthe, Philippe; Over, Ann P.; Picardo, Michelle; Byers, Anthony W.

    2017-01-01

    ESA and the European Industry are supplying the European Service Module for Orion. An overview of the system and subsystem configuration of the Orion European Service Module (ESM) as designed and built for the EM-1 mission is provided as well as an outline of its development, assembly, integration and verification process performed by ESA and NASA in coordination with their respective Industrial prime contractors, Airbus Defence and Space and Lockheed Martin.

  15. Qualification status of LEU [low enriched uranium] fuels

    International Nuclear Information System (INIS)

    Snelgrove, J.L.

    1987-01-01

    Sufficient data has been obtained from tests of high-density, low-enriched fuels for research and test reactors to declare them qualified for use. These fuels include UZrH x (TRIGA fuel) and UO 2 (SPERT fuel) for rod-type reactors and UAl x , U 3 O 8 , U 3 Si 2 , and U 3 Si dispersed in aluminium for plate-type reactors. Except for U 3 Si, the allowable fission density for LEU applications is limited only by the available 235 U. Several reactors are now using these fuels, and additional conversions are in progress. The basic performance characteristics and limits, if any, of the qualified low-enriched (and medium-enriched) fuels are discussed. Continuing and planned work to qualify additional fuels is also discussed. (Author)

  16. 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

  17. Unintended Consequences: How Qualification Constrains Innovation

    Science.gov (United States)

    Brice, Craig A.

    2011-01-01

    The development and implementation of new materials and manufacturing processes for aerospace application is often hindered by the high cost and long time span associated with current qualification procedures. The data requirements necessary for material and process qualification are extensive and often require millions of dollars and multiple years to complete. Furthermore, these qualification data can become obsolete for even minor changes to the processing route. This burden is a serious impediment to the pursuit of revolutionary new materials and more affordable processing methods for air vehicle structures. The application of integrated computational materials engineering methods to this problem can help to reduce the barriers to rapid insertion of new materials and processes. By establishing predictive capability for the development of microstructural features in relation to processing and relating this to critical property characteristics, a streamlined approach to qualification is possible. This paper critically examines the advantages and challenges to a modeling-assisted qualification approach for aerospace structural materials. An example of how this approach might apply towards the emerging field of additive manufacturing is discussed in detail.

  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. 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

  20. Mechanical seals qualification procedure of the main pumps of nuclear power plants in France

    International Nuclear Information System (INIS)

    Buchdahl, D.; Martin, R.; Girault, J.M.

    1992-12-01

    Many important pumps in the nuclear power plants are equipped with mechanical seals. The good behaviour and reliability of mechanical seals depend specially on the quality and the stability of an interface of several microns. Peripheral speed reaches 50 m/s and pressure 5 MPa, shaft diameter may be 200 mm. Any failure of the mechanical seals may stop the production of electricity or may compromise nuclear safety. As far back as 1970, EDF has conducted qualification actions for the most important mechanical seals in terms of availability and safety. A qualification of mechanical seals needs three steps: - constructor test (tuning) at normal conditions, -qualification test on test rig at EDF/DER (semi-industrial) at normal, exceptional and incidental conditions lasting about 1500 h, - industrial qualification test in nuclear power station over one year. Several supplying sources are absolutely necessary. Any pump may receive mechanical seals from at least two different suppliers. A compromise had to be found to restrict the suppliers' number down to three. This choice concerned three high technology suppliers. A consistent modification procedure had been developed (references file procedure). For each power plant series, about ten types of mechanical seals are concerned. The selection criteria are the higher loads factors P, Vg or the safety related importance. This expensive approach is useful for EDF, many functional failures have been detected before the serial mechanical seals installation in the power plants. (authors). 1 annexe

  1. Inspection qualification as a tool to risk based ET ISI of VVER type SG tubes

    International Nuclear Information System (INIS)

    Horacek, L.

    2002-01-01

    A Pilot study on Eddy current inspection qualification of VVER 440 steam generator tubes, discussed in this paper, followed the ENIQ methodology principles and covered briefly the assumed scope of ET qualification, relevant elaborated qualification documents, known ISI limitations and a review of input information on component and defects determined for Eddy current inspection qualification of VVER 440 steam generator tubes. The information includes the fabrication of the test blocks with SG tube segments provided by intended defect simulations of realistic SCC type and basic data on the realistic SCC type defects manufacturing technology. Lessons learned from the development of manufacturing technology of SSC type of defects, regional blind tests, elaboration of the preliminary technical justification for Eddy current automated inspections, potential optimisation of inspection procedures, laboratory and practical open trials are summarised in the paper. The results of the Pilot study also especially in relation to POD curve being determined seem to be useful for practical operational ISI programme and Risk informed ISI decisions and the establishment of plugging criteria of VVER 440 and VVER 1000 type steam generator tubes. (orig.)

  2. 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

  3. SRS H1616 Hydride Transport Vessel Qualification Report

    International Nuclear Information System (INIS)

    Smith, A.C.

    1999-01-01

    This report serves as the design qualification basis for both transport and facility use. Headings identify report sections as containing qualification information for transport use, facility use, or both transport and facility use

  4. SRS H1616 Hydride Transport Vessel Qualification Report

    International Nuclear Information System (INIS)

    Van Alstine, M.N.

    1998-01-01

    This report serves as the design qualification basis for both transport and facility use. Headings identify report sections as containing qualification information for transport use, facility use, or both transport and facility use

  5. 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

    The Savannah River National Laboratory (SRNL) has evaluated the existing waste feed qualification strategy for the Hanford Tank Waste Treatment and Immobilization Plant (WTP) based on experience from the Savannah River Site (SRS) Defense Waste Processing Facility (DWPF) waste qualification program. The current waste qualification programs for each of the sites are discussed in the report to provide a baseline for comparison. Recommendations on strategies are then provided that could be implemented at Hanford based on the successful Macrobatch qualification strategy utilized at SRS to reduce the risk of processing upsets or the production of a staged waste campaign that does not meet the processing requirements of the WTP. Considerations included the baseline WTP process, as well as options involving Direct High Level Waste (HLW) and Low Activity Waste (LAW) processing, and the potential use of a Tank Waste Characterization and Staging Facility (TWCSF). The main objectives of the Hanford waste feed qualification program are to demonstrate compliance with the Waste Acceptance Criteria (WAC), determine waste processability, and demonstrate unit operations at a laboratory scale. Risks to acceptability and successful implementation of this program, as compared to the DWPF Macro-Batch qualification strategy, include: Limitations of mixing/blending capability of the Hanford Tank Farm; The complexity of unit operations (i.e., multiple chemical and mechanical separations processes) involved in the WTP pretreatment qualification process; The need to account for effects of blending of LAW and HLW streams, as well as a recycle stream, within the PT unit operations; and The reliance on only a single set of unit operations demonstrations with the radioactive qualification sample. This later limitation is further complicated because of the 180-day completion requirement for all of the necessary waste feed qualification steps. The primary recommendations/changes include the

  6. T25 Qualification of old containers

    International Nuclear Information System (INIS)

    Hoerning, T.; Kasparek, E.M.; Voelzke, H.

    2013-01-01

    Radioactive waste for final disposal in the repository Konrad has to be packaged in licensed containers. The qualification of containers is performed according the respective standards and BfS requirements. The latter ones differ for different container types with respect to accident resistance based on the release behavior of the waste. Usually qualification of container types is performed before series production. The qualification of already produced containers (''old containers'') is significantly more complicated. The differences of quality assurance and materials properties of the older containers have to be evaluated. A main tool for this evaluation is the numerical re-calculation of accident scenarios for estimation of the safety margins. The validation of appropriate finite element models is available. Based on these date it might be possible to abandon additional drop tests with the existing old containers to prove the structural integrity.

  7. 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

  8. Effect of Teacher's Qualification on the Performance of Senior Secondary School Physics Students: Implication on Technology in Nigeria

    Science.gov (United States)

    Owolabi, Olabode Thomas; Adedayo, Julius Olugbenga

    2012-01-01

    The study examined the effect of teacher's qualification on the performance of Senior Secondary School students in Physics. The purpose was to determine whether the status of the teacher has any impact on the performance of the students in Physics. The survey type of descriptive research design was adopted. The sample for the study consisted of…

  9. 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.

  10. 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

  11. The ENIQ pilot study: current status

    Energy Technology Data Exchange (ETDEWEB)

    Lemaitre, P; Eriksen, B; Crutzen, S [European Commission, DG Joint Research Centre, Petten (Netherlands); Hansch, M [Preussische Elektrizitaets-AG (Preussenelektra), Hannover (Germany); Whittle, J [AEA Technology, Warrington (United Kingdom)

    1998-11-01

    A pilot study is currently being carried out by ENIQ (European Network for Inspection Qualification) in order to explore the issues involved in inspection qualification applied along the general principles of the European methodology. The components selected for the pilot study are austenitic pipe to pipe and pipe to elbows welds typical of those in BWR recirculation loops. A range of defect parameters has been defined. A suitable inspection procedure designed to find the designated defects will be applied to geometrically representative test pieces. The procedure/equipment will be qualified through open trials and technical justification. The personnel qualification will be done in a blind way. Once all features of the inspection system will have been qualified an in-service inspection will be simulated in order to test the feasibility of the qualification approach followed. In this paper the current status of this pilot study is discussed. (orig.)

  12. Women with oligo-/amenorrhoea and polycystic ovaries have identical responses to GnRH stimulation regardless of their androgen status: comparison of the Rotterdam and Androgen Excess Society diagnostic criteria.

    Science.gov (United States)

    Lewandowski, Krzysztof C; Cajdler-Luba, Agata; Bieńkiewicz, Małgorzata; Lewiński, Andrzej

    2011-01-01

    As increased frequency of gonadotrophin-releasing hormone (GnRH) pulses is characteristic for polycystic ovary syndrome (PCOS), we assessed gonadotrophin response to GnRH in women with PCOS with normal and raised androgens and in regularly menstruating controls. The study involved 155 subjects: PCOS, n=121, age (mean±SD) 24.8±5.4 yrs, BMI 24.5±6.0 kg/m2, all with oligo-/amenorrhoea and PCO morphology, and 34 controls. Gonadotrophins were measured in early follicular phase after GnRH stimulation (0, 30 and 60 minutes). Fifty four (41.9%) women with PCOS had androgens (testosterone, androstendione, dihydroepiandrosterone sulphate) within the reference range, and would fulfil the "Rotterdam", but not the Androgen Excess Society PCOS criteria. Baseline and stimulated LH concentrations were higher in PCOS (9.09±5.56 vs 4.83±1.71 IU/l, 35.48±31.4 vs 16.30±6.68 IU/l, 33.86±31.8 vs 13.45±5.2 IU/l, at 0, 30 and 60 min post GnRH, respectively, pPCOS increased further after GnRH stimulation. ROC analysis revealed that LH30min/FSH30min >2.11 or LH60min/FSH60min >1.72 had 78.3% and 87.5% sensitivity and 81.7% and 81.3% specificity for diagnosis of PCOS. Both baseline and GnRH-stimulated LH and FSH concentrations were similar in women with PCOS and raised androgens and with androgens within the reference range (p=0.71 and p=0.20 for LH and FSH, respectively). Regardless of their androgen status, women with PCO morphology and oligo-/amenorrhoea have higher baseline and GnRH-stimulated LH concentrations and higher GnRH-stimulated LH/FSH ratio than controls, suggestive of similar underlying mechanism accounting for menstrual irregularities. These observations support validity of PCOS diagnostic criteria based on the Rotterdam consensus.

  13. Qualification of nuclear power plant operations personnel

    International Nuclear Information System (INIS)

    1984-01-01

    With the ultimate aim of reducing the possibility of human error in nuclear power plant operations, the Guidebook discusses the organizational aspects, the staffing requirements, the educational systems and qualifications, the competence requirements, the ways to establish, preserve and verify competence, the specific aspects of personnel management and training for nuclear power plant operations, and finally the particular situations and difficulties to be overcome by utilities starting their first nuclear power plant. An important aspect presented in the Guidebook is the experience in training and qualification of nuclear power plant personnel in various countries: Argentina, Belgium, Canada, Czechoslovakia, France, Federal Republic of Germany, Spain, Sweden, United Kingdom and United States of America

  14. 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

  15. Minimum qualifications for nuclear criticality safety professionals

    International Nuclear Information System (INIS)

    Ketzlach, N.

    1990-01-01

    A Nuclear Criticality Technology and Safety Training Committee has been established within the U.S. Department of Energy (DOE) Nuclear Criticality Safety and Technology Project to review and, if necessary, develop standards for the training of personnel involved in nuclear criticality safety (NCS). The committee is exploring the need for developing a standard or other mechanism for establishing minimum qualifications for NCS professionals. The development of standards and regulatory guides for nuclear power plant personnel may serve as a guide in developing the minimum qualifications for NCS professionals

  16. Low-level radioactive waste form qualification testing

    Energy Technology Data Exchange (ETDEWEB)

    Sohal, M.S.; Akers, D.W.

    1998-06-01

    This report summarizes activities that have already been completed as well as yet to be performed by the Idaho National Engineering and Environmental Laboratory (INEEL) to develop a plan to quantify the behavior of radioactive low-level waste forms. It briefly describes the status of various tasks, including DOE approval of the proposed work, several regulatory and environmental related documents, tests to qualify the waste form, preliminary schedule, and approximate cost. It is anticipated that INEEL and Brookhaven National Laboratory will perform the majority of the tests. For some tests, services of other testing organizations may be used. It should take approximately nine months to provide the final report on the results of tests on a waste form prepared for qualification. It is anticipated that the overall cost of the waste quantifying service is approximately $150,000. The following tests are planned: compression, thermal cycling, irradiation, biodegradation, leaching, immersion, free-standing liquid tests, and full-scale testing.

  17. Low-level radioactive waste form qualification testing

    International Nuclear Information System (INIS)

    Sohal, M.S.; Akers, D.W.

    1998-06-01

    This report summarizes activities that have already been completed as well as yet to be performed by the Idaho National Engineering and Environmental Laboratory (INEEL) to develop a plan to quantify the behavior of radioactive low-level waste forms. It briefly describes the status of various tasks, including DOE approval of the proposed work, several regulatory and environmental related documents, tests to qualify the waste form, preliminary schedule, and approximate cost. It is anticipated that INEEL and Brookhaven National Laboratory will perform the majority of the tests. For some tests, services of other testing organizations may be used. It should take approximately nine months to provide the final report on the results of tests on a waste form prepared for qualification. It is anticipated that the overall cost of the waste quantifying service is approximately $150,000. The following tests are planned: compression, thermal cycling, irradiation, biodegradation, leaching, immersion, free-standing liquid tests, and full-scale testing

  18. 5 CFR 317.502 - Qualifications Review Board certification.

    Science.gov (United States)

    2010-01-01

    ... REGULATIONS EMPLOYMENT IN THE SENIOR EXECUTIVE SERVICE Career Appointments § 317.502 Qualifications Review Board certification. (a) A Qualification Review Board (QRB) convened by OPM must certify the executive... 5 Administrative Personnel 1 2010-01-01 2010-01-01 false Qualifications Review Board certification...

  19. 14 CFR 121.453 - Flight engineer qualifications.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 3 2010-01-01 2010-01-01 false Flight engineer qualifications. 121.453... REQUIREMENTS: DOMESTIC, FLAG, AND SUPPLEMENTAL OPERATIONS Crewmember Qualifications § 121.453 Flight engineer qualifications. (a) No certificate holder may use any person nor may any person serve as a flight engineer on an...

  20. 49 CFR 214.351 - Training and qualification of flagmen.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 4 2010-10-01 2010-10-01 false Training and qualification of flagmen. 214.351... ADMINISTRATION, DEPARTMENT OF TRANSPORTATION RAILROAD WORKPLACE SAFETY Roadway Worker Protection § 214.351 Training and qualification of flagmen. (a) The training and qualification for roadway workers assigned the...

  1. Long-Term Safety Analysis of Baldone Radioactive Waste Repository and Updating of Waste Acceptance Criteria

    International Nuclear Information System (INIS)

    2001-12-01

    The main objective of the project was to provide advice to the Latvian authorities on the safety enhancements and waste acceptance criteria for near surface radioactive waste disposal facilities of the Baldone repository. The project included the following main activities: Analysis of the current status of the management of radioactive waste in Latvia in general and, at the Baldone repository in particular Development of the short and long-term safety analysis of the Baldone repository, including: the planned increasing of capacity for disposal and long term storage, the radiological analysis for the post-closure period Development of the Environment Impact Statement, for the new foreseen installations, considering the non radiological components Proposal of recommendations for future updating of radioactive waste acceptance criteria Proposal of recommendations for safety upgrades to the facility. The work programme has been developed in phases and main tasks as follows. Phase 0: Project inception, Phase 1: Establishment of current status, plans and practices (Legislation, regulation and standards, Radioactive waste management, Waste acceptance criteria), Phase 2: Development of future strategies for long-term safety management and recommendations for safety enhancements. The project team found the general approach use at the installation, the basic design and the operating practices appropriate to international standards. Nevertheless, a number of items subject to potential improvements were also identified. These upgrading recommendations deal with general aspects of the management (mainly storage versus disposal of long-lived sources), site and environmental surveillance, packaging (qualification of containers, waste characterization requirements), the design of an engineered cap and strategies for capping. (author)

  2. Commissioning of qualification of structures, systems and components for seismic and environmental loads of CIRENE nuclear power plant

    International Nuclear Information System (INIS)

    Bianchi, A.; Gatti, F.; Muzzi, F.; Zola, M.; De Pasquali, F.

    1993-01-01

    On behalf of the Italian National Electricity Board (ENEL) concerning the commissioning of qualification of structures, systems and components of CIRENE NPP, ISMES performed a technical surveillance on the documentation concerning the environmental and seismic qualification of the safety related systems and experimental activities (dynamic and static tests) on plant buildings. The aims of the work were: - the evaluation of the qualification carried out (by test, by analysis, by combination of analysis and test) on the equipment and system, compared with the requirements of the ENEL technical specifications and the most recent international regulations; - the experimental determination of modal quantities (frequencies, damping, mode shapes) of the structures and, in the case of reactor building, the complex impedance of the soil for supporting the analytical work. The present paper deals with the criteria, the system and the results concerning the technical surveillance and with the characteristics and the results of the experimental tests

  3. 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

  4. 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.

  5. 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

  6. Qualification of the AUTOBUS Mod. 2 Code

    International Nuclear Information System (INIS)

    Ciarniello, U.; Peroni, P.

    1988-01-01

    The paper presents the qualification of AUTOBUS MOD.2 code. After a brief description of the code itself, all the critical experiments simulated by the code are illustrated to prove the accuracy of criticality calculation and power distribution. An interpretation of the results and a conclusion close this presentation

  7. Qualifications and Skills: The Organisational Perspective

    Science.gov (United States)

    Dafou, Efthimia

    2009-01-01

    This paper portrays the inferences that employers in Greece draw from particular aspects of study programmes, as recorded on educational qualifications. Based on semi-structured interviews with human resource managers in 37 industrial and service organisations and general directors of careers offices in eight higher education institutions, and…

  8. The Diploma Disease. Education, Qualification and Development.

    Science.gov (United States)

    Dore, Ronald

    The aims and motives of schooling are changing, and it is becoming more and more a ritualized process of qualification-earning. The underlying causes of this change are traced through the education histories of Britain, Japan, Sri Lanka, and Kenya. It is illustrated that the competitve scramble for scarce modern jobs has created a "backwash…

  9. 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

  10. STEM Leadership Qualification: Tomorrow's Leaders Today

    Science.gov (United States)

    Williams, Chris

    2009-01-01

    This article features the Science, Technology, Engineering and Mathematics (STEM) Leadership Qualification programme, developed by the Centre for Science Education (CSE) at Sheffield Hallam University in collaboration with Edexcel, which sets out to develop leadership skills and capabilities through contexts in STEM. With six units to complete…

  11. Relationship Between Teachers\\' Qualification And Students ...

    African Journals Online (AJOL)

    It has been observed that students\\' performance in technical subjects is very poor. Coupled with this problem is that of lack of qualified technical teachers. This study determines the relationship between teachers\\' qualification and students\\' performance in technical subjects in selected schools in northern Nigeria.

  12. PR Faculty: What Are Their Qualifications?

    Science.gov (United States)

    Johnson, Thomas B.; Rabin, Kenneth

    1977-01-01

    Discusses a study designed to determine existing trends in the backgrounds and qualifications of public relations instructors and how these might affect public relations education. Available from: Public Relations Review, Ray Hiebert, Dean, College of Journalism, University of Maryland, College Park, MD 20742. (MH)

  13. 5 CFR 330.208 - Qualification requirements.

    Science.gov (United States)

    2010-01-01

    ... perform the duties and responsibilities of the position. (c) The sex of an individual may not be... qualified for a position if he or she: (1) Meets OPM-established or approved qualification standards and requirements for the position, including any minimum educational requirements, and any selection placement...

  14. 42 CFR 485.705 - Personnel qualifications.

    Science.gov (United States)

    2010-10-01

    ... Physical Therapy and Speech-Language Pathology Services § 485.705 Personnel qualifications. (a) General... involved in the furnishing of outpatient physical therapy, occupational therapy, and speech-language...) of the Act and the requirements in part 484 of this chapter. (2) For a speech-language pathologist...

  15. 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...

  16. PROBLEMS OF QUALIFICATION OF MEDIATHION IN BRIBERY

    Directory of Open Access Journals (Sweden)

    Alexander Uskin

    2015-12-01

    Full Text Available The article analysed the controversial issues of qualification of actions of the intermediary in bribery under article 291.1 of the Criminal code, are the kinds of mediation depending on the subject of bribes. On the basis of analysis of legislative construction is concluded decriminalize mediation in bribery if the bribe amount is less than 25 thousand rubles.

  17. 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

  18. 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

  19. 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

  20. Seismic qualification for water chillers of nuclear power plant

    International Nuclear Information System (INIS)

    Wang Chunming

    2005-01-01

    Water chillers are important components of the electric building chilled water system of Nuclear Power Plant. In this article, we describe the seismic qualification methodology. A united method of seismic analysis and experiment testing were applied. Since the seismic classification of the evaporator, condenser and oil separator is 1F, the chillers must satisfy the function criteria. The functional and performance of the control panel were qualified by seismic test. In order to get the seismic time histories of the base of the motor, compressor and control panel, we did time histories analysis for the whole chillers using the seismic acceleration time history of the building floor on which the water chillers was located. Then, these curves were translated into required response spectrum (RRS), which were used by the seismic test of water chillers compressor sets. All passive components, such as evaporator, condenser, oil separator and support, were qualified by seismic stress analysis method. These components were verified to satisfy the standard when they were subjected to the seismic, gravitational, operational pressure and nozzle loads. The Chillers' components were qualified to the specification and the standard. The motor-compressor set and control panel were qualified to the functional and performance criteria. The applied of this methodology qualified the function of the water chillers compressor sets effectively, especially after the aging test. (author)

  1. Actively cooled plasma facing components qualification, commissioning and health monitoring

    International Nuclear Information System (INIS)

    Escourbiac, F.; Durocher, A.; Grosman, A.; Courtois, X.; Farjon, J.-L.; Schlosser, J.; Merola, M.; Tivey, R.

    2006-01-01

    In modern steady state magnetic fusion devices, actively cooled plasma facing components (PFC) have to handle heat fluxes in the range of 10-20 MW/m 2 . This generates a number of engineering constraints: the armour materials must be refractory and compatible with plasma wall interaction requirements (low sputtering and/or low atomic number); the heat sink must offer high thermal conductivity, high mechanical resistance and sufficient ductility; the component cooling system -which is generally based on the circulation of pressurized water in the PFC's heat sink - must offer high thermal heat transfer efficiency. Furthermore, the assembling of the refractory armour material onto the metallic heat sink causes generic difficulties strongly depending on thermo-mechanical properties of materials and design requirements. Life time of the PFC during plasma operation are linked to their manufacturing quality, in particular they are reduced by the possible presence of flaw assembling. The fabrication of PFC in an industrial frame including their qualification and their commissioning - which consists in checking the manufacturing quality during and at the end of manufacture - is a real challenge. From experience gained at Tore Supra on carbon fibre composite flat tiles technology components, it was assessed that a set of qualifications activities must be operated during R(and)D and manufacturing phases. Dedicated Non Destructive Technique (NDT) based on advanced active infrared thermography was developed for this purpose, afterwards, correlations between NDT, high heat flux testing and thermomechanical modelling were performed to analyse damage detection and propagation, and define an acceptance criteria valuable for industrial application. Health monitoring using lock-in technique was also recently operated in-situ of the Tore Supra tokamak for detection of possible defect propagation during operations, presence of acoustic precursor for critical heat flux detection induced

  2. Quantitative assessment of clinical disease status in primary Sjögren's syndrome

    DEFF Research Database (Denmark)

    Asmussen, K.; Andersen, V.; Bendixen, Gunnar

    1999-01-01

    ophthalmology, Sjögren's syndrome, terminology, classification criteria, status indices, immunoinflammation, cytokines......ophthalmology, Sjögren's syndrome, terminology, classification criteria, status indices, immunoinflammation, cytokines...

  3. Social Advertising Quality: Assessment Criteria

    Directory of Open Access Journals (Sweden)

    S. B. Kalmykov

    2017-01-01

    Full Text Available Purpose: the The purpose of the publication is development of existing criterial assessment in social advertising sphere. The next objectives are provided for its achievement: to establish research methodology, to develop the author’s version of necessary notional apparatus and conceptual generalization, to determine the elements of social advertising quality, to establish the factors of its quality, to conduct the systematization of existing criteria and measuring instruments of quality assessment, to form new criteria of social advertising quality, to apply received results for development of criterial assessment to determine the further research perspectives. Methods: the methodology of research of management of social advertising interaction with target audience, which has dynamic procedural character with use of sociological knowledge multivariate paradigmatic status, has been proposed. Results: the primary received results: the multivariate paradigmatic research basis with use of works of famous domestic and foreign scientists in sociology, qualimetry and management spheres; the definitions of social advertising, its quality, sociological quality provision system, target audience behavior model during social advertising interaction are offered; the quality factors with three groups by level of effect on consumer are established; the systematization of existing quality and its measure instruments assessment criteria by detected social advertising quality elements are conducted; the two new criteria and its management quality assessment measuring instruments in social advertising sphere are developed; the one of the common groups of production quality criteria – adaptability with considering of new management quality criteria and conducted systematization of existing social advertising creative quality assessment criteria development; the perspective of further perfection of quality criterial assessment based on social advertising

  4. 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

  5. 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

  6. Secondary Waste Cast Stone Waste Form Qualification Testing Plan

    Energy Technology Data Exchange (ETDEWEB)

    Westsik, Joseph H.; Serne, R. Jeffrey

    2012-09-26

    The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is being constructed to treat the 56 million gallons of radioactive waste stored in 177 underground tanks at the Hanford Site. The WTP includes a pretreatment facility to separate the wastes into high-level waste (HLW) and low-activity waste (LAW) fractions for vitrification and disposal. The LAW will be converted to glass for final disposal at the Integrated Disposal Facility (IDF). Cast Stone – a cementitious waste form, has been selected for solidification of this secondary waste stream after treatment in the ETF. The secondary-waste Cast Stone waste form must be acceptable for disposal in the IDF. This secondary waste Cast Stone waste form qualification testing plan outlines the testing of the waste form and immobilization process to demonstrate that the Cast Stone waste form can comply with the disposal requirements. Specifications for the secondary-waste Cast Stone waste form have not been established. For this testing plan, Cast Stone specifications are derived from specifications for the immobilized LAW glass in the WTP contract, the waste acceptance criteria for the IDF, and the waste acceptance criteria in the IDF Permit issued by the State of Washington. This testing plan outlines the testing needed to demonstrate that the waste form can comply with these waste form specifications and acceptance criteria. The testing program must also demonstrate that the immobilization process can be controlled to consistently provide an acceptable waste form product. This testing plan also outlines the testing needed to provide the technical basis for understanding the long-term performance of the waste form in the disposal environment. These waste form performance data are needed to support performance assessment analyses of the long-term environmental impact of the secondary-waste Cast Stone waste form in the IDF

  7. Novel qualification methodology for subsea processing

    Energy Technology Data Exchange (ETDEWEB)

    Nilsen, Paal Jahre; Bratfos, Hans A. [Det Norske Veritas, Oslo (Norway)

    2004-07-01

    The purpose of the Reliability Analysis is to quantify the overall reliability of the technology to confirm that the functional requirements and the target reliability laid down in the Qualification Basis are met. On this basis DNV may issue a Statement of Fitness for Service affirming that the technology is considered qualified. Although a technology may be convincingly proven fit for service without using reliability measures, a quantified reliability makes the technology more competitive in a business where profitability is directly related to the reliability of the technology. In this respect it should also be noted that a reliability analysis require specific input data that sometimes must be derived by testing. It is therefore important to take this into consideration already in the selection and planning of qualification methods. (author)

  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. Essential elements of an effective data qualification

    International Nuclear Information System (INIS)

    Jenkins, E.W.

    1994-01-01

    Before data is used in any statistical evaluation, it should be subjected to a thorough data qualification to ensure its integrity. Data Qualification efforts may vary in scope but should all contain certain basic elements. Outliers should be eliminated so that any estimates obtained from the data will not be overly biased. Plots may be generated to uncover potential outliers, and these observations can be confirmed as being anomalous through the use of statistical testing. Non-stationarity of the data (i.e., time trends) may also be initially identified through the use of plots and confirmed by the results of statistical analyses, e.g., the use of the Kendall's tau statistic. When the dataset has been qualified, replicates and duplicates should be averaged to create a pseudo-independence between data points. An algorithm based on the groundwater data from the Savannah River Site has been used by the Applied Statistics Group at Westinghouse Savannah River Company for this

  10. 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

  11. 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

  12. 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

  13. 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.

  14. Qualification of RETRAN for simulator applications

    International Nuclear Information System (INIS)

    Harrison, J.F.

    1988-01-01

    The use of full-scope control room replica simulators increased substantially following the accident at Three Mile Island Unit 2. The technical capability required to represent severe events has been included, in varying degrees, in most simulators purchased since the TMI-2 accident. The ability of the instructor to create a large variety of combinations of malfunctions has also greatly expanded. The nuclear industry has developed a standard which establishes the minimum functional requirements for full-scope nuclear control room simulators used for operator training. This standard, ANSI/ANS-3.5, was first issued in 1981 and was reissued in 1985. A method for performing simulator qualification with best estimate analytical data has been proposed in EPRI NP-4243, Analytic Simulator Qualification Methodology. The idea presented there is to choose a set of transients which drive the simulator into all the system conditions (dynamic states) likely to be encountered during operator training. The key observable parameters for each state are compared to analyses performed with the best estimate analytical model The closeness of the comparison determines the fidelity of the simulator. The approach described in EPRI NP-4243 has been adapted for evaluating RETRAN's capability for use in simulator qualification. RETRAN analyses which compare the RETRAN results to plant or test facility data are evaluated with respect to the simulator test matrix documented in EPRI NP-4243

  15. 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

  16. 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

  17. Software qualification of selected TOUGH2 modules

    International Nuclear Information System (INIS)

    Wu, Y.S.; Ahlers, C.F.; Fraser, P.; Simmons, A.; Pruess, K.

    1996-10-01

    The purpose of this package of reports is to provide all software baseline documents necessary for the software qualification of the single-phase Gas (EOS1G), Effective Continuum Method (ECM), Saturated/Unsaturated Flow (EOS9), and Radionuclide Transport (T2R3D) modules of TOUGH2, a numerical simulation code for multi-dimensional coupled fluid and heat flow of multiphase, multicomponent fluid mixtures in porous and fractured media. This report contains the following sections: (1) Requirements Specification, (2) Design Description, (3) Software Validation Test Plan and Report, (4) Software User Documentation, and (5) Appendices. These sections comprise sequential parts of the Software Life Cycle, and are not intended to stand alone but should be used in conjunction with the TOUGH User's Guide (Pruess, 1987), TOUGH2--A General Purpose Numerical Simulator for Multiphase Fluid and Heat Flow (Pruess, 1991), and the above-referenced TOUGH2 software qualification document. The qualification package is complete with the attached Software Identification Form and executable source code for the single-phase Gas, Effective Continuum method, Saturated/Unsaturated Flow, and Radionuclide Transport modules of TOUGH2

  18. Criteria for decommissioning

    International Nuclear Information System (INIS)

    Ricci, P.F.

    1988-01-01

    In this paper the authors describe three risk acceptability criteria as parts of a strategy to clean up decommissioned facilities, related to both the status quo and to a variety of alternative technical clean-up options. The acceptability of risk is a consideration that must enter into any decision to establish when a site is properly decommissioned. To do so, both the corporate and public aspects of the acceptability issue must be considered. The reasons for discussion the acceptability of risk are to: Legitimize the process for making cleanup decisions; Determine who is at risk, who benefits, and who bears the costs of site cleanup, for each specific cleanup option, including the do nothing option; Establish those factors that, taken as a whole, determine measures of acceptability; Determine chemical-specific aggregate and individual risk levels; and Establish levels for cleanup. The choice of these reasons is pragmatic. The method consistent with these factors is risk-risk-effectiveness: the level of cleanup must be consistent with the foreseeable use of the site and budget constraints. Natural background contamination is the level below which further cleanup is generally inefficient. Case-by-case departures from natural background are to be considered depending on demonstrated risk. For example, a hot spot is obviously a prima facie exception, but should be rebuttable. Rebuttability means that, through consensus, the ''hot spot'' is shown not to be associated with exposure

  19. AGR-3/4 Final Data Qualification Report for ATR Cycles 151A through 155B-1

    Energy Technology Data Exchange (ETDEWEB)

    Pham, Binh T. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-03-01

    This report provides the qualification status of experimental data for the entire Advanced Gas Reactor 3/4 (AGR 3/4) fuel irradiation. AGR-3/4 is the third in a series of planned irradiation experiments conducted in the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL) for the AGR Fuel Development and Qualification Program, which supports development of the advanced reactor technology under the INL ART Technology Development Office (TDO). The main objective of AGR-3/4 irradiation is to provide a known source of fission products for subsequent transport through compact matrix and structural graphite materials due to the presence of designed-to-fail fuel particles. Full power irradiation of the AGR 3/4 test began on December 14, 2011 (ATR Cycle 151A), and was completed on April 12, 2014 (end of ATR Cycle 155B) after 369.1 effective full power days of irradiation. The AGR-3/4 test was in the reactor core for eight of the ten ATR cycles between 151A and 155B. During the unplanned outage cycle, 153A, the experiment was removed from the ATR northeast flux trap (NEFT) location and stored in the ATR canal. This was to prevent overheating of fuel compacts due to higher than normal ATR power during the subsequent Powered Axial Locator Mechanism cycle, 153B. The AGR 3/4 test was inserted back into the ATR NEFT location during the outage of ATR Cycle 154A on April 26, 2013. Therefore, the AGR-3/4 irradiation data received during these 2 cycles (153A and 153B) are irrelevant and their qualification status isnot included in this report. Additionally, during ATR Cycle 152A the ATR core ran at low power for a short enough duration that the irradiation data are not used for physics and thermal calculations. However, the qualification status of irradiation data for this cycle is still covered in this report. As a result, this report includes data from 8 ATR Cycles: 151A, 151B, 152A, 152B, 154A, 154B, 155A, and 155B, as recorded in the Nuclear Data Management and

  20. Report on the Regulators Experience of NDT Qualification for In-service Inspection of Nuclear Components

    International Nuclear Information System (INIS)

    2003-08-01

    In November 1992, the Nuclear Regulators Working Group (NRWG) decided to set up a task force on qualification of non-destructive testing (NDT) systems for pre and in-service inspection of light water reactors. The first task was to agree on the philosophy and principles governing the qualification of techniques, equipment, software, procedures, and personnel for NDT to be used for the inspection of structural components that are important to safety in nuclear power plants; and to establish a common view on essential aspects of NDT qualifications. The first task, which also included a comparison of the common views of the European regulators with the qualification approach outlined in Appendix VIII to Section XI of the ASME Code, was completed in 1996. The result was published in the report ''Common position of European regulators on qualification of NDT systems for pre- and in-service inspection of light water reactor components''2. In parallel, the European nuclear power industries had set up a working group, the European Network for Inspection Qualification (ENIQ), to discuss and agree on how to perform inspection qualifications. In 1995, ENIQ finalized its first version of ''European methodology for qualification of non-destructive tests''3. A second version 4 was then published in 1997. This second version is in relatively close agreement with the principles given in the regulators common position document. With these two basic documents, a platform was established for the further development of qualification strategies in the European countries. The second task of the NRWG Task Force was to follow and evaluate the first ENIQ pilot study from a regulatory point of view. The objective of this pilot study was to explore ways of how to apply the European qualification methodology and to test its feasibility. The pilot study commenced late 1996 and was planned to be finalized a year later. Depending on unforeseen difficulties, the pilot study has been delayed

  1. Qualification of high heat flux components: application to target elements of W7-X divertor

    International Nuclear Information System (INIS)

    Missirlian, M; Durocher, A; Grosman, A; Schlosser, J; Boscary, J; Escourbiac, F; Cismondi, F

    2007-01-01

    The development of actively cooled plasma-facing components (PFC) represents one of fusion's most challenging engineering efforts. In this frame, a high-quality bonding between the refractory armour and the heat sink is essential to ensure the heat removal capability and the thermal performances of PFC. Experience gained during manufacturing of Tore Supra actively cooled PFC led to the establishment of a qualification methodology and provided a large experience of acceptance criteria using an active infrared thermography (systeme d'acquisition de traitement infra-rouge, SATIR). This paper presents the application of this qualification process to the W7-X pre-series components, with the objective of assessing and defining workable acceptance criteria that enable reliable predictions of performance at the nominal heat flux requirements in W7-X. Finally, to check the reliability of the non-destructive examination (NDE) method by transient infrared thermography, the newly defined acceptance criteria were applied to W7-X pre-series target elements (batch no. 3). The SATIR results, benchmarked with HHF tests performed on the GLADIS ion beam facility were discussed to assess the ability to detect critical defects at the interface between tiles and heat sink

  2. QUALIFICATIONS FRAMEWORKS FOR LIFELONG LEARNING CONQUERING THE WORLD?

    Directory of Open Access Journals (Sweden)

    Arjen Deij

    2014-01-01

    Full Text Available The paper reveals the international prospects of developing and spreading the qualifications frameworks across the globe. It introduces the key terms and concepts related to the given issue, and examines both the benefits and challenges of qualifications frameworks implementation. The author looks into the origins and causes of the worldwide interest in qualifications framework application, and gives the overview of related recent publications and their conclusions to reinforce the provided argumentation.

  3. 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

  4. 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)

  5. 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)

  6. 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

  7. Chapter No.8. Personnel qualification and training

    International Nuclear Information System (INIS)

    2002-01-01

    The overall training system and the development projects of training the staff of all categories from NPP V-1, NPP V-2 Bohunice, SE-VYZ and NPP Mochovce were the subject of UJD's attention. During 2001 following inspections were carried out on nuclear personnel training: - PP's Bohunice: an inspection focused on compliance with requirements for staff qualifications and compliance with the prescribed training of Bohunice plant staff; - Mochovce NPP: an inspection focused on compliance with the requirements for staff qualifications and compliance with the prescribed training of NPP Mochovce staff; - SE-VYZ: an inspection focused on compliance with the requirements for staff qualifications and compliance with the prescribed training of SE-VYZ staff. Training the staff of the NPP's Bohunice: - The fundamental and periodical theoretical training as sure as the fundamental and periodical simulator training is carried out by the VUJE Training centre in Trnava. - The fundamental practical training in the workplace and training for the change work- rank is carried at Bohunice plant. Training of the staff of the NPP Mochovce: - The fundamental and periodical theoretical training is carried out by the VUJE Training centre in Trnava. The fundamental practical training in the workplace and training for the change work- rank as well as the fundamental and periodical simulator training is carried at Mochovce plant. Based on a successful passing of examination before the examining committee, UJD issues a certificate on special professional skills of selected staff members of nuclear installations for specific activity for the given type of nuclear installation and for the following positions: 1. Scientific shift manager for start up with the right of manipulation; 2. Shift supervisor; 3. Unit supervisor; 4. Primary circuit operator; 5. Secondary circuit operator; 6. Reactor physicist; 7. Scientific shift manager for start up without the right of manipulation. Examinations of

  8. 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

  9. Qualification of nuclear power plant inspection, examination, and testing personnel. Revision 1, September 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, requires that the quality assurance program provide for indoctrination and training of personnel performing activities affecting quality as necessary to ensure that quality assurance personnel achieve and maintain suitable proficiency. This guide describes a method acceptable to the NRC staff for complying with the Commission's regulations with regard to qualification of inspection, examination, and testing personnel for all types of nuclear power plants

  10. 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.)

  11. Qualification of ISI for Bulgarian NPP: UK support

    International Nuclear Information System (INIS)

    Booler, R.

    2000-01-01

    UK Regulator (NII) Phare project provides an assistance to the Bulgarian Regulator in setting up the technical infrastructure for inspection qualification consistent with IAEA Guidelines and western European practice. The Strategy Document defines the methodology for inspection qualification and general roles and responsibilities of the involved organizations. The Qualification Inputs Document describes the information required for the Technical Specifications (component details, inspection aims and limitations). It applies the idea of qualification level - level 1(lowest) to level 3 (highest). The Qualification Procedure Document provides a guidance to the utility ('Kozloduy' NPP) on the preparation of Qualification Procedures (QP). The appendix provides a specific guidance on the performance of the all aspects of qualification at different levels and recommendations for technical justification. QB Method Working Document provides guidance for the Qualification Body. Facilities and Resources Document defines the facilities and resources required for the Qualification Body to perform the tasks described in the Method Working Document. High level QA Document defines the principles of quality control. Other issues and progress report are also presented

  12. 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)

  13. 77 FR 10607 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2012-02-22

    ...-2011-0367] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor... diabetes mellitus (ITDM) from operating commercial motor vehicles (CMVs) in interstate commerce. The...). [[Page 10608

  14. Seismic evaluation of piping systems using screening criteria

    International Nuclear Information System (INIS)

    Campbell, R.D.; Landers, D.F.; Minichiello, J.C.; Slagis, G.C.; Antaki, G.A.

    1994-01-01

    This document may be used by a qualified review team to identify potential sources of seismically induced failure in a piping system. Failure refers to the inability of a piping system to perform its expected function following an earthquake, as defined in Table 1. The screens may be used alone or with the Seismic Qualification Utility Group -- Generic Implementation Procedure (SQUG-GIP), depending on the piping system's required function, listed in Table 1. Features of a piping system which do not the screening criteria are called outliers. Outliers must either be resolved through further evaluations, or be considered a potential source of seismically induced failure. Outlier evaluations, which do not necessarily require the qualification of a complete piping system by stress analysis, may be based on one or more of the following: simple calculations of pipe spans, search of the test or experience data, vendor data, industry practice, etc

  15. 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

  16. ITER ECRH Upper Launcher: Test plan for qualification of the Diamond Torus Window Prototype III

    Energy Technology Data Exchange (ETDEWEB)

    Schreck, Sabine, E-mail: sabine.schreck@kit.edu [Karlsruhe Institute of Technology, Institute for Applied Materials, Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen (Germany); Aiello, Gaetano; Meier, Andreas; Strauss, Dirk [Karlsruhe Institute of Technology, Institute for Applied Materials, Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen (Germany); Gagliardi, Mario; Saibene, Gabriella [F4E, Antennas and Plasma Engineering, Josep Pla 2, Torres Diagonal Litoral B3, 08019 Barcelona (Spain); Scherer, Theo [Karlsruhe Institute of Technology, Institute for Applied Materials, Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen (Germany)

    2016-11-01

    Highlights: • A qualification program for the ITER diamond torus window is being developed. • The testing program for the qualification of the bare diamond disk is defined. • First qualification tests show a very good quality of the diamond disk prototypes. - Abstract: The diamond window is part of the electron cyclotron heating upper launcher system for ITER. Together with the isolation valve it constitutes the primary vacuum boundary and it also acts as first tritium barrier. Therefore the window is classified as Safety/Protection Important Component (SIC/PIC) with the nuclear safety function “confinement”. As the diamond window unit is not entirely covered by standard codes, an ad-hoc qualification program needs to be defined, including analysis, prototyping and testing. In the framework of a contract with F4E, the test program for a diamond window prototype is being developed with the aim to prove its operability for normal, accidental and incidental conditions as identified in the ITER load specifications. Tests range from dielectric loss measurements for the bare Chemical Vapour Deposition (CVD) diamond disk up to mechanical and vacuum tests for the complete window assembly. Finally mm-wave properties have to be characterized for the complete window. A clear definition of the testing requirements and of the acceptance criteria is necessary as well as a complete documentation of the process. This paper will present the development of the test plan for a window prototype, which is currently under manufacturing. First tests are directed to the characterization of the bare diamond disk with a focus on its dielectric properties.

  17. Questions of qualification exam for non-destructive testing and materials science - the first level

    International Nuclear Information System (INIS)

    Shaaban, H.I.; Addarwish, J.M.A.

    2013-01-01

    The book contains seven chapters: Questions of qualification for magnetic particles testing method - Questions of qualification for liquids penetrant testing method - Questions of qualification for the visual inspection testing method - Questions of qualification for the ultrasonic testing method - Questions of qualification for the eddy current testing method - Questions of rehabilitation for industrial radiographic testing method - Qualification questions about materials science and manufacturing defects of castings and welding and comparison between non-destructive testing methods.

  18. Recruitment, qualification and training of personnel for nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2005-01-01

    The objective of this Safety Guide is to outline the various factors that should to be considered in order to ensure that the operating organization has a sufficient number of qualified personnel for safe operation of a nuclear power plant. In particular, the objective of this publication is to provide general recommendations on the recruitment and selection of plant personnel and on the training and qualification practices that have been adopted in the nuclear industry since the predecessor Safety Guide was published in 1991. In addition, this Safety Guide seeks to establish a framework for ensuring that all managers and staff employed at a nuclear power plant demonstrate their commitment to the management of safety to high professional standards. This Safety Guide deals specifically with those aspects of qualification and training that are important to the safe operation of nuclear power plants. It provides recommendations on the recruitment, selection, qualification, training and authorization of plant personnel. That is, of all personnel in all safety related functions and at all levels of the plant. Some parts or all of this Safety Guide may also be used, with due adaptation, as a guide to the recruitment, selection, training and qualification of staff for other nuclear installations (such as research reactors or nuclear fuel cycle facilities). Section 2 gives guidance on the recruitment and selection of suitable personnel for a nuclear power plant. Section 3 gives guidance on the establishment of personnel qualification, explains the relationship between qualification and competence, and identifies how competence may be developed through education, experience and training. Section 4 deals with general aspects of the training policy for nuclear power plant personnel: the systematic approach, training settings and methods, initial and continuing training, and the keeping of training records. Section 5 provides guidance on the main aspects of training programmes

  19. Recruitment, qualification and training of personnel for nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2002-01-01

    The objective of this Safety Guide is to outline the various factors that should to be considered in order to ensure that the operating organization has a sufficient number of qualified personnel for safe operation of a nuclear power plant. In particular, the objective of this publication is to provide general recommendations on the recruitment and selection of plant personnel and on the training and qualification practices that have been adopted in the nuclear industry since the predecessor Safety Guide was published in 1991. In addition, this Safety Guide seeks to establish a framework for ensuring that all managers and staff employed at a nuclear power plant demonstrate their commitment to the management of safety to high professional standards. This Safety Guide deals specifically with those aspects of qualification and training that are important to the safe operation of nuclear power plants. It provides recommendations on the recruitment, selection, qualification, training and authorization of plant personnel; that is, of all personnel in all safety related functions and at all levels of the plant. Some parts or all of this Safety Guide may also be used, with due adaptation, as a guide to the recruitment, selection, training and qualification of staff for other nuclear installations (such as research reactors or nuclear fuel cycle facilities). Section 2 gives guidance on the recruitment and selection of suitable personnel for a nuclear power plant. Section 3 gives guidance on the establishment of personnel qualification, explains the relationship between qualification and competence, and identifies how competence may be developed through education, experience and training. Section 4 deals with general aspects of the training policy for nuclear power plant personnel: the systematic approach, training settings and methods, initial and continuing training, and the keeping of training records. Section 5 provides guidance on the main aspects of training programmes

  20. Test report: Electron-proton spectrometer qualification test unit, qualification test

    Science.gov (United States)

    Vincent, D. L.

    1972-01-01

    Qualification tests of the electron-proton spectrometer test unit are presented. The tests conducted were: (1) functional, (2) thermal/vacuum, (3) electromagnetic interference, (4) acoustic, (5) shock, (6) vibration, and (7) humidity. Results of each type of test are presented in the form of data sheets.

  1. 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

  2. NRC Information No. 88-04: Inadequate qualification and documentation of fire barrier penetration seals

    International Nuclear Information System (INIS)

    Rossi, C.E.

    1992-01-01

    The current NRC review was prompted by reports, inspection findings, allegations, and other information that indicated the possibility that NRC requirements for fire barrier penetration seals were not being met in all aspects. The review included: evaluations of fire barrier penetration seal specifications and procedures developed by licensees, licensee agents, and licensee contractors; evaluations of various fire barrier penetration seal tests and test data; and inspections of various fire barrier penetrations seal designs and installations. The types of concerns identified to date and mentioned below are related to weaknesses in the implementation of NRC requirements and guidelines as related to fire barrier penetration seal design qualification. The NRC review also has identified a current practice that can affect the qualification status of installed seals. Plant modifications are being made that require running new cable and conduits through existing penetration seals. These modifications are generally being made without an associated technical review to ensure that the resulting penetration seal design configuration or design parameters are consistent with those validated by initial qualification tests. Over a period of time, numerous minor modifications to the same area could cumulatively result in a degraded fire barrier rating

  3. 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

  4. 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.

  5. 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)

  6. 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)

  7. 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.

  8. Inspection Qualification Centre in NPP 'Kozloduy'

    International Nuclear Information System (INIS)

    Mikhovski, M.

    2000-01-01

    In May 1999 according to the working plan of the IAEA project RER 4/020 and the decision of the NPP the Inspection Qualification Centre (IQC) has been established in order to provide examination services in the NPP. During year 1999 IVC (AEA Technology) in the framework of the DTI project provides consulting and technical assistance to the NPP, IQC, Bulgarian Academy of Sciences and Regulatory Authorities in setting up the IQC infrastructure. Now IQC work as an independent inspection body B type. The IQC activities for the period 1999-2000 are presented and further tasks are outlined

  9. 49 CFR 391.11 - General qualifications of drivers.

    Science.gov (United States)

    2010-10-01

    ... understand highway traffic signs and signals in the English language, to respond to official inquiries, and... QUALIFICATIONS OF DRIVERS AND LONGER COMBINATION VEHICLE (LCV) DRIVER INSTRUCTORS Qualification and... motor vehicle unless he/she is qualified to drive a commercial motor vehicle. Except as provided in...

  10. Qualification Paths of Adult Educators in Sweden and Denmark

    Science.gov (United States)

    Andersson, Per; Kopsen, Susanne; Larson, Anne; Milana, Marcella

    2013-01-01

    The qualification of adult educators is a central aspect of the quality of adult education. However, within current policy discourses and adult education research on the professional development of prospective adult educators, little attention is paid to teacher qualification when compared to other fields of education and training. In this study,…

  11. 42 CFR 21.47 - Examination; anticipation of meeting qualifications.

    Science.gov (United States)

    2010-10-01

    ... 42 Public Health 1 2010-10-01 2010-10-01 false Examination; anticipation of meeting qualifications. 21.47 Section 21.47 Public Health PUBLIC HEALTH SERVICE, DEPARTMENT OF HEALTH AND HUMAN SERVICES PERSONNEL COMMISSIONED OFFICERS Appointment § 21.47 Examination; anticipation of meeting qualifications. A...

  12. 14 CFR 135.247 - Pilot qualifications: Recent experience.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 3 2010-01-01 2010-01-01 false Pilot qualifications: Recent experience... Flight Crewmember Requirements § 135.247 Pilot qualifications: Recent experience. (a) No certificate holder may use any person, nor may any person serve, as pilot in command of an aircraft carrying...

  13. 14 CFR 121.437 - Pilot qualification: Certificates required.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 3 2010-01-01 2010-01-01 false Pilot qualification: Certificates required... Pilot qualification: Certificates required. (a) No pilot may act as pilot in command of an aircraft (or... pilots) unless he holds an airline transport pilot certificate and an appropriate type rating for that...

  14. 14 CFR 121.439 - Pilot qualification: Recent experience.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 3 2010-01-01 2010-01-01 false Pilot qualification: Recent experience. 121... Pilot qualification: Recent experience. (a) No certificate holder may use any person nor may any person serve as a required pilot flight crewmember, unless within the preceding 90 days, that person has made...

  15. 14 CFR 125.285 - Pilot qualifications: Recent experience.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 3 2010-01-01 2010-01-01 false Pilot qualifications: Recent experience... Requirements § 125.285 Pilot qualifications: Recent experience. (a) No certificate holder may use any person, nor may any person serve, as a required pilot flight crewmember unless within the preceding 90...

  16. 12 CFR 563c.3 - Qualification of public accountant.

    Science.gov (United States)

    2010-01-01

    ... 12 Banks and Banking 5 2010-01-01 2010-01-01 false Qualification of public accountant. 563c.3... REQUIREMENTS Form and Content of Financial Statements § 563c.3 Qualification of public accountant. (See also 17 CFR 210.2-01.) The term “qualified public accountant” means a certified public accountant or licensed...

  17. 30 CFR 75.155 - Qualified hoisting engineer; qualifications.

    Science.gov (United States)

    2010-07-01

    ... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Qualified hoisting engineer; qualifications. 75... Persons § 75.155 Qualified hoisting engineer; qualifications. (a)(1) A person is a qualified hoisting engineer within the provisions of subpart O of this part, for the purpose of operating a steam-driven hoist...

  18. Qualifications of Subject Teachers in Special Education Schools

    Science.gov (United States)

    Rasmussen, Meryem Uçar; Kis, Arzu

    2018-01-01

    Teacher qualifications are essential to be able to teach children with special needs efficiently. Therefore the aim of this study is to determine the qualifications of subject teachers in special education schools in Turkey. In the study 20 subject teachers within the field of music, art and sports who worked in special education schools in Turkey…

  19. 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

  20. 48 CFR 1252.237-70 - Qualifications of contractor employees.

    Science.gov (United States)

    2010-10-01

    ... contractor employees. 1252.237-70 Section 1252.237-70 Federal Acquisition Regulations System DEPARTMENT OF....237-70 Qualifications of contractor employees. As prescribed in (TAR) 48 CFR 1237.110(a), insert the following clause: Qualifications of Contractor Employees (APR 2005) a. Definitions. As used in this clause...

  1. 48 CFR 1437.7001 - Contractor qualification requirements.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 5 2010-10-01 2010-10-01 false Contractor qualification requirements. 1437.7001 Section 1437.7001 Federal Acquisition Regulations System DEPARTMENT OF THE INTERIOR... Contractor qualification requirements. (a) Prior to award of a contract for real property appraisal services...

  2. 49 CFR 214.343 - Training and qualification, general.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 4 2010-10-01 2010-10-01 false Training and qualification, general. 214.343... ADMINISTRATION, DEPARTMENT OF TRANSPORTATION RAILROAD WORKPLACE SAFETY Roadway Worker Protection § 214.343 Training and qualification, general. (a) No employer shall assign an employee to perform the duties of a...

  3. Qualifications Frameworks and Their Conflicting Social Imaginaries of Globalisation

    Science.gov (United States)

    Louise Sarauw, Laura

    2012-01-01

    Critics often see the European Bologna Process as a univocal standardisation of higher education. By exploring how different qualifications frameworks project different social imaginaries of globalisation, this article takes a different stance. The overarching qualifications framework of the Bologna Process rests on a socially constituted and…

  4. 32 CFR 935.139 - Motor vehicle operator qualifications.

    Science.gov (United States)

    2010-07-01

    ... 32 National Defense 6 2010-07-01 2010-07-01 false Motor vehicle operator qualifications. 935.139... AND INSULAR REGULATIONS WAKE ISLAND CODE Motor Vehicle Code § 935.139 Motor vehicle operator qualifications. (a) No person may operate a privately owned motor vehicle on Wake Island unless he has an island...

  5. 29 CFR 1926.1076 - Qualifications of dive team.

    Science.gov (United States)

    2010-07-01

    ... 29 Labor 8 2010-07-01 2010-07-01 false Qualifications of dive team. 1926.1076 Section 1926.1076 Labor Regulations Relating to Labor (Continued) OCCUPATIONAL SAFETY AND HEALTH ADMINISTRATION... § 1926.1076 Qualifications of dive team. Note: The requirements applicable to construction work under...

  6. 29 CFR 1910.410 - Qualifications of dive team.

    Science.gov (United States)

    2010-07-01

    ... 29 Labor 5 2010-07-01 2010-07-01 false Qualifications of dive team. 1910.410 Section 1910.410... Requirements § 1910.410 Qualifications of dive team. (a) General. (1) Each dive team member shall have the experience or training necessary to perform assigned tasks in a safe and healthful manner. (2) Each dive team...

  7. Inspection qualification and implementation of ENIQ in Sweden

    International Nuclear Information System (INIS)

    Zettervall, Tommy

    2013-01-01

    Many countries are currently considering their approaches to inspection qualification and risk-informed in-service inspection (RI-ISI) and are carefully assessing experience data. In Europe most of the utilities operating nuclear power plants have joined together to form the European Network for Inspection Qualification ENIQ. In practice, qualification can be performed with varying degrees of complexity and cost, varying from capability statement based on existing evidence, through to an extensive qualification consisting of a detailed Technical Justification (TJ) together with open and blind trials on full-scale test blocks. An Inspection Qualification is an investigation and demonstration, which confirm that an inspection system has the ability to solve its specific tasks. The qualification is a Quality Assurance of an inspection system based on documents and practical trials. A reliable inspection system, based on a reliable qualification and correct prerequisites, will reduce total costs for Licensees and increase the credibility of the inspection result. To get such inspection system, which could be valid for many years, it's of necessity to fulfil all included parts in the process. It begins with the Technical Specification from Licensee, where input data and requirements about the actual component are specified. To get an inspection system that could live over time, the Technical Justification is of importance. Finally the test blocks and used simulation techniques play an important part of the final result, and these test blocks together with TJ form the basis for qualification body's decision. (author)

  8. 27 CFR 19.823 - Changes after original qualification.

    Science.gov (United States)

    2010-04-01

    ... 27 Alcohol, Tobacco Products and Firearms 1 2010-04-01 2010-04-01 false Changes after original... Vaporizing Process Qualification Documents § 19.823 Changes after original qualification. When there is a change in the information recorded in the original approved application, the proprietor shall make a...

  9. 12 CFR 231.3 - Qualification as a financial institution.

    Science.gov (United States)

    2010-01-01

    ... 12 Banks and Banking 3 2010-01-01 2010-01-01 false Qualification as a financial institution. 231.3... RESERVE SYSTEM NETTING ELIGIBILITY FOR FINANCIAL INSTITUTION (REGULATION EE) § 231.3 Qualification as a financial institution. (a) A person qualifies as a financial institution for purposes of sections 401-407 of...

  10. Qualification Users' Perceptions and Experiences of Assessment Reliability

    Science.gov (United States)

    Chamberlain, Suzanne

    2013-01-01

    This paper presents the findings of a study designed to explore qualification users' perceptions and experiences of reliability in the context of national assessment outcomes in England. The study consisted of 17 focus groups conducted across six sectors of qualification users: students, teachers, trainee teachers, job-seekers, employers and…

  11. Systematic assessment of benefits and risks: study protocol for a multi-criteria decision analysis using the Analytic Hierarchy Process for comparative effectiveness research [v1; ref status: indexed, http://f1000r.es/1fk

    Directory of Open Access Journals (Sweden)

    Nisa M Maruthur

    2013-07-01

    Full Text Available Background: Regulatory decision-making involves assessment of risks and benefits of medications at the time of approval or when relevant safety concerns arise with a medication. The Analytic Hierarchy Process (AHP facilitates decision-making in complex situations involving tradeoffs by considering risks and benefits of alternatives. The AHP allows a more structured method of synthesizing and understanding evidence in the context of importance assigned to outcomes. Our objective is to evaluate the use of an AHP in a simulated committee setting selecting oral medications for type 2 diabetes.  Methods: This study protocol describes the AHP in five sequential steps using a small group of diabetes experts representing various clinical disciplines. The first step will involve defining the goal of the decision and developing the AHP model. In the next step, we will collect information about how well alternatives are expected to fulfill the decision criteria. In the third step, we will compare the ability of the alternatives to fulfill the criteria and judge the importance of eight criteria relative to the decision goal of the optimal medication choice for type 2 diabetes. We will use pairwise comparisons to sequentially compare the pairs of alternative options regarding their ability to fulfill the criteria. In the fourth step, the scales created in the third step will be combined to create a summary score indicating how well the alternatives met the decision goal. The resulting scores will be expressed as percentages and will indicate the alternative medications' relative abilities to fulfill the decision goal. The fifth step will consist of sensitivity analyses to explore the effects of changing the estimates. We will also conduct a cognitive interview and process evaluation.  Discussion: Multi-criteria decision analysis using the AHP will aid, support and enhance the ability of decision makers to make evidence-based informed decisions consistent

  12. The State of the Otolaryngology Match: A Review of Applicant Trends, "Impossible" Qualifications, and Implications.

    Science.gov (United States)

    Bowe, Sarah N; Schmalbach, Cecelia E; Laury, Adrienne M

    2017-06-01

    Objective This State of the Art Review aims (1) to define recent qualifications of otolaryngology resident applicants by focusing on United States Medical Licensing Examination (USMLE) scores, Alpha Omega Alpha (AOA) status, and research/publications and (2) to summarize the current literature regarding the relationship between these measures and performance in residency. Data Sources Electronic Residency Application Service, National Residency Matching Program, PubMed, Ovid, and GoogleScholar. Review Methods Electronic Residency Application Service and National Residency Matching Program data were analyzed to evaluate trends in applicant numbers and qualifications. Additionally, a literature search was performed with the aforementioned databases to identify relevant articles published in the past 5 years that examined USMLE Step 1 scores, AOA status, and research/publications. Conclusions Compared with other highly competitive fields over the past 3 years, the only specialty with decreasing applicant numbers is otolaryngology, with the rest remaining relatively stable or slightly increased. Additionally, USMLE Step 1 scores, AOA status, and research/publications do not reliably correlate with performance in residency. Implications for Practice The consistent decline in applications for otolaryngology residency is concerning and reflects a need for change in the current stereotype of the "ideal" otolaryngology applicant. This includes consideration of additional selection measures focusing on noncognitive and holistic qualities. Furthermore, otolaryngology faculty should counsel medical students that applying in otolaryngology is not "impossible" but rather a feasible and worthwhile endeavor.

  13. 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

  14. Developing competence based qualification system in the nuclear energy sector

    International Nuclear Information System (INIS)

    Ceclan, Mihail

    2016-01-01

    The Institute for Energy and Transport of the Joint Research Centre, European Commission, developed a strategy and road map for ECVET implementation. The JRC road map for European Credit System for Vocational Education and Training (ECVET) implementation has reached the stage of Competence-Based Qualification System development. The Competence-Based Qualification System can help bridge the gap between Human Resources demand and supply in the nuclear market by structuring qualifications in small independent parts. This very specific ECVET feature of a qualification, facilitates the process of competences accumulation and the lifelong learning, mobility and flexible learning pathways. New developments are presented about the Competence-Based Qualification System development for the nuclear energy sector.

  15. Developing competence based qualification system in the nuclear energy sector

    Energy Technology Data Exchange (ETDEWEB)

    Ceclan, Mihail [European Commission, Petten (Netherlands). Inst. for Energy and Transport

    2016-04-15

    The Institute for Energy and Transport of the Joint Research Centre, European Commission, developed a strategy and road map for ECVET implementation. The JRC road map for European Credit System for Vocational Education and Training (ECVET) implementation has reached the stage of Competence-Based Qualification System development. The Competence-Based Qualification System can help bridge the gap between Human Resources demand and supply in the nuclear market by structuring qualifications in small independent parts. This very specific ECVET feature of a qualification, facilitates the process of competences accumulation and the lifelong learning, mobility and flexible learning pathways. New developments are presented about the Competence-Based Qualification System development for the nuclear energy sector.

  16. Seismic qualification of PWR plant auxiliary feedwater systems

    International Nuclear Information System (INIS)

    Lu, S.C.; Tsai, N.C.

    1983-08-01

    The NRC Standard Review Plan specifies that the auxiliary feedwater (AFW) system of a pressurized water reactor (PWR) is a safeguard system that functions in the event of a Safe Shutdown Earthquake (SSE) to remove the decay heat via the steam generator. Only recently licensed PWR plants have an AFW system designed to the current Standard Review Plan specifications. The NRC devised the Multiplant Action Plan C-14 in order to make a survey of the seismic capability of the AFW systems of operating PWR plants. The purpose of this survey is to enable the NRC to make decisions regarding the need of requiring the licensees to upgrade the AFW systems to an SSE level of seismic capability. To implement the first phase of the C-14 plan, the NRC issued a Generic Letter (GL) 81-14 to all operating PWR licensees requesting information on the seismic capability of their AFW systems. This report summarizes Lawrence Livermore National Laboratory's efforts to assist the NRC in evaluating the status of seismic qualification of the AFW systems in 40 PWR plants, by reviewing the licensees' responses to GL 81-14

  17. Skill qualifications in pediatric minimally invasive surgery.

    Science.gov (United States)

    Iwanaka, Tadashi; Morikawa, Yasuhide; Yamataka, Atsuyuki; Nio, Masaki; Segawa, Osamu; Kawashima, Hiroshi; Sato, Masahito; Terakura, Hirotsugu; Take, Hiroshi; Hirose, Ryuichiro; Yagi, Makoto

    2011-07-01

    In 2006, The Japanese Society of Pediatric Endoscopic Surgeons devised a plan to develop a pediatric endoscopic surgical skill qualification (ESSQ) system. This system is controlled by The Japan Society for Endoscopic Surgery. The standard requirement for skills qualification is the ability of each applicant to complete common types of laparoscopic surgery. The main goal of the system is to decrease complications of laparoscopic surgery by evaluating the surgical skills of each applicant and subsequently certify surgeons with adequate skills to perform laparoscopic operations safely. A committee of pediatric ESSQ created a checklist to assess the applicant's laparoscopic surgical skills. Skills are assessed in a double-blinded fashion by evaluating an unedited video recording of a fundoplication for pediatric gastroesophageal reflux disease. The initial pediatric ESSQ system was started in 2008. In 2008 and 2009, respectively, 9 out of 17 (53%) and 6 out of 12 (50%) applicants were certified as expert pediatric laparoscopic surgeons. Our ultimate goal is to provide safe and appropriate pediatric minimally invasive procedures and to avoid severe complications. To prove the predictive validity of this system, a survey of the outcomes of operations performed by certified pediatric surgeons is required.

  18. MTR fuel plate qualification in OSIRIS reactor

    International Nuclear Information System (INIS)

    Sacristan, P.; Boulcourt, P.; Naury, S.; Marchard, L.; Carcreff, H.; Noirot, J.

    2005-01-01

    Qualification of new MTR fuel needs the irradiation in research reactors under representative neutronic, heat flux and thermohydraulic conditions. The experiments are performed in France in the OSIRIS reactor by irradiating MTR full size fuel plates in the IRIS device located in the reactor core. The fuel plates are easily removed from the device during the shutdown of the reactor for performing thickness measurements along the plates by means of a swelling measurement device. Beside the calculation capabilities, the experimental platform includes: the ISIS neutron mock-up for the measurement of neutron flux distribution along the plates; the γ spectrometry for the purpose of measuring the activities of the radionuclides representative of the power and the burnup and to compare with the neutronic calculation. Owing to the experience feedback, a good agreement is observed between calculation and measurement; destructive post irradiation examinations in the LECA facility (Cadarache). New irradiations with the IRIS device and at higher heat flux are under preparation for qualification of MTR fuels. (author)

  19. Biological Water Quality Criteria

    Science.gov (United States)

    Page contains links to Technical Documents pertaining to Biological Water Quality Criteria, including, technical assistance documents for states, tribes and territories, program overviews, and case studies.

  20. 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.

  1. A system for personnel qualification of non-destructive testing procedures from testing and and qualification system in Sweden

    International Nuclear Information System (INIS)

    Kuna, M.; Kubis, S.; Plasek, J.

    1999-01-01

    The method for qualification of non-destructive testing personnel carrying out inspections by means of ultrasonic and eddy-current tests to inspect cladding in BWR reactor pressure vessel and core shroud lid. Development of procedures tests with real artificial cracks, blind tests. Evaluation of results by the Swedish Qualification Commission. Performance of the tests at Oskarshamn-1

  2. Regulatory Guide 1.131: Qualification tests of electric cables, field splices, and connections for light-water-cooled nuclear power plants

    International Nuclear Information System (INIS)

    Anon.

    1992-01-01

    Criterion III, ''Design Control,'' of Appendix B, ''Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plant,'' to 10 CFR Part 50, ''Licensing of Production and Utilization Facilities,'' requires that, where a test program is used to verify the adequacy of a specific design feature, it include suitable qualification testing of a prototype unit under the most adverse design conditions. This regulatory guide describes a method acceptable to the NRC staff for complying with the Commission's regulations with regard to qualification testing of electric cables, field splices, and connections for service in light-water-cooled nuclear power plants to ensure that the cables, field splices, and connections can perform their safety-related functions. The fire test provisions of this guide do not apply to qualification for an installed configuration

  3. 78 FR 76590 - Physical Qualification of Drivers; Standards; Changes to Vision Exemption Program Criteria

    Science.gov (United States)

    2013-12-18

    ...) hold a valid license; (2) are at least 21 years old; and (3) have 3 years of intrastate CMV driving... eliminate the driving experience criterion. The basis for this change is derived from the Medical Exemption... CFR 391.41(b). Adequate visual function is necessary for safe driving. The current vision standard...

  4. 44 CFR 63.14 - Criteria for State qualification to perform imminent collapse certifications.

    Science.gov (United States)

    2010-10-01

    ... base of mean annual erosion rates for all reaches of coastal shorelines subject to erosion in the State... must be administering a coastal zone management program which includes the following components, as a... seaward of an adopted erosion setback. Such setback must be based in whole or in part on some multiple of...

  5. Qualification method for a 1 MGy-tolerant front-end chip designed in 65 nm CMOS for the read-out of remotely operated sensors and actuators during maintenance in ITER

    Energy Technology Data Exchange (ETDEWEB)

    Verbeeck, Jens, E-mail: jens.verbeeck@esat.kuleuven.be [KU Leuven (KUL), Div. LRD-MAGyICS, Kasteelpark Arenberg 10, 3001 Heverlee (Belgium); Cao, Ying [KU Leuven (KUL), Div. LRD-MAGyICS, Kasteelpark Arenberg 10, 3001 Heverlee (Belgium); Van Uffelen, Marco; Casellas, Laura Mont; Damiani, Carlo; Morales, Emilio Ruiz; Santana, Roberto Ranz [Fusion for Energy (F4E), c/Josep, no. 2, Torres Diagonal Litoral, Ed. B3, 08019 Barcelona (Spain); Meek, Richard; Haist, Bernhard [Oxford Technologies Ltd. (OTL), 7 Nuffield Way, Abingdon OX14 1RL (United Kingdom); Hamilton, David [ITER Organisation (IO), Route de Vinon-sur-Verdon, CS 90 046, 13067 St. Paul les Durance Cedex (France); Steyaert, Michiel [KU Leuven, ESAT-MICAS, Kasteelpark Arenberg 10, 3001 Heverlee (Belgium); Leroux, Paul [KU Leuven, ESAT-MICAS, Kasteelpark Arenberg 10, 3001 Heverlee (Belgium); KU Leuven, ESAT, Advanced Integrated Sensing Lab (AdvISe), Kleinhoefstraat 4, 2440 Geel (Belgium)

    2015-10-15

    This paper describes the radiation qualification procedure for a 1 MGy-tolerant Application Specific Integrated Circuit (ASIC) developed in 65 nm CMOS technology. The chip is intended for the read-out of electrical signals of sensors and actuators during maintenance in ITER. First the general working principle of the ASIC is shown. The developed IC allows to read-out, condition and digitize multiple low bandwidth (<10 kHz) sensors. In addition the IC is able to multiplex the digitized sensor signals. To comply with ITER-relevant constraints an adapted radiation qualification procedure has been proposed. The radiation-qualification procedure describes the test criteria and test conditions of the developed ASICs, which are also compared with COTS alternatives, to meet the stringent qualification procedures for electronics exposed to radiation in ITER.

  6. Repository operational criteria analysis

    International Nuclear Information System (INIS)

    Hageman, J.P.; Chowdhury, A.H.

    1992-08-01

    The objective of the ''Repository Operational Criteria (ROC) Feasibility Studies'' (or ROC task) was to conduct comprehensive and integrated analyses of repository design, construction, and operations criteria in 10 CFR Part 60 regulations, considering the interfaces and impacts of any potential changes to those regulations. The study addresses regulatory criteria related to the preclosure aspects of the geologic repository. The study task developed regulatory concepts or potential repository operational criteria (PROC) based on analysis of a repository's safety functions and other regulations for similar facilities. These regulatory concepts or PROC were used as a basis to assess the sufficiency and adequacy of the current criteria in 10 CFR Part 60. Where the regulatory concepts were same as current operational criteria, these criteria were referenced. The operations criteria referenced or the PROC developed are given in this report. Detailed analyses used to develop the regulatory concepts and any necessary PROC for those regulations that may require a minor change are also presented. The results of the ROC task showed a need for further analysis and possible major rule change related to the design bases of a geologic repository operations area, siting, and radiological emergency planning

  7. CCS site characterisation criteria

    Energy Technology Data Exchange (ETDEWEB)

    Bachu, S.; Hawkes, C.; Lawton, D.; Pooladi-Darvish, M.; Perkins, E.

    2009-12-15

    IEA GHG recently commissioned the Alberta Research Counil in Canada to conduct a review of storage site selection criteria and site characterisation methods in order to produce a synthesis report. This report reviews the literature on the subject on the site seleciton and characterisation since the publication of the IPCC Special Report on CCS, and provides a synthesis and classification of criteria. 161 refs.

  8. Green Supplier Selection Criteria

    DEFF Research Database (Denmark)

    Nielsen, Izabela Ewa; Banaeian, Narges; Golinska, Paulina

    2014-01-01

    Green supplier selection (GSS) criteria arise from an organization inclination to respond to any existing trends in environmental issues related to business management and processes, so GSS is integrating environmental thinking into conventional supplier selection. This research is designed...... to determine prevalent general and environmental supplier selection criteria and develop a framework which can help decision makers to determine and prioritize suitable green supplier selection criteria (general and environmental). In this research we considered several parameters (evaluation objectives......) to establish suitable criteria for GSS such as their production type, requirements, policy and objectives instead of applying common criteria. At first a comprehensive and deep review on prevalent and green supplier selection literatures performed. Then several evaluation objectives defined to assess the green...

  9. Plutonium storage criteria

    Energy Technology Data Exchange (ETDEWEB)

    Chung, D. [Scientech, Inc., Germantown, MD (United States); Ascanio, X. [Dept. of Energy, Germantown, MD (United States)

    1996-05-01

    The Department of Energy has issued a technical standard for long-term (>50 years) storage and will soon issue a criteria document for interim (<20 years) storage of plutonium materials. The long-term technical standard, {open_quotes}Criteria for Safe Storage of Plutonium Metals and Oxides,{close_quotes} addresses the requirements for storing metals and oxides with greater than 50 wt % plutonium. It calls for a standardized package that meets both off-site transportation requirements, as well as remote handling requirements from future storage facilities. The interim criteria document, {open_quotes}Criteria for Interim Safe Storage of Plutonium-Bearing Solid Materials{close_quotes}, addresses requirements for storing materials with less than 50 wt% plutonium. The interim criteria document assumes the materials will be stored on existing sites, and existing facilities and equipment will be used for repackaging to improve the margin of safety.

  10. Chapter 9. Personnel qualification and training

    International Nuclear Information System (INIS)

    2000-01-01

    In 1999 the Nuclear Regulatory Authority of the Slovak Republic (UJD) focused on the overall training system and on developing programmes for individual categories for NPP V-1 Bohunice, NPP V-2 Bohunice, NPP Mochovce and SE-VYZ. The fundamental theoretical and periodical training for both Bohunice and Mochovce NPPs personnel, simulator training for NPP Bohunice, and periodical simulator training for Bohunice personnel is carried out by the VUJE Training center in Trnava, whereas the simulator training and periodical training for NPP Mochovce is carried at Mochovce plant. Based on a successful passing of examination before the examining committee, UJD issues, a certificate on special professional skills of selected staff of nuclear installations for specific activity for the given type of nuclear installation and for the following positions: (a)Shift manager for scientific start up with the right of manipulation; (b) Shift supervisor; (c) Unit supervisor; (d) Primary circuit operator; (e) Secondary circuit operator; (f) Reactor physicist; (g) Shift manager for scientific start up without the right of manipulation. Examination of selected personnel is described. Last year the examining committee held twelve session for oral theoretical examination. The number of licenses issued in 1999 and the total number of valid licenses is given.Conclusions from inspections carried out by UJD and inspections and tests carried out by the NPP operators in 1999, as well as results from operation and start up of nuclear units confirm that the standard of professional skills of the staff at nuclear installations a high standard of operational safety is being achieved on a permanent basis. Increasing the qualification of UJD staff was done in a form of training and courses scheduled in the plan of training for the staff for 1999. These training, composed of specialized qualification study, functional study, as well as study aimed at maintaining qualification. Training courses organized

  11. The Big-Five Personality Traits, Maternal Smoking during Pregnancy, and Educational Qualifications as Predictors of Tobacco Use in a Nationally Representative Sample.

    Directory of Open Access Journals (Sweden)

    Helen Cheng

    Full Text Available To investigate the associations between the Big-Five personality traits, parental social class, maternal smoking status during pregnancy, childhood cognitive ability, education and occupation, and tobacco use in a longitudinal birth cohort study.17,415 babies born in Great Britain in 1958 and followed up at 11, 33, and 50 years of age. Lifelong tobacco use status (ever/never and current tobacco use status (yes/no at age 50 years were the outcome measures respectively.Logistic regression analyses showed that among the 5,840 participants with complete data, whilst maternal smoking status, educational qualifications, and all the big-5 personality traits were significant predictors of adult lifelong tobacco use; educational qualifications, own occupational levels, traits Extraversion, Conscientiousness, and Openness were significant predictors of current smoking status. In lifelong measure men tended to have a greater rate of tobacco use than women (52.1% in men and 49.2% in women. However, the sex effect on lifelong tobacco use ceased to be significant once a set of socio-economic and psychological variables in childhood and adulthood were taken into account.Educational qualifications and the Big-Five personality traits were significantly associated with both current and lifelong tobacco use status.

  12. The Big-Five Personality Traits, Maternal Smoking during Pregnancy, and Educational Qualifications as Predictors of Tobacco Use in a Nationally Representative Sample.

    Science.gov (United States)

    Cheng, Helen; Furnham, Adrian

    2016-01-01

    To investigate the associations between the Big-Five personality traits, parental social class, maternal smoking status during pregnancy, childhood cognitive ability, education and occupation, and tobacco use in a longitudinal birth cohort study. 17,415 babies born in Great Britain in 1958 and followed up at 11, 33, and 50 years of age. Lifelong tobacco use status (ever/never) and current tobacco use status (yes/no) at age 50 years were the outcome measures respectively. Logistic regression analyses showed that among the 5,840 participants with complete data, whilst maternal smoking status, educational qualifications, and all the big-5 personality traits were significant predictors of adult lifelong tobacco use; educational qualifications, own occupational levels, traits Extraversion, Conscientiousness, and Openness were significant predictors of current smoking status. In lifelong measure men tended to have a greater rate of tobacco use than women (52.1% in men and 49.2% in women). However, the sex effect on lifelong tobacco use ceased to be significant once a set of socio-economic and psychological variables in childhood and adulthood were taken into account. Educational qualifications and the Big-Five personality traits were significantly associated with both current and lifelong tobacco use status.

  13. 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

  14. Revision of the qualification framework at the Technical University of Denmark Part 2

    DEFF Research Database (Denmark)

    Henneberg, Kaj-Åge; Kuhn, Luise Theil; Jungersen, Gregers

    2017-01-01

    Using a revised Qualification Framework (QF) with four main categories: -to know, - to be, -to interact, and -to do, this paper demonstrates how to use the elements of the QF to construct Programme-Qualification Matrices. A general Programme- Qualification Matrix defines the qualifications and th...

  15. Federal Rule CLI 80-21: Commission Memorandum and Order of May 23, 1980 on environmental qualification

    International Nuclear Information System (INIS)

    Ahearne, J.F.; Gilinsky, V.; Kennedy, R.T.; Hendrie, J.M.; Bradford, P.A.

    1993-01-01

    Upon consideration of a petition by the Union of Concerned Scientists for reconsideration of CLI-78-6, 7 NRC 400 (1978), which denied petitioner's requests for emergency relief concerning fire protection for electrical cables and environmental qualification of electrical components the Commission affirms its earlier decision with certain revisions and clarifications. A fundamental principle of NRC regulation of nuclear power reactors is that safety systems must perform their intended functions in spite of the environment which may result from postulated accidents. Confirmation that these systems will remain functional under postulated accident conditions constitutes environmental qualification, the legal requirements for which are found in General Design Criteria 1 and 4 of Appendix A, Part 50; Criterion III of Appendix B, Part 50; and 10 CFR 50.55a(h)

  16. 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

  17. INDUSTRIAL RESTRUCTURING AND PROFESSIONAL QUALIFICATION REQUIREMENTS

    Directory of Open Access Journals (Sweden)

    João Amato Neto

    2014-09-01

    Full Text Available Among the most complex subjects that affect modern society in this early millennium, the problem of relationships between the educational patterns and the work organization seems to be one of the most important and full of uncertainties. Specially, this problem acquires greater relevance when one thinks of the impacts of the techno-scientific revolution in the work world, as well as in the educational system. In this sense, the present work researches some elements regarding the new educational patterns and qualification requirements in face of the new industrial paradigm and discusses the transformations accomplished by the techno-scientific revolution and its implications on the new lean and flexible production paradigm and on the (reorganization of work in the modern industry. The methodological approach is based on a bibliographic revision with a quantitative approach.

  18. Response Variability in Commercial MOSFET SEE Qualification

    International Nuclear Information System (INIS)

    George, J. S.; Clymer, D. A.; Turflinger, T. L.; Mason, L. W.; Stone, S.

    2016-01-01

    Single-event effects (SEE) evaluation of five different part types of next generation, commercial trench MOSFETs indicates large part-to-part variation in determining a safe operating area (SOA) for drain-source voltage (V_D_S) following a test campaign that exposed >50 samples per part type to heavy ions. These results suggest a determination of a SOA using small sample sizes may fail to capture the full extent of the part-to-part variability. An example method is discussed for establishing a Safe Operating Area using a one-sided statistical tolerance limit based on the number of test samples. Finally, burn-in is shown to be a critical factor in reducing part-to-part variation in part response. Implications for radiation qualification requirements are also explored.

  19. The COPD Biomarker Qualification Consortium (CBQC)

    DEFF Research Database (Denmark)

    Casaburi, Richard; Celli, Bartolome; Crapo, James

    2013-01-01

    Abstract Knowledge about the pathogenesis and pathophysiology of chronic obstructive pulmonary disease (COPD) has advanced dramatically over the last 30 years. Unfortunately, this has had little impact in terms of new treatments. Over the same time frame, only one new class of medication for COPD......, and no interested party has been in a position to undertake such a process. In order to facilitate the development of novel tools to assess new treatments, the Food and Drug Administration, in collaboration with the COPD Foundation, the National Heart Lung and Blood Institute and scientists from the pharmaceutical...... industry and academia conducted a workshop to survey the available information that could contribute to new tools. Based on this, a collaborative project, the COPD Biomarkers Qualification Consortium, was initiated. The Consortium in now actively preparing integrated data sets from existing resources...

  20. Qualification of quality testing personnel, in particular the training offered

    International Nuclear Information System (INIS)

    Knoedler, D.

    1980-01-01

    Personnel qualification is one of the most important tasks of quality assurance. The qualification is reached by professional education, by experience made on the job and by additional external and company-internal training. A determination of qualification requirements should cover only the general principles. Especially this should be considered specifying the requirements for theoretical knowledge and for examinations since the factor of relevant experience is difficult to be estimated by third parties. Equal principles apply for the personnel of the manufacturer, of the main contractor, of the utility and of the auhtorized inspectors' organizations. The detailed guidelines should be part of the internal QA-systems of the organizations involved. (orig.) [de

  1. European methodology for qualification of NDT as developed by ENIQ

    International Nuclear Information System (INIS)

    Champigny, F.; Sandberg, U.; Engl, G.; Crutzen, S.; Lemaitre, P.

    1997-01-01

    The European Network for Inspection Qualification (ENIQ) groups the major part of the nuclear power plant operators in the European Union (and Switzerland). The main objective of ENIQ is to co-ordinate and manage at European level expertise and resources for the qualification of NDE inspection systems, primarily for nuclear components. In the framework of ENIQ the European methodology for qualification of NDT has been developed. In this paper the main principles of the European methodology are given besides the main activities and organisation of ENIQ. (orig.)

  2. [Evaluation of the status of patients with severe infection, criteria for intensive care unit admittance. Spanish Society for Infectious Diseases and Clinical Microbiology. Spanish Society of Intensive and Critical Medicine and Coronary Units].

    Science.gov (United States)

    Olaechea, Pedro M; Alvarez-Lerma, Francisco; Sánchez, Miguel; Torres, Antonio; Palomar, Mercedes; Fernández, Pedro; Miró, José M; Cisneros, José Miguel; Torres, Manuel

    2009-06-01

    Recent studies have shown that early attention in patients with serious infections is associated with a better outcome. Assistance in intensive care units (ICU) can effectively provide this attention; hence patients should be admitted to the ICU as soon as possible, before clinical deterioration becomes irreversible. The objective of this article is to compile the recommendations for evaluating disease severity in patients with infections and describe the criteria for ICU admission, updating the criteria published 10 years ago. A literature review was carried out, compiling the opinions of experts from the Sociedad Española de Enfermedades Infecciosas y Microbiología Clínica (SEIMC, Spanish Society for Infectious Diseases and Clinical Microbiology) and the Sociedad Española de Medicina Intensiva, Crítica y Unidades Coronarias (SEMICYUC, Spanish Society for Intensive Medicine, Critical Care and Coronary Units) as well as the working groups for infections in critically ill patients (GEIPC-SEIMC and GTEI-SEMICYUC). We describe the specific recommendations for ICU admission related to the most common infections affecting patients, who will potentially benefit from critical care. Assessment of the severity of the patient's condition to enable early intensive care is stressed.

  3. NPP Krsko full scope simulator verification and qualification

    International Nuclear Information System (INIS)

    Krajnc, B.; Glaser, B.; Novsak, M.; Spiler, J.

    1998-01-01

    NPP Krsko (NEK) will, as a part of the Modernization plan, obtain also Krsko Full Scope Simulator (KFSS). Contract has been awarded to CAE Electronics for the design, construction and integration. KFSS will support in real time, the training for the complete range of operation, which can be performed from the main control room and some selected plant areas (remote shutdown panels, etc). Based on the lessons learned on development of NPP Krsko Basic Principle Simulator we decided for active approach. That means that NPP Krsko personnel will be heavily involved into all phases of KFSS development and testing. Since NPP Krsko is going to replace the existing steam generators, raise the nominal power and perform necessary modifications to support the power uprate, it was decided that the development of the KFSS will be conducted in two steps: 1. Development of the models as well as all the hardware interface in the MCR for the existing plant Cycle 15 and then, 2. Models and hardware will be modified, added or replaced as needed to take into account the steam generator replacement and plant uprate projects. In spite of the fact that the simulator will be used for the training of the plant operators for the uprated conditions and with new steam generators, the upper described approach was selected since we want to be sure that the models will at the beginning adequately simulate the existing plant. For the existing conditions we have available reference data for different plant conditions, as well as data for different plant transients. By verifying that simulator will be able adequately simulate the existing conditions the level of confidence for the uprated simulator will be much higher. This is of special importance since it will support initial training for modernized plant conditions. In this paper the plan for verification and qualification of KFSS as well as the amount of the work needed on NPP Krsko side to develop the test acceptance criteria will be presented.(author)

  4. 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

  5. Multimodal freight investment criteria.

    Science.gov (United States)

    2010-07-01

    Literature was reviewed on multi-modal investment criteria for freight projects, examining measures and techniques for quantifying project benefits and costs, as well as ways to describe the economic importance of freight transportation. : A limited ...

  6. Water Quality Criteria

    Science.gov (United States)

    EPA develops water quality criteria based on the latest scientific knowledge to protect human health and aquatic life. This information serves as guidance to states and tribes in adopting water quality standards.

  7. Aquatic Life Criteria - Ammonia

    Science.gov (United States)

    Documents related to EPA's final 2013 Aquatic Life Ambient Water Quality Criteria for Ammonia (Freshwater). These documents pertain to the safe levels of Ammonia in water that should protect to the majority of species.

  8. Aquatic Life Criteria - Copper

    Science.gov (United States)

    Documents pertain to Aquatic Life Ambient Water Quality criteria for Copper (2007 Freshwater, 2016 Estuarine/marine). These documents contain the safe levels of Copper in water that should protect to the majority of species.

  9. Integrated Criteria Document Chromium

    NARCIS (Netherlands)

    Slooff W; Cleven RFMJ; Janus JA; van der Poel P; van Beelen P; Boumans LJM; Canton JH; Eerens HC; Krajnc EI; de Leeuw FAAM; Matthijsen AJCM; van de Meent D; van der Meulen A; Mohn GR; Wijland GC; de Bruijn PJ; van Keulen A; Verburgh JJ; van der Woerd KF

    1990-01-01

    Betreft de engelse versie van rapport 758701001
    Bij dit rapport behoort een appendix onder hetzelfde nummer getiteld: "Integrated Criteria Document Chromium: Effects" Auteurs: Janus JA; Krajnc EI
    (appendix: see 710401002A)

  10. 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

  11. Dual Criteria Decisions

    DEFF Research Database (Denmark)

    Andersen, Steffen; Harrison, Glenn W.; Lau, Morten Igel

    2014-01-01

    The most popular models of decision making use a single criterion to evaluate projects or lotteries. However, decision makers may actually consider multiple criteria when evaluating projects. We consider a dual criteria model from psychology. This model integrates the familiar tradeoffs between...... to the clear role that income thresholds play in such decision making, but does not rule out a role for tradeoffs between risk and utility or probability weighting....

  12. AGR-2 Data Qualification Report for ATR Cycles 147A, 148A, 148B, and 149A

    Energy Technology Data Exchange (ETDEWEB)

    Michael L. Abbott; Keith A. Daum

    2011-08-01

    This report presents the data qualification status of fuel irradiation data from the first four reactor cycles (147A, 148A, 148B, and 149A) of the on-going second Advanced Gas Reactor (AGR-2) experiment as recorded in the NGNP Data Management and Analysis System (NDMAS). This includes data received by NDMAS from the period June 22, 2010 through May 21, 2011. AGR-2 is the second in a series of eight planned irradiation experiments for the AGR Fuel Development and Qualification Program, which supports development of the very high temperature gas-cooled reactor (VHTR) under the Next Generation Nuclear Plant (NGNP) Project. Irradiation of the AGR-2 test train is being performed at the Advanced Test Reactor (ATR) at the Idaho National Laboratory (INL) and is planned for 600 effective full power days (approximately 2.75 calendar years) (PLN-3798). The experiment is intended to demonstrate the performance of UCO (uranium oxycarbide) and UO2 (uranium dioxide) fuel produced in a large coater. Data qualification status of the AGR-1 experiment was reported in INL/EXT-10-17943 (Abbott et al. 2010).

  13. AGR-2 Data Qualification Report for ATR Cycles 147A, 148A, 148B, and 149A

    International Nuclear Information System (INIS)

    Abbott, Michael L.; Daum, Keith A.

    2011-01-01

    This report presents the data qualification status of fuel irradiation data from the first four reactor cycles (147A, 148A, 148B, and 149A) of the on-going second Advanced Gas Reactor (AGR-2) experiment as recorded in the NGNP Data Management and Analysis System (NDMAS). This includes data received by NDMAS from the period June 22, 2010 through May 21, 2011. AGR-2 is the second in a series of eight planned irradiation experiments for the AGR Fuel Development and Qualification Program, which supports development of the very high temperature gas-cooled reactor (VHTR) under the Next Generation Nuclear Plant (NGNP) Project. Irradiation of the AGR-2 test train is being performed at the Advanced Test Reactor (ATR) at the Idaho National Laboratory (INL) and is planned for 600 effective full power days (approximately 2.75 calendar years) (PLN-3798). The experiment is intended to demonstrate the performance of UCO (uranium oxycarbide) and UO2 (uranium dioxide) fuel produced in a large coater. Data qualification status of the AGR-1 experiment was reported in INL/EXT-10-17943 (Abbott et al. 2010).

  14. Rating of environmental criteria

    Energy Technology Data Exchange (ETDEWEB)

    Glueck, K; Krasser, G

    1980-01-01

    After a general theoretical discussion on the question of rating within a framework of cost-benefit studies, first trials as to the quantification and standardisation of twelve selected environmental criteria by means of an indicator system are worked out and compiled. The selection includes the criteria exhaust gas, dust, micro climate, water pollution, water regime, land requirement, vibrations, traffic noise, landscape scene, urban scene, effect of separation and safety risks. An insight is given of the rating practice using an evaluation of the available literature, of a household interview and of an interview of experts. The interviewing of 156 experts as to their rating conception of ten criteria in the second round has provided contributions to the general problem of the evaluation estimate based on multi criteria analysis as well as differentiation of the twelve or ten environmental criteria. The following criteria ratings given by the experts and which are averaged and smoothed are: traffic noise 20,0% +- 8,5; air pollution 15,0% +- 7,0; safety risk 13,0% +- 7,0; soil and water pollution 8,5% +- 5,0; landscape scene 8,0% +- 4,5; urban scene 8,0% +- 4,5; water regime 6,5% +- 3,5 and vibrations 4,5% +- 2,5.

  15. The SQUG program for resolution of USI A-46 - status and implementation plans

    International Nuclear Information System (INIS)

    Schmidt, W.R.; Kassawara, R.P.; Yanev, P.

    1990-01-01

    In response to U.S. (NRC), Unresolved Safety Issue (USI) A-46, 'Seismic Qualification of Equipment and Operating Nuclear Power Plants', the Seismic Qualification Utility Group (SQUG), with the support of EPRI, developed a comprehensive program to verify the seismic adequacy of equipment in operating nuclear power plants. The primary thrust of the program has been the development of procedures, criteria, and data to apply actual experience on the performance of equipment during earthquakes to the verification of seismic ruggedness of similar equipment in nuclear plants. While the use of such experience data continues to play a primary part in the SQUG program for resolution of USI A-46, the overall SQUG program includes a number of other significant elements which, taken together, provide a comprehensive approach for verification of the seismic adequacy of equipment in nuclear plants. These elements of the SQUG program include the assimilation and use of seismic shake table data in a generic way; the development of simplified analytical tools and criteria for evaluation of equipment anchorage, tanks, heat exchangers and cable trays; and the development of procedures for identifying and evaluating electrical relays, which are essential to plant shutdown in response to an earthquake. Procedures and data bases for performing and documenting the various seismic evaluations and plant walkdowns, and a program for training the large number of engineers who will be required to implement the SQUG methodology, have also been developed. This paper describes the main elements of the SQUG program for resolution of USI A-46 and provides a status report on the plans for their implementation in SQUG member plants. (orig./HP)

  16. An investigation of individual functionality football referees qualifications

    Directory of Open Access Journals (Sweden)

    S.M. Berezka

    2014-12-01

    Full Text Available Purpose: determine the level of individual functionality referees qualifications. Objective of the study was to determine the physiological parameters characterizing the functionality of football referees qualifications. Material : mainly experiment involved 29 highly qualified referees aged 21-45 years. In the main experiment participated 29 referees and 40 assistant referees (n = 69 Ukrainian Premier League. Results: found that the means and methods that use Ukrainian football referee high qualification in the special physical training for a competition, are not effective enough. Consequence of poorly planned training process is to increase the number of wrong decisions of the referees during the match associated with poor motor activity. Conclusions: data obtained in the course of educational research confirmed our theory about the necessity of individualization process special physical training qualifications of referees, which would entail increasing the functional and motor abilities of the referees, and as a consequence of better and successful completion of the work.

  17. 75 FR 77947 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2010-12-14

    ... safety mandated by the statutes. Qualifications of Applicants Richard B. Angus Mr. Angus, age 55, has had... monitoring; has stable control of his diabetes using insulin; and is able to drive a CMV safely. Mr. Angus...

  18. 48 CFR 6301.2 - Qualifications of members.

    Science.gov (United States)

    2010-10-01

    ... contract law. ... CONTRACT APPEALS BOARD OF CONTRACT APPEALS 6301.2 Qualifications of members. Each member of the Board must... administrative law judges appointed pursuant to section 3105 of title 5 of the United States Code, with the...

  19. Inspection procedure and essential parameters in NDT qualification

    International Nuclear Information System (INIS)

    Sarkimo, M.

    2000-06-01

    The objective of the inspection qualification is to ensure that applied non-destructive methods (NDT) have the required performance. The approach of the qualification process is systematic and carefully documented and therefore some new requirements can be seen concerning the composition of the documentation. There are also new document types, that only application of the inspection qualification requires. The most important of these is the technical justification, that includes the documented evidences concerning the performance of the inspection system. This publication includes two reports: 'Compilation of the inspection procedure' and 'Essential/influential parameters in NDT qualification'. The former of these discusses the issues to be considered in an inspection procedure especially from the point of view of the mechanised ultrasonic testing. The later report explains the parameters formulated to analyse in the technical justification all aspects of the inspection application. (orig.)

  20. Virtual design and qualification of IC backend structures

    NARCIS (Netherlands)

    Silfhout, van R.B.R.; Sluis, van der O.; Driel, van W.D.; Janssen, J.H.J.; Zhang, G.Q.

    2006-01-01

    For Integrated Circuit (IC) wafer backend development, process developers have to design robust backend structures that guarantee both functionality and reliability during waferfab processes, packaging, qualification tests and lifetime. Figure 1 shows a simplified diagram for the design (and

  1. Navigating the National Qualifications Framework (NQF): The role of ...

    African Journals Online (AJOL)

    Navigating the National Qualifications Framework (NQF): The role of career guidance. ... opportunities (including, but not confined to, those within higher education). ... It argues that the time is ripe for a high-level national career development ...

  2. Relating Teaching Qualifications and Basic Need Satisfaction in Medical Teaching

    NARCIS (Netherlands)

    Engbers, R.; Fluit, C.R.; Bolhuis, S.; Sluiter, R.; Stuyt, P.M.; Laan, R.F.; Wade, S.L.

    2017-01-01

    INTRODUCTION: Teaching Qualifications (TQs) have been implemented in University Medical Centers, but their relation to teachers’ motivation for medical teaching is unknown. Because teacher motivation influences important outcomes, it is crucial to study how TQs are related to promoting teacher

  3. Present stage evaluation of Furnas calculus methodology qualification

    International Nuclear Information System (INIS)

    1987-07-01

    This technical note is about the present stage evaluation of FURNAS Calculus Methodology Qualification related to reload licensing process and licensing support of operation questions of Angra 1 NPP concerning transient and Core ThermalHydraulic areas. (Author) [pt

  4. 78 FR 76399 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2013-12-17

    ...-2013-0185] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor... its decision to exempt 37 individuals from its rule prohibiting persons with insulin-treated diabetes... receipt of Federal diabetes exemption applications from [[Page 76400

  5. 76 FR 9854 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2011-02-22

    ...-0011] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor Carrier Safety Administration (FMCSA). ACTION: Notice of applications for exemption from the diabetes mellitus... exemption from the prohibition against persons with insulin-treated diabetes mellitus (ITDM) operating...

  6. 78 FR 1923 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2013-01-09

    ...-0350] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor Carrier Safety Administration (FMCSA). ACTION: Notice of applications for exemption from the diabetes mellitus... exemption from the prohibition against persons with insulin-treated diabetes mellitus (ITDM) operating...

  7. 77 FR 3549 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2012-01-24

    ...-0368] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor Carrier Safety Administration (FMCSA), DOT. ACTION: Notice of applications for exemption from the diabetes... individuals for exemption from the prohibition against persons with insulin-treated diabetes mellitus (ITDM...

  8. 77 FR 5873 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2012-02-06

    ...-2011-0326] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor... diabetes mellitus (ITDM) from operating commercial motor vehicles (CMVs) in interstate commerce. The... diabetes exemption applications from fifteen individuals and requested comments from the public (76 FR...

  9. 76 FR 9862 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2011-02-22

    ...-0025] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor Carrier Safety Administration (FMCSA). ACTION: Notice of applications for exemption from the diabetes mellitus... exemption from the prohibition against persons with insulin-treated diabetes mellitus (ITDM) operating...

  10. 78 FR 1927 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2013-01-09

    ...-0351] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor Carrier Safety Administration (FMCSA). ACTION: Notice of applications for exemption from the diabetes mellitus... exemption from the prohibition against persons with insulin-treated diabetes mellitus (ITDM) operating...

  11. 78 FR 63285 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2013-10-23

    ... Mr. Van Gog understands diabetes management and monitoring, has stable control of his diabetes using...-0185] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor Carrier... against persons with insulin- treated diabetes mellitus (ITDM) operating commercial motor vehicles (CMVs...

  12. 76 FR 64165 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2011-10-17

    ...-0277] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor Carrier Safety Administration (FMCSA). ACTION: Notice of applications for exemption from the diabetes mellitus... individuals for exemption from the prohibition against persons with insulin-treated diabetes mellitus (ITDM...

  13. 77 FR 533 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2012-01-05

    ...-0367] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor Carrier Safety Administration (FMCSA). ACTION: Notice of applications for exemption from the diabetes mellitus... for exemption from the prohibition against persons with insulin-treated diabetes mellitus (ITDM...

  14. 78 FR 38439 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2013-06-26

    ...-0020] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor Carrier Safety Administration (FMCSA). ACTION: Notice of applications for exemption from the diabetes mellitus... exemption from the prohibition against persons with insulin-treated diabetes mellitus (ITDM) operating...

  15. 78 FR 14406 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2013-03-05

    ...-0013] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor Carrier Safety Administration (FMCSA), DOT. ACTION: Notice of applications for exemption from the diabetes... individuals for exemption from the prohibition against persons with insulin-treated diabetes mellitus (ITDM...

  16. 76 FR 61140 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2011-10-03

    ...-0194] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor Carrier Safety Administration (FMCSA), DOT. ACTION: Notice of applications for exemption from the diabetes... individuals for exemption from the prohibition against persons with insulin-treated diabetes mellitus (ITDM...

  17. 77 FR 40941 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2012-07-11

    ...-0163] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor Carrier Safety Administration (FMCSA). ACTION: Notice of applications for exemption from the diabetes mellitus... exemption from the prohibition against persons with insulin-treated diabetes mellitus (ITDM) operating...

  18. 77 FR 70530 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2012-11-26

    ...-0348] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor Carrier Safety Administration (FMCSA), DOT. ACTION: Notice of applications for exemption from the diabetes... revision must provide for individual assessment of drivers with diabetes mellitus, and be consistent with...

  19. 77 FR 46149 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2012-08-02

    ...-0164] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor Carrier Safety Administration (FMCSA). ACTION: Notice of applications for exemption from the diabetes mellitus... exemption from the prohibition against persons with insulin-treated diabetes mellitus (ITDM) operating...

  20. 77 FR 64181 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2012-10-18

    ...-0283] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor Carrier Safety Administration (FMCSA). ACTION: Notice of applications for exemption from the diabetes mellitus... exemption from the prohibition against persons with insulin-treated diabetes mellitus (ITDM) operating...

  1. 78 FR 26419 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2013-05-06

    ...-0018] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor Carrier Safety Administration (FMCSA). ACTION: Notice of applications for exemption from the diabetes mellitus... exemption from the prohibition against persons with insulin-treated diabetes mellitus (ITDM) operating...

  2. 77 FR 52384 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2012-08-29

    ...-0218] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor Carrier... from the diabetes mellitus requirement; request for comments. SUMMARY: FMCSA announces receipt of... diabetes mellitus (ITDM) operating commercial motor vehicles (CMVs) in interstate commerce. If granted, the...

  3. 77 FR 56258 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2012-09-12

    ...-0219] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor Carrier Safety Administration (FMCSA). ACTION: Notice of applications for exemption from the diabetes mellitus... exemption from the prohibition against persons with insulin-treated diabetes mellitus (ITDM) operating...

  4. 78 FR 38435 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2013-06-26

    ...-0181] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor Carrier Safety Administration (FMCSA). ACTION: Notice of applications for exemption from the diabetes mellitus... exemption from the prohibition against persons with insulin-treated diabetes mellitus (ITDM) operating...

  5. 76 FR 66120 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2011-10-25

    ...-0278] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor Carrier Safety Administration (FMCSA). ACTION: Notice of applications for exemption from the diabetes mellitus... exemption from the prohibition against persons with insulin-treated diabetes mellitus (ITDM) operating...

  6. 78 FR 20381 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2013-04-04

    ...-0015] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor Carrier Safety Administration (FMCSA). ACTION: Notice of applications for exemption from the diabetes mellitus... exemption from the prohibition against persons with insulin-treated diabetes mellitus (ITDM) operating...

  7. 77 FR 65931 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2012-10-31

    ...-0347] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor Carrier... diabetes mellitus requirement; request for comments. SUMMARY: FMCSA announces receipt of applications from 12 individuals for exemption from the prohibition against persons with insulin-treated diabetes...

  8. 77 FR 10612 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2012-02-22

    ...-0382] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor Carrier Safety Administration (FMCSA). ACTION: Notice of applications for exemption from the diabetes mellitus... exemption from the prohibition against persons with insulin-treated diabetes mellitus (ITDM) operating...

  9. 78 FR 79062 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2013-12-27

    ...-0193] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor Carrier Safety Administration (FMCSA). ACTION: Notice of applications for exemption from the diabetes mellitus... exemption from the prohibition against persons with insulin-treated diabetes mellitus (ITDM) operating...

  10. 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

  11. 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.

  12. 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.)

  13. Testing and qualification of confidence in statistical procedures

    Energy Technology Data Exchange (ETDEWEB)

    Serghiuta, D.; Tholammakkil, J.; Hammouda, N. [Canadian Nuclear Safety Commission (Canada); O' Hagan, A. [Sheffield Univ. (United Kingdom)

    2014-07-01

    This paper discusses a framework for designing artificial test problems, evaluation criteria, and two of the benchmark tests developed under a research project initiated by the Canadian Nuclear Safety Commission to investigate the approaches for qualification of tolerance limit methods and algorithms proposed for application in optimization of CANDU regional/neutron overpower protection trip setpoints for aged conditions. A significant component of this investigation has been the development of a series of benchmark problems of gradually increased complexity, from simple 'theoretical' problems up to complex problems closer to the real application. The first benchmark problem discussed in this paper is a simplified scalar problem which does not involve extremal, maximum or minimum, operations, typically encountered in the real applications. The second benchmark is a high dimensional, but still simple, problem for statistical inference of maximum channel power during normal operation. Bayesian algorithms have been developed for each benchmark problem to provide an independent way of constructing tolerance limits from the same data and allow assessing how well different methods make use of those data and, depending on the type of application, evaluating what the level of 'conservatism' is. The Bayesian method is not, however, used as a reference method, or 'gold' standard, but simply as an independent review method. The approach and the tests developed can be used as a starting point for developing a generic suite (generic in the sense of potentially applying whatever the proposed statistical method) of empirical studies, with clear criteria for passing those tests. Some lessons learned, in particular concerning the need to assure the completeness of the description of the application and the role of completeness of input information, are also discussed. It is concluded that a formal process which includes extended and detailed benchmark

  14. Neutron absorber qualification and acceptance testing from the designer's perspective

    Energy Technology Data Exchange (ETDEWEB)

    Bracey, W. [Transnuclear, Inc, Hawthorne, NY (United States); Chiocca, R. [Cogema Logistics, St. Quentin en Yvelines (France)

    2004-07-01

    Starting in the mid 1990's, the USNRC began to require less than 100% credit for the 10B present in fixed neutron absorbers spent fuel transport packages. The current practice in the US is to use only 75% of the specified 10B in criticality safety calculations unless extensive acceptance testing demonstrates both the presence of the 10B and uniformity of its distribution. In practice, the NRC has accepted no more than 90% credit for 10B in recent years, while other national competent authorities continue to accept 100%. More recently, with the introduction of new neutron absorber materials, particularly aluminum / boron carbide metal matrix composites, the NRC has also expressed expectations for qualification testing, based in large part on Transnuclear's successful application to use a new composite material in the TN-68 storage / transport cask. The difficulty is that adding more boron than is really necessary to a metal has some negative effects on the material, reducing the ductility and the thermal conductivity, and increasing the cost. Excessive testing requirements can have the undesired effect of keeping superior materials out of spent fuel package designs, without a corresponding justification based on public safety. In European countries and especially in France, 100% credit has been accepted up to now with materials controls specified in the Safety Analysis Report (SAR): Manufacturing process approved by qualification testing Materials manufacturing controlled under a Quality Assurance system. During fabrication, acceptance testing directly on products or on representative samples. Acceptance criteria taking into account a statistical uncertainty corresponding to 3{sigma}. The original and current bases for the reduced {sup 10}B credit, the design requirements for neutron absorber materials, and the experience of Transnuclear and Cogema Logistics with neutron absorber testing are examined. Guidelines for qualification and acceptance testing and

  15. On tungsten technologies and qualification for DEMO

    International Nuclear Information System (INIS)

    Laan, J. van der; Hegeman, H.; Wouters, O.; Luzginova, N.; Jonker, B.; Van der Marck, S.; Opschoor, J.; Wang, J.; Dowling, G.; Stuivenga, M.; Carton, E.

    2009-01-01

    Tungsten alloys are considered prime candidates for the in-vessel components directly facing the plasma. For example, in the HEMJ helium cooled divertor design tiles may be operated at temperatures up to 1700 deg. C, supported by a structure partially consisting of tungsten at temperatures from 600 to 1000 deg. C, and connected to a HT steel structure. The tungsten armoured primary wall is operated at 500-900 deg. C. Irradiation doses will be few tens dpa at minimum, but FPR requirements for plants availability will stretch these targets. Recently injection moulding technology was developed for pure tungsten and representative parts were manufactured for ITER monobloc divertors and DEMO HEMJ thimbles. The major advantages for this technology are the efficient use of material feedstock/resources and the intrinsic possibility to produce near-finished product, avoiding machining processes that are costly and may introduce surface defects deteriorating the component in service performance. It is well suited for mass-manufacturing of components as well known in e.g. lighting industries. To further qualify this material technology various specimen types were produced with processing parameters identical to the components, and tested successfully, showing the high potential for implementation in (fusion) devices. Furthermore, the engineering approach can clearly be tailored away from conventional design and manufacturing technologies based on bulk materials. The technology is suitable for shaping of new W-alloys and W-ODS variants as well. Basically this technology allows a particular qualification trajectory. There is no need to produce large batches of material during the material development and optimization stage. For the verification of irradiation behaviour in the specific neutron spectra, there is a further attractive feature to use e.g. isotope tailored powders to adjust to available irradiation facilities like MTR's. In addition the ingrowth of transmutation

  16. Qualification Practices in Nuclear Industry: Steam Generator Eddy Current Probe Qualification

    International Nuclear Information System (INIS)

    Vavrous, M.; Gracin, R.

    2010-01-01

    Through history of nuclear power plant operation, a large number of nuclear power plant forced outages related to tube failures occurred. It resulted with large amount of repair and outage costs, what initiated implementation of regulated practice of periodical tube examination and tube condition monitoring. Purpose of examinations is to detect existing or potential tube degradations that could affect tube integrity and therefore result in forced outages and unwanted costs related to emergency repair activities and loss of ability for electrical power production. With increased examination activities, additional information about steam generator tube condition became available and additional methods for ensuring tube integrity became available. As the number of examination solutions increased, need for validation and assessment of examination methods occurred. For that purpose, a large number of standards and guidelines with its requirements were implemented in nuclear industry regulatory requirements to ensure that adequately validated examinations are applied. With this purpose, qualification requirements for inspection activities were implemented with other requirements. With progress of technology, progress was also achieved in examination methods and more advanced examination methods and advanced inspection systems were developed. This advancement is accompanied by advancement in regulatory requirements regarding inspection and monitoring of tube integrity and condition. Ultimate goal of implementation of qualification processes and its requirements in all aspects of nuclear industry is to achieve minimal rate of forced outages, which would ensure maximum electrical power production capabilities and maximum optimization of operational costs while maintaining safe operation in accordance with environmental policies. This article will focus on qualification of steam generator eddy current bobbin probe.(author).

  17. Summarized water quality criteria

    International Nuclear Information System (INIS)

    Kempster, P.L.; Hattingh, W.H.J.; Van Vliet, H.R.

    1980-08-01

    The available world literature from 27 sources on existing water quality criteria are summarized for the 15 main uses of water. The minimum, median and maximum specified values for 96 different determinands are included. Under each water use the criteria are grouped according to the functional significance of the determinands e.g. aesthetic/physical effects, high toxic potential, low toxic potential etc. A synopsis is included summarizing salient facts for each determinand such as the conditions under which it is toxic and its relationship to other determinands. The significance of the criteria is briefly discussed and the importance of considering functional interactions between determinands emphasized in evaluating the potential for toxic or beneficial effects. From the source literature it appears that the toxic potential, in addition to being determined by concentration, is also affected by the origin of the substance concerned, i.e. whether from natural sources or from anthropogenic pollution

  18. Qualification of diesel generator exhaust carbon steel piping to intermitted elevated temperatures

    International Nuclear Information System (INIS)

    Ratiu, M.D.; Moisidis, N.T.

    1996-01-01

    The diesel generator exhaust piping, usually made up of carbon steel piping (e.g., ASME SA-106, SA-53), is subjected to successive short time exposures at elevated temperatures up to 1,000 F (538 C). A typical design of this piping, without consideration for creep-fatigue cumulative damage, is at least incomplete, if not inappropriate. Also, a design for creep-fatigue, usually employed for long-term exposure to elevated temperatures, would be too conservative and will impose replacement of the carbon steel piping with heat-resistant CrMo alloy piping. The existing ASME standard procedures do not explicitly provide acceptance criteria for the design qualification to withstand these intermittent exposures to elevated temperatures. The serviceability qualification proposed is based on the evaluation of equivalent full temperature cycles which are presumed/expected to be experienced by the exhaust piping during the design operating life of the diesel engine. The proposed serviceability analysis consists of: (a) determination of the permissible stress at elevated temperatures, and (b) estimation of creep-fatigue damage for the total expected cycles of elevated temperature exposures following the procedure provided in ASME Code Cases N-253-6 and N-47-28

  19. 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

  20. Environmental qualification testing of TFE valve components

    International Nuclear Information System (INIS)

    Eyvindson, A.; Krasinski, W.; McCutcheon, R.

    1997-01-01

    Valves containing tetrafluoroethylene (TFE) components are being used in many CANDU Nuclear Generating Stations. However, some concerns remain about the performance of TFE after exposure to high levels of radiation. Stations must therefore ensure that such valves perform reliably after being exposed to postulated accident radiation dose levels. The current Ontario Hydro Environmental Qualification [EQ] program specifies much higher postulated radiation exposure than the original design, to account for conditions following a LOCA. Initial assessments indicated that Teflon components would require replacement. Proof of acceptable performance can remove the need for large scale replacement, avoiding a significant cost penalty and preserving benefits due to the superior performance of TFE-based seals. A test program was undertaken at Chalk River Laboratories (CRL) to investigate the performance of three valves after irradiation to 10 Mrad. Such valves are currently used at the Bruce B Nuclear Generating Station. Each contains TFE packing rings; one also has TFE seats. Two of the valves are used in the ECIS recovery system, while the third is used for instrumentation loop isolation or as drain valves. All are exposed to little or no radiation during normal use. Based on the results of the tests, all the valves tested will still meet functional and performance requirements after the TFE components have been exposed to 10 Mrad of irradiation. (author)

  1. 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

  2. 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

  3. At site qualification of accelerating tube dynodes

    International Nuclear Information System (INIS)

    Rajan, Rehim N.; Dewangan, S.; Sharma, D.K.

    2015-01-01

    A dc electron beam accelerator rated for 3 MeV encountered numerous vacuum side discharges at terminal voltage levels of 1800 kV. The cumulative rating of the accelerating tube in the system is 3350 kV. Pulsed currents in the order of 50 mA has been observed at the beam collector during these events along with voltage dips in terminal voltage. As dynode to dynode arcing is suspected to be the primary cause of this behaviour, it is desired to test the voltage withstanding capacity of each pair of dynodes. The accelerating tubes are rated for 335 kV at 6 kg/cm 2 SF 6 environment. However working at these pressures and testing of individual pairs of dynodes are impractical for qualification of dynodes of the 10 sets of accelerating tubes mounted in the accelerator. This problem has been overcome by using atmospheric pressure SF 6 and solid dielectrics. Experience of at site testing of the accelerating tube dynodes are described in this paper. (author)

  4. Philosophy, qualifications and training in Canada

    International Nuclear Information System (INIS)

    Rheaume, R.

    1989-01-01

    The Canadian nuclear power industry record concerning radiation protection is commendable, with low doses and no over-exposures, and this despite the much higher risk in this sector compared with the other sectors studied. Various technical factors have contributed towards this achievement, of course, but the philosophy adopted and the high level of qualification of the radiation protection personnel have played a major role. A great deal of work has been put into training nuclear plant operatives up to the desired level, since many were not particularly well-educated. The solution has been to improve the teaching aspect of the training, and to clearly identify the workers' needs by analyzing the tasks which they are required to perform. Consequently, the creation of a systematic training programme for users of radiation sources in universities and hospitals would help to improve radiation protection, especially as the users in this sector are generally better educated than the maintenance workers in power stations. In the mining sector, training does not have such a significant role to play in dose reduction, but it will nevertheless have an indirect impact: once miners know more about radiation and its health implications, their demands, on issues such as ventilation, for example, will become more specific and have more substance

  5. 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.

  6. Effects of Rating Training on Inter-Rater Consistency for Developing a Dental Hygiene Clinical Rater Qualification System

    Directory of Open Access Journals (Sweden)

    Jeong Ran Park

    2007-12-01

    Full Text Available We tried to develop itemized evaluation criteria and a clinical rater qualification system through rating training of inter-rater consistency for experienced clinical dental hygienists and dental hygiene clinical educators. A total of 15 clinical dental hygienists with 1-year careers participated as clinical examination candidates, while 5 dental hygienists with 3-year educations and clinical careers or longer participated as clinical raters. They all took the clinical examination as examinees. The results were compared, and the consistency of competence was measured. The comparison of clinical competence between candidates and clinical raters showed that the candidate group?占퐏 mean clinical competence ranged from 2.96 to 3.55 on a 5-point system in a total of 3 instruments (Probe, Explorer, Curet, while the clinical rater group?占퐏 mean clinical competence ranged from 4.05 to 4.29. There was a higher inter-rater consistency after education of raters in the following 4 items: Probe, Explorer, Curet, and insertion on distal surface. The mean score distribution of clinical raters ranged from 75% to 100%, which was more uniform in the competence to detect an artificial calculus than that of candidates (25% to 100%. According to the above results, there was a necessity in the operating clinical rater qualification system for comprehensive dental hygiene clinicians. Furthermore, in order to execute the clinical rater qualification system, it will be necessary to keep conducting a series of studies on educational content, time, frequency, and educator level.

  7. Qualification of expansion and welding procedures of tube-to-tubesheet joints for heat exchangers in nuclear power plants

    International Nuclear Information System (INIS)

    Camargo, G.D.M.; Couto, J.G.V.; Castro, L.A.S. de

    1986-01-01

    Leaking tube to tubesheet joints are among the most frequent defects detected in the operation of tubular heat exchangers. This kind of problem requires a special treatment, in the case of heat exchangers intalled in nuclear power plants, aiming at a minimum of leakages and further repair outages. The criteria used for the pre-qualification of tube-to-tubesheet joints, is described, and the experiences acquired during the tests and fabrication of several components supplied by national manufacturers, are presented. (Author) [pt

  8. 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

  9. Radiological design criteria

    International Nuclear Information System (INIS)

    Selby, J.M.; Andersen, B.V.; Carter, L.A.; Waite, D.A.

    1977-01-01

    Many new nuclear facilities are unsatisfactory from a radiation protection point of view, particularly when striving to maintain occupational exposure as low as practicable 'ALAP'. Radiation protection is achieved through physical protective features supplemented by administrative controls. Adequate physical protective feature should be achieved during construction so that supplemental administrative controls may be kept simple and workable. Many nuclear facilities fall short of adequate physical protective features, thus, remedial and sometimes awkward administrative procedures are required to safely conduct work. In reviewing the various handbooks, reports and regulations which deal with radiation protection, it may be noted that there is minimal radiological design guidance for application to nuclear facilities. A set of criteria or codes covering functional areas rather than specific nuclear facility types is badly needed. The following are suggested as functional areas to be considered: characterization of the Facility; siting and access; design exposure limits; layout (people and materials flow); ventilation and effluent control; radiation protection facilities and systems. The application of such radiological design criteria early in the design process would provide some assurance that nuclear facilities will be safe, flexible, and efficient with a minimum of costly retrofitting or administrative restrictions. Criteria which we have found helpful in these functional areas is discussed together with justification for adoption of such criteria and identification of problems which still require solution

  10. Comments on confinement criteria

    International Nuclear Information System (INIS)

    Kurak, V.; Schroer, B.; Swieca, J.A.

    1977-01-01

    For a QED 2 model with SU(n) flavour, the nature of the physical states space is more subtle than one expects on the basis of the loop criterion for confinement. One may have colour confinement without confinement of the fundamental flavour representation. Attempts to formulate confinement criteria in which the quark fields play a more fundamental role are discussed [pt

  11. A Motor Drive Electronics Assembly for Mars Curiosity Rover: An Example of Assembly Qualification for Extreme Environments

    Science.gov (United States)

    Kolawa, Elizabeth; Chen, Yuan; Mojarradi, Mohammad M.; Tudryn Weber, Carissa

    2013-01-01

    In this paper, the technology development and infusion of the motor drive electronics assembly, along with the technology qualification and space qualification, is described and detailed. The process is an example of the qualification methodology for extreme environmen

  12. Qualification, commissioning and in situ monitoring of high heat flux plasma facing components

    Energy Technology Data Exchange (ETDEWEB)

    Escourbiac, F. [Association Euratom-CEA, CEA/DSM/DRFC, CEA/Cadarache, F-13108 Saint Paul Lez Durance (France)], E-mail: frederic.escourbiac@cea.fr; Durocher, A.; Grosman, A.; Cismondi, F.; Courtois, X.; Farjon, J.L.; Schlosser, J. [Association Euratom-CEA, CEA/DSM/DRFC, CEA/Cadarache, F-13108 Saint Paul Lez Durance (France); Merola, M.; Tivey, R. [ITER Team, CEA/Cadarache, F-13108 Saint Paul Lez Durance (France)

    2007-10-15

    Up-to-date development of actively cooled high heat flux (HHF) plasma facing components (PFC) prototypes only allows reduced margins with regards to the ITER thermal requirements. Additionally, perfect quality cannot be ensured along series manufacturing: the presence of flaws which impair the heat transfer capability of the component, in particular at the interface armour/heat sink appears to be statistically unavoidable. In order to ensure a successful series production, a qualification methodology of actively cooled high heat flux plasma facing components is proposed. Secondly, advanced non-destructive techniques developed for HHF PFC commissioning are detailed with definition of acceptance criteria. Finally, innovative diagnostics for in situ monitoring during plasma operations or tokamak shutdowns are investigated in order to prevent immediate damage (safety monitoring); or evaluate component degradation (health monitoring). This work takes into account the relevance to Tore Supra, and is applied to W7X and ITER Divertor HHF PFC.

  13. 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)

  14. Sustainability of sources of electric generation: indicators and global qualification using fuzzy logic

    International Nuclear Information System (INIS)

    Martin del Campo M, C.; Francois L, J.L.

    2005-01-01

    A methodology developed to evaluate the sustainability of sources of electric generation but used in Mexico and in the World is presented. For it was applied one matrix of sustainability indicators that considers the principles and criteria of general sustainability as 'not exhaustion of natural resources', 'non production of non degradable waste', and 'not high sensibility to social and environmental factors'. The approaches to evaluate in a wide way these principles are numerous and to each approach associates an indicator, call sustainability indicator. The contribution of this work consists on the development of a methodology to qualify globally the sustainability of each option of electric generation, combining all the sustainability indicators. The methodology applies a system of diffuse control to build the function of global qualification of sustainability dependent of all the indicators. (Author)

  15. 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

  16. Qualification, commissioning and in situ monitoring of high heat flux plasma facing components

    International Nuclear Information System (INIS)

    Escourbiac, F.; Durocher, A.; Grosman, A.; Cismondi, F.; Courtois, X.; Farjon, J.L.; Schlosser, J.; Merola, M.; Tivey, R.

    2007-01-01

    Up-to-date development of actively cooled high heat flux (HHF) plasma facing components (PFC) prototypes only allows reduced margins with regards to the ITER thermal requirements. Additionally, perfect quality cannot be ensured along series manufacturing: the presence of flaws which impair the heat transfer capability of the component, in particular at the interface armour/heat sink appears to be statistically unavoidable. In order to ensure a successful series production, a qualification methodology of actively cooled high heat flux plasma facing components is proposed. Secondly, advanced non-destructive techniques developed for HHF PFC commissioning are detailed with definition of acceptance criteria. Finally, innovative diagnostics for in situ monitoring during plasma operations or tokamak shutdowns are investigated in order to prevent immediate damage (safety monitoring); or evaluate component degradation (health monitoring). This work takes into account the relevance to Tore Supra, and is applied to W7X and ITER Divertor HHF PFC

  17. Current quality criteria

    International Nuclear Information System (INIS)

    Sajaroff, Pedro M.

    1999-01-01

    The Safety Series 50-C/SG-Q 'Quality Assurance for Safety in Nuclear Power Plants and other Nuclear Installations' published by the IAEA in 1996, contains the Code and 14 Safety Guides. It is more addressed to operating organizations than to regulatory authorities. Priority is assigned to programme implementation and to work effectiveness. Emphasis is putted on doing work correctly from the very beginning (right first time attitude), and not on finding and correcting errors instead of preventing them. The essential aspects for assuring quality (that is, for achieving and maintaining an acceptable level of safety) cover the ten basic requirements established by the Code: Management (QA programme, training and qualification, non-conformance control and corrective actions, document control and records); Performance (work, design, procurement, inspection and testing for acceptance); and Assessment (management self-assessment, independent assessment). These requirements are applicable, on a graded approach basis, to the overall QA programme of the operating organization and its partial programmes during design, construction, commissioning, operation and decommissioning stages. The requirements can be also applied, with due adaptations, to other nuclear installations. The research and development activities related to such stages are comprised under the quality 'umbrella' as well. Therefore the scope of the traditional quality assurance is expanded and consolidated as a management tool more oriented to user. Responsibilities for achieving quality objectives are assigned to all involved individuals and organizations at all levels: management, working groups and assessment teams. Managers' is important but individual responsibilities are unavoidable. For the Argentine Nuclear Regulatory Authority, performance-based quality assurance was not a novelty. In line with the regulatory philosophy (which is essentially based on performance) the regulatory standard AR 3.6.1 (Rev.1

  18. ESCC standards, evaluation and qualification of optical fiber connectors for space application

    Science.gov (United States)

    Taugwalder, Frédéric

    2017-11-01

    Optical fiber connectors have been used for the past fifteen years in space application. Reviewing the heritage left from past and current mission, the status of ESCC standards for these components and assemblies will help future use of fiber in space applications. In the frame of the ESA ECI program, Diamond has evaluated and is currently qualifying according to ESCC standards the AVIM and Mini-AVIM connectors. The configuration retained to qualify the connector sets is using a polarization maintaining fiber at 1550nm with a loose tube in PEEK as cable structure. The evaluation has been used to step-stress specific characteristics of the optical fiber connectors with a particular aim at possible failure modes to establish a safety factor for the qualification. The evaluation results presented can be used on a case by case to evaluate special applications that would require to extend the specification. The qualification components can be extended further and a structure for assemblies is proposed in order to simplify fiber optics implementation in space projects.

  19. RMs1: qualification results of the rotary miniature Stirling cryocooler at Thales Cryogenics

    Science.gov (United States)

    Martin, Jean-Yves; Seguineau, Cédric; Van-Acker, Sébastien; Sacau, Mikel; Le Bordays, Julien; Etchanchu, Thierry; Vasse, Christophe; Abadie, Christian; Laplagne, Gilles; Benschop, Tonny

    2017-05-01

    The trend for miniaturized Integrated Dewar and Cooler Assemblies (IDCA) has been confirmed over the past few years with several mentions of a new generation of IR detector working at High Operating Temperature (HOT). This key technology enables the use of cryocooler with reduced needs of cryogenics power. As a consequence, miniaturized IDCA are the combination of a HOT IR detector coupled with a low-size, low-weight and low-power (SWaP) cryocooler. Thales Cryogenics has developed his own line of SWaP products. Qualification results on linear solution where shown last year. The current paper focuses on the latest results obtained on RMs1 prototypes, the new rotary SWaP cryocooler from Thales Cryogenics. Cryogenic performances and induced vibrations are presented. In a second part, progress is discussed on compactness and weight on one side, and on power consumption on the other side. It shows how the trade-off made between weight and power consumption could lead to an optimized solution at system level. At least, an update is made on the qualification status.

  20. Counsellors in primary care in Southampton: a questionnaire survey of their qualifications, working arrangements, and casemix.

    Science.gov (United States)

    Clark, A; Hook, J; Stein, K

    1997-01-01

    BACKGROUND: There has been an upsurge of interest in counselling in primary care over the past five years. This has been stimulated by a growing demand for non-drug treatment of emotional disorders and by the extension of reimbursement for the costs of counsellors. Continued calls for careful evaluation have been largely unheeded in the face of heady growth. AIM: To establish the prevalence of counselling services in the 67 general practices in the Southampton and South West Hampshire Health District, and to describe in detail their qualifications, working arrangements, and casemix. METHOD: A questionnaire enquiring about counselling services was sent to all the general practices in the district. A second questionnaire was then posted to all the counsellors identified as working in these practices. RESULTS: Twenty-six (39%) practices employed one or more counsellors. Fundholding practices were four times more likely than non-fundholders to employ a counsellor. Most of the counselling work was short term (4-20 sessions). The most common presenting complaints were relationship problems, depression, anxiety, and bereavement. CONCLUSION: This descriptive study highlights the wide variation in the qualifications and training of counsellors. Until the issue of effectiveness is resolved through further research, the best safeguard of quality is to ensure that counsellors meet the appropriate training standards laid down by the British Association of Counsellors. Monitoring standards is a legitimate task for those commissioning health care who are increasingly responsible for reimbursement of a counsellor's salary. Counsellors who meet appropriate training criteria should be encouraged to pursue accreditation with the British Association of Counsellors. Those who do not meet these criteria should be encouraged to undergo additional training. PMID:9474822

  1. Background information for NDT qualification of Finnish disposal canisters of spent fuel

    Energy Technology Data Exchange (ETDEWEB)

    Sarkimo, M. [VTT Technical Research Centre of Finland, Espoo (Finland); Pitkaenen, J.

    2013-12-15

    This report presents a review to basic concepts, which are applied in the qualification of non-destructive testing (NDT) techniques. The qualification systems developed and used in some countries are briefly described in the beginning of the report. Anyway the report mainly discusses the qualification practices applied in the Finnish nuclear industry. The Finnish Radiation and Nuclear Safety Authority (STUK) in the YVL Guide 3.8 define the Finnish qualification approach applied for the in-service inspections. The principles presented in this document follow the views of the international organisations: Nuclear Regulator Working Group (NRWG) and European Network for Inspection and Qualification (ENIQ). For the practical qualification work a national guideline is established using so called SP-documents that include specific rules and instructions for execution of qualifications in accordance with YVL Guide 3.8 principles. Altogether the Finnish qualification system can be seen very well to follow the European (ENIQ) methodology. The report discusses several qualification terms and documents. Thus the normally necessary tasks and parts of a qualification are described. The qualification can be seen as a project that includes several tasks, which will be performed by different parties. Enough resources and time should be reserved for the planning and control of a qualification project to ensure its fluent progress. Some tasks are discussed in the report taking into account the situation in the qualification cases that are seen to be linked to the inspections of disposal canisters of spent fuel. (orig.)

  2. Background information for NDT qualification of Finnish disposal canisters of spent fuel

    International Nuclear Information System (INIS)

    Sarkimo, M.; Pitkaenen, J.

    2013-12-01

    This report presents a review to basic concepts, which are applied in the qualification of non-destructive testing (NDT) techniques. The qualification systems developed and used in some countries are briefly described in the beginning of the report. Anyway the report mainly discusses the qualification practices applied in the Finnish nuclear industry. The Finnish Radiation and Nuclear Safety Authority (STUK) in the YVL Guide 3.8 define the Finnish qualification approach applied for the in-service inspections. The principles presented in this document follow the views of the international organisations: Nuclear Regulator Working Group (NRWG) and European Network for Inspection and Qualification (ENIQ). For the practical qualification work a national guideline is established using so called SP-documents that include specific rules and instructions for execution of qualifications in accordance with YVL Guide 3.8 principles. Altogether the Finnish qualification system can be seen very well to follow the European (ENIQ) methodology. The report discusses several qualification terms and documents. Thus the normally necessary tasks and parts of a qualification are described. The qualification can be seen as a project that includes several tasks, which will be performed by different parties. Enough resources and time should be reserved for the planning and control of a qualification project to ensure its fluent progress. Some tasks are discussed in the report taking into account the situation in the qualification cases that are seen to be linked to the inspections of disposal canisters of spent fuel. (orig.)

  3. Qualification tests for PWR control element drive mechanism

    Energy Technology Data Exchange (ETDEWEB)

    Kim, In Yong; Jin, Choon Eon; Choi Suhn [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1996-01-01

    It is necessary to perform the qualification test for the magnetic jack type CEDM to show the design compatibility because the CEDM is composed of many mechanical and electrical components complicatedly. ABB-CE performed various qualification tests during the development of the System80 CEDM to which Korea Standard Nuclear Plant (KSNP) CEDM referred. The qualification test for the CEDM is classified into the performance test and the dynamic test. The performance test is to verify operability of the CEDM, and the dynamic test is to find dynamic characteristics and to verify the structural integrity if the CEDM for the seismic accidents. Described in this report are the test requirements, the test facilities and the test methods for the performance and the dynamic qualification tests of the PWR magnetic jack type CEDM. The impacts of the design changes in the Korea Next Generation Reactor (KNGR) on the KSNP CEDM were analyzed to present the necessity for the tests. This report also proposes the facilities to perform the tests in KAERI including reasonable schedule for the tests. Attached to this report is the summary of qualification tests of System 80 CEDM performed by ABB-CE. 20 figs., 16 tabs., 21 refs. (Author) .new.

  4. Qualification tests for PWR control element drive mechanism

    International Nuclear Information System (INIS)

    Kim, In Yong; Jin, Choon Eon; Choi Suhn

    1996-01-01

    It is necessary to perform the qualification test for the magnetic jack type CEDM to show the design compatibility because the CEDM is composed of many mechanical and electrical components complicatedly. ABB-CE performed various qualification tests during the development of the System80 CEDM to which Korea Standard Nuclear Plant (KSNP) CEDM referred. The qualification test for the CEDM is classified into the performance test and the dynamic test. The performance test is to verify operability of the CEDM, and the dynamic test is to find dynamic characteristics and to verify the structural integrity if the CEDM for the seismic accidents. Described in this report are the test requirements, the test facilities and the test methods for the performance and the dynamic qualification tests of the PWR magnetic jack type CEDM. The impacts of the design changes in the Korea Next Generation Reactor (KNGR) on the KSNP CEDM were analyzed to present the necessity for the tests. This report also proposes the facilities to perform the tests in KAERI including reasonable schedule for the tests. Attached to this report is the summary of qualification tests of System 80 CEDM performed by ABB-CE. 20 figs., 16 tabs., 21 refs. (Author) .new

  5. 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

  6. 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

  7. Criteria for accepting piping thermal expansion movements during FFTF plant startup

    International Nuclear Information System (INIS)

    Clark, G.L.; Anderson, M.J.

    1981-03-01

    A deflection measurement program was conducted as a final step in the design qualification of the Fast Flux Test Facility liquid sodium piping. Measurements were obtained from the ambient empty position, through the 400 0 F (204 0 C) sodium fill, to an 800 0 F (427 0 C) maximum iso-thermal test condition. The program was designed to confirm that the pipe responded as predicted under both deadweight and thermal expansion loads. This paper describes the design of the test programs; the criteria used to select appropriate measurement locations from the approximately 4000 supports used on this pipe; and the criteria used to accept test results

  8. Human Systems Design Criteria

    DEFF Research Database (Denmark)

    Rasmussen, Jens

    1982-01-01

    This paper deals with the problem of designing more humanised computer systems. This problem can be formally described as the need for defining human design criteria, which — if used in the design process - will secure that the systems designed get the relevant qualities. That is not only...... the necessary functional qualities but also the needed human qualities. The author's main argument is, that the design process should be a dialectical synthesis of the two points of view: Man as a System Component, and System as Man's Environment. Based on a man's presentation of the state of the art a set...... of design criteria is suggested and their relevance discussed. The point is to focus on the operator rather than on the computer. The crucial question is not to program the computer to work on its own conditions, but to “program” the operator to function on human conditions....

  9. Intelligent intefrace design criteria

    International Nuclear Information System (INIS)

    Sicard, Y.; Siebert, S.; Thebault, M.H.

    1990-01-01

    Optimum adequation between control means and the capacities of the teams of operators is sought for to achieve computerization of control and monitoring interfaces. Observation of the diagnosis activity of populations of operators in incident situations on a simulator enables design criteria well-suited to the characteristics of the detection, interpretation of symptoms and incident location tasks to be defined. A software tool based on a qualitative approach enables the design process to be systematized

  10. Qualification, training, licensing/authorization and retraining of operating personnel in nuclear power plants. Noteworthy topics identified by evaluation of the practices in countries of the European Communities

    International Nuclear Information System (INIS)

    Kraut, A.; Pfeffer, W.

    1987-01-01

    In the report EUR 10118 '' Qualification, training, licensing and retraining of operating shift personnel in nuclear power plants'' the current practice in the countries of the European Communities as well as the procedures and programmes applied in Sweden, Switzerland and the USA are outlined and evaluated. The intent was to derive fundamental and generally valid concepts concerning shift-staff training and other relevant aspects. Those items were identified that seemed to be noteworthy because they give some guidance on how to achieve and maintain the qualification of the shift staff of NPPs or how to improve the staffing of the control room. These noteworthy topics identified by evaluation of the practice in countries of the European Communities and also elsewhere are presented in the publication at hand. The report addresses the following topics: tasks of the shift personnel, nomenclature for different grades of the personnel; shift staffing and staffing of the control room; criteria for personnel selection when recruiting new shift staff; personnel qualification necessary for recruitment; training of shift personnel; retraining and preservation of qualification standards; training facilities, especially simulators; responsibility for training; licensing/authorization; retirement from shift work. Consideration of these more general aspects and concepts may lead to improvement in training. The job descriptions given in the Annex to the document are only intended to give a general understanding of the typical designations, tasks and responsibilities of shift staff

  11. Safety system status monitoring

    International Nuclear Information System (INIS)

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

    1984-03-01

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

  12. Safety system status monitoring

    Energy Technology Data Exchange (ETDEWEB)

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

    1984-03-01

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

  13. Investigation on legislation necessity of qualification of quality assurance auditors for civilian nuclear components

    International Nuclear Information System (INIS)

    Zhu Hong

    2004-01-01

    The paper discusses the actual state and legislation necessity of administration for qualification of quality assurance auditors engaging in nuclear component activities in our country, and presents the tentative idea for establishing qualification system of quality assurance auditors. (author)

  14. Qualification of box HEPA filters for nuclear applications

    International Nuclear Information System (INIS)

    Bergman, W.; Larsen, G.; Wilson, K.; Rainer, F.

    1995-03-01

    We have successfully completed qualification tests on high efficiency particulate air (HEPA) filters that are encapsulated within a box and manufactured by American Air Filters. The qualification tests are required by the American Society of Mechanical Engineers Standard ASME N509 and the U.S. Military Standard MIL-F-51068 for HEPA filters to be used in nuclear applications. The qualification tests specify minimum filter efficiencies following exposure to heated air, overpressure, and rough handling. Prior to this study, no box HEPA filters from any manufacturer had been qualified despite their wide-spread use in Department of Energy (DOE) facilities. Box HEPA filters are not addressed in any of the existing HEPA standards and only briefly discussed in the Nuclear Air Cleaning Handbook

  15. 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

  16. Qualifications Frameworks and their conflicting social imaginaries of globalisation

    DEFF Research Database (Denmark)

    Sarauw, Laura Louise

    2013-01-01

    Critics of the European Bologna process often see it as a univocal standardization of higher education. By exploring how different qualifications frameworks currently project unlike imaginaries of and responses to globalisation, this article takes a different stance. As a key point, I argue...... that the well-known imaginary of globalisation as a change towards a more diverse and unforeseeable world, which calls for the development of flexible, lifelong learners with a broad knowledge base and strong democratic competencies that we find in the overarching qualifications framework of the Bologna process......, is a highly contested imaginary. In contrast, for example, the Danish qualifications framework of 2003 projects an imaginary of globalisation as a change towards a smaller and more predictable world, which enables a novel and more efficient alignment of the curriculum towards specific professional needs...

  17. The path from biomarker discovery to regulatory qualification

    CERN Document Server

    Goodsaid, Federico

    2013-01-01

    The Path from Biomarker Discovery to Regulatory Qualification is a unique guide that focuses on biomarker qualification, its history and current regulatory settings in both the US and abroad. This multi-contributed book provides a detailed look at the next step to developing biomarkers for clinical use and covers overall concepts, challenges, strategies and solutions based on the experiences of regulatory authorities and scientists. Members of the regulatory, pharmaceutical and biomarker development communities will benefit the most from using this book-it is a complete and practical guide to biomarker qualification, providing valuable insight to an ever-evolving and important area of regulatory science. For complimentary access to chapter 13, 'Classic' Biomarkers of Liver Injury, by John R. Senior, Associate Director for Science, Food and Drug Administration, Silver Spring, Maryland, USA, please visit the following site:  http://tinyurl.com/ClassicBiomarkers Contains a collection of experiences of different...

  18. 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

  19. Evaluation and qualification of novel control techniques with safety requirements

    International Nuclear Information System (INIS)

    Gossner, S.; Wach, D.

    1985-01-01

    The paper discusses the questions related to the assessment and qualification of new I and C-systems. The tasks of nuclear power plant I and Cs as well as the efficiency of the new techniques are reflected. Problems with application of new I and Cs and the state of application in Germany and abroad are addressed. Starting from the essential differencies between conventional and new I and C-systems it is evaluated, if and in which way existing safety requirements can be met and to what extent new requirements need to be formulated. An overall concept has to be developed comprising the definition of graded requirement profiles for design and qualification. Associated qualification procedures and tools have to be adapted, developed and tuned upon each other. (orig./HP) [de

  20. Qualification of NDT systems for in-service inspections of nuclear power plant pressure vessels

    International Nuclear Information System (INIS)

    Elfving, K.

    1998-11-01

    The goal of this study is to determine the requirements of the in-service inspection qualification in Europe, their feasibility in practice and to find out possible manufacture defects in test pieces used in practical trials. The literature study consists of qualification requirements set by European regulatory bodies and by the European nuclear power utilities. Also a brief summary of qualification requirements set by ASME Code, Section XI and comparison between ASME and European qualification requirements is included

  1. 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

  2. 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

  3. 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

  4. Fatigue qualification of high thickness composite rotor components

    Science.gov (United States)

    Raggi, M.; Mariani, U.; Zaffaroni, G.

    Fatigue qualification aspects of composite rotor components are presented according with the safe life procedure usually applied by helicopter manufacturers. Test activities are identified at three levels of specimen complexity: coupon, structural element and full scale component. Particular attention is given to high thickness laminates qualification as far as environmental exposure is concerned. A practical approach for an accelerated conditioning procedure is described. The application to a main rotor tension link is presented showing the negligible effect of the moisture absorption on its fatigue strength.

  5. Qualification Procedures of the CMS Pixel Barrel Modules

    CERN Document Server

    Starodumov, A; Horisberger, R.; Kastli, H.Chr.; Kotlinski, D.; Langenegger, U.; Meier, B.; Rohe, T.; Trueb, P.

    2006-01-01

    The CMS pixel barrel system will consist of three layers built of about 800 modules. One module contains 66560 readout channels and the full pixel barrel system about 48 million channels. It is mandatory to test each channel for functionality, noise level, trimming mechanism, and bump bonding quality. Different methods to determine the bump bonding yield with electrical measurements have been developed. Measurements of several operational parameters are also included in the qualification procedure. Among them are pixel noise, gains and pedestals. Test and qualification procedures of the pixel barrel modules are described and some results are presented.

  6. 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

  7. The ASEAN economic community and medical qualification.

    Science.gov (United States)

    Kittrakulrat, Jathurong; Jongjatuporn, Witthawin; Jurjai, Ravipol; Jarupanich, Nicha; Pongpirul, Krit

    2014-01-01

    In the regional movement toward ASEAN Economic Community (AEC), medical professions including physicians can be qualified to practice medicine in another country. Ensuring comparable, excellent medical qualification systems is crucial but the availability and analysis of relevant information has been lacking. This study had the following aims: 1) to comparatively analyze information on Medical Licensing Examinations (MLE) across ASEAN countries and 2) to assess stakeholders' view on potential consequences of AEC on the medical profession from a Thai perspective. To search for relevant information on MLE, we started with each country's national body as the primary data source. In case of lack of available data, secondary data sources including official websites of medical universities, colleagues in international and national medical student organizations, and some other appropriate Internet sources were used. Feasibility and concerns about validity and reliability of these sources were discussed among investigators. Experts in the region invited through HealthSpace.Asia conducted the final data validation. For the second objective, in-depth interviews were conducted with 13 Thai stakeholders, purposely selected based on a maximum variation sampling technique to represent the points of view of the medical licensing authority, the medical profession, ethicists and economists. MLE systems exist in all ASEAN countries except Brunei, but vary greatly. Although the majority has a national MLE system, Singapore, Indonesia, and Vietnam accept results of MLE conducted at universities. Thailand adopted the USA's 3-step approach that aims to check pre-clinical knowledge, clinical knowledge, and clinical skills. Most countries, however, require only one step. A multiple choice question (MCQ) is the most commonly used method of assessment; a modified essay question (MEQ) is the next most common. Although both tests assess candidate's knowledge, the Objective Structured Clinical

  8. AGC-2 Irradiation Data Qualification Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Laurence C. Hull

    2012-07-01

    The Graphite Technology Development Program will run a series of six experiments to quantify the effects of irradiation on nuclear grade graphite. The second Advanced Graphite Creep (AGC) experiment (AGC-2) began with Advanced Test Reactor (ATR) Cycle 149A on April 12, 2011, and ended with ATR Cycle 151B on May 5, 2012. The purpose of this report is to qualify AGC-2 irradiation monitoring data following INL Management and Control Procedure 2691, Data Qualification. Data that are Qualified meet the requirements for data collection and use as described in the experiment planning and quality assurance documents. Data that do not meet the requirements are Failed. Some data may not quite meet the requirements, but may still provide some useable information. These data are labeled as Trend. No Trend data were identified for the AGC-2 experiment. All thermocouples functioned throughout the AGC-2 experiment. There was one instance where spurious signals or instrument power interruption resulted in a recorded temperature value being well outside physical reality. This value was identified and labeled as Failed data. All other temperature data are Qualified. All helium and argon gas flow data are within expected ranges. Total gas flow was approximately 50 sccm through the capsule. Helium gas flow was briefly increased to 100 sccm during reactor shutdown. All gas flow data are Qualified. At the start of the experiment, moisture in the outflow gas line increased to 200 ppmv then declined to less than 10 ppmv over a period of 5 days. This increase in moisture coincides with the initial heating of the experiment and drying of the system. Moisture slightly exceeded 10 ppmv three other times during the experiment. While these moisture values exceed the 10 ppmv threshold value, the reported measurements are considered accurate and to reflect moisture conditions in the capsule. All moisture data are Qualified. Graphite creep specimens are subjected to one of three loads, 393 lbf

  9. Global National Qualifications Framework Inventory: Country Cases from EU and ETF Partner Countries

    Science.gov (United States)

    Cedefop - European Centre for the Development of Vocational Training, 2013

    2013-01-01

    Certificates, diplomas and titles are commonly known as qualifications. Their purpose is to show employers, training providers, and individuals what the person holding the qualification has learned and can do. Every country issues many different qualifications, but for the European labor market to work as intended--that is for European citizens to…

  10. 78 FR 53025 - Pilot Certification and Qualification Requirements for Air Carrier Operations; Correction

    Science.gov (United States)

    2013-08-28

    ...-0100; Amdt. No. 141-17A] RIN 2120-AJ67 Pilot Certification and Qualification Requirements for Air... regulations to create new certification and qualification requirements for pilots in air carrier operations..., the FAA published a final rule entitled, ``Pilot Certification and Qualification Requirements for Air...

  11. 5 CFR 531.212 - Superior qualifications and special needs pay-setting authority.

    Science.gov (United States)

    2010-01-01

    ... 5 Administrative Personnel 1 2010-01-01 2010-01-01 false Superior qualifications and special needs... Appointment Or Position Changes § 531.212 Superior qualifications and special needs pay-setting authority. (a) Agency authority. (1) An agency may use the superior qualifications and special needs pay-setting...

  12. 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…

  13. 25 CFR 117.26 - Expenses incurred pending qualification of an executor or administrator.

    Science.gov (United States)

    2010-04-01

    ... 25 Indians 1 2010-04-01 2010-04-01 false Expenses incurred pending qualification of an executor or... HAVE CERTIFICATES OF COMPETENCY § 117.26 Expenses incurred pending qualification of an executor or administrator. Pending the qualification of the executor or administrator of the estate of a deceased Indian of...

  14. 49 CFR 214.349 - Training and qualification of watchmen/lookouts.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 4 2010-10-01 2010-10-01 false Training and qualification of watchmen/lookouts...) FEDERAL RAILROAD ADMINISTRATION, DEPARTMENT OF TRANSPORTATION RAILROAD WORKPLACE SAFETY Roadway Worker Protection § 214.349 Training and qualification of watchmen/lookouts. (a) The training and qualification for...

  15. Forced Attention to Specific Applicant Qualifications: Impact on Physical Attractiveness and Sex of Applicant Biases.

    Science.gov (United States)

    Cann, Arnie; And Others

    1981-01-01

    Undergraduates evaluated the qualifications of an attractive, average, or unattractive male or female applicant. Ratings of specific qualifications preceded or followed an overall and hiring decision rating. The order variable influenced ratings of specific qualifications but not the overall or hiring decision. Male and attractive applicants were…

  16. Criteria for software modularization

    Science.gov (United States)

    Card, David N.; Page, Gerald T.; Mcgarry, Frank E.

    1985-01-01

    A central issue in programming practice involves determining the appropriate size and information content of a software module. This study attempted to determine the effectiveness of two widely used criteria for software modularization, strength and size, in reducing fault rate and development cost. Data from 453 FORTRAN modules developed by professional programmers were analyzed. The results indicated that module strength is a good criterion with respect to fault rate, whereas arbitrary module size limitations inhibit programmer productivity. This analysis is a first step toward defining empirically based standards for software modularization.

  17. Project for qualification of the Kozloduy confinement system; Proyecto de cualificacion del sistema de confinamiento de Kozloduy

    Energy Technology Data Exchange (ETDEWEB)

    Montes Rodriguez, J L [Empresarios Agrupados, A.I.E., Madrid (Spain)

    1993-12-15

    One of the projects awarded to Empresarios Agrupados within the Six-Month WANO Programme for Kozloduy NPP, financed through the European Community's PHARE Programme, relates to the first tasks of plant confinement system qualification. Development of this project - the results of which will serve as a reference for other power plants with VVER-440/230 models - aroused considerable interest in the Bulgarian nuclear community as well as in international entities which render assistance to Eastern power plants. In fact, this is one of the few projects in the programme which takes into account hardware-oriented activities to be carried out urgently in the plant. The VVER-440/230 confinement system performs functions parallel to the containment system of Western PWR reactors. However, it differs significantly in its criteria and operation details. These important differences form the basis for a rational and prudent application of the essence of Western codes and standards relating to the qualification of these systems. The criteria which are developed to make this application viable constitute the most challenging and, at the same time, most risky part of this job. The project will be in its final stages when the 18th Annual Meeting of the Spanish Nuclear Society is held; it is therefore likely that this paper will advance the results and conclusions expected. (author)

  18. LL/ILW: Post-Qualification of Old Waste through Non-Destructive Extraction of Barrels from Cement Shields - 13535

    International Nuclear Information System (INIS)

    Oehmigen, Steffen; Ambos, Frank

    2013-01-01

    Currently there is a large number of radioactive waste drums entombed in cement shields at German nuclear power plants. These concrete containers used in the past for the waste are not approved for the final repository. Compliance with current acceptance criteria of the final repository has to be proven by qualification measures on the waste. To meet these criteria, a new declaration and new packing is necessary. A simple non-destructive extraction of about 2000 drums from their concrete shields is not possible. So different methods were tested to find a way of non-destructive extraction of old waste drums from cement shields and therefore reduce the final repository volume and final repository costs by using a container accepted and approved for Konrad. The main objective was to build a mobile system to offer this service to nuclear plant stations. (authors)

  19. Safety and reliability criteria

    International Nuclear Information System (INIS)

    O'Neil, R.

    1978-01-01

    Nuclear power plants and, in particular, reactor pressure boundary components have unique reliability requirements, in that usually no significant redundancy is possible, and a single failure can give rise to possible widespread core damage and fission product release. Reliability may be required for availability or safety reasons, but in the case of the pressure boundary and certain other systems safety may dominate. Possible Safety and Reliability (S and R) criteria are proposed which would produce acceptable reactor design. Without some S and R requirement the designer has no way of knowing how far he must go in analysing his system or component, or whether his proposed solution is likely to gain acceptance. The paper shows how reliability targets for given components and systems can be individually considered against the derived S and R criteria at the design and construction stage. Since in the case of nuclear pressure boundary components there is often very little direct experience on which to base reliability studies, relevant non-nuclear experience is examined. (author)

  20. Overview and status of ITER internal components

    International Nuclear Information System (INIS)

    Merola, Mario; Escourbiac, Frederic; Raffray, René; Chappuis, Philippe; Hirai, Takeshi; Martin, Alex

    2014-01-01

    Highlights: • Manufacturing technologies for the ITER internal components have been developed. • The Blanket System successfully went through its Final Design Review in April 2013. • The decision to start operation with a Divertor with a full-W armour has been taken. - Abstract: The internal components of ITER are one of the most design and technically challenging components of the ITER machine, and include the Blanket System and the Divertor. The Blanket System successfully went through its Final Design Review in April 2013 and now it is entering into the procurement phase. The design and qualification of the Divertor with a full-tungsten armour was successfully completed and this enabled the decision in November 2013 to start operation with this material option. This paper summarizes the engineering design, the R and D, the technology qualification and procurement status of the Blanket System and of the Divertor of the ITER machine

  1. Overview and status of ITER internal components

    Energy Technology Data Exchange (ETDEWEB)

    Merola, Mario, E-mail: mario.merola@iter.org; Escourbiac, Frederic; Raffray, René; Chappuis, Philippe; Hirai, Takeshi; Martin, Alex

    2014-10-15

    Highlights: • Manufacturing technologies for the ITER internal components have been developed. • The Blanket System successfully went through its Final Design Review in April 2013. • The decision to start operation with a Divertor with a full-W armour has been taken. - Abstract: The internal components of ITER are one of the most design and technically challenging components of the ITER machine, and include the Blanket System and the Divertor. The Blanket System successfully went through its Final Design Review in April 2013 and now it is entering into the procurement phase. The design and qualification of the Divertor with a full-tungsten armour was successfully completed and this enabled the decision in November 2013 to start operation with this material option. This paper summarizes the engineering design, the R and D, the technology qualification and procurement status of the Blanket System and of the Divertor of the ITER machine.

  2. Combining the IADPSG criteria with the WHO diagnostic criteria for ...

    African Journals Online (AJOL)

    Macrosomia or at least one adverse outcome were more likely in GDM patients who met the diagnostic criteria by both the IADPSG and WHO criteria (P = 0.001). Conclusion: A diagnosis of GDM that meets both the WHO and IADPSG criteria provides stronger prediction for adverse pregnancy outcome than a diagnosis that ...

  3. Decant pump assembly and controls qualification testing - test report

    Energy Technology Data Exchange (ETDEWEB)

    Staehr, T.W., Westinghouse Hanford

    1996-05-02

    This report summarizes the results of the qualification testing of the supernate decant pump and controls system to be used for in-tank sludge washing in aging waste tank AZ-101. The test was successful and all components are qualified for installation and use in the tank.

  4. The Impact of Teacher Qualification and Subject Major in the ...

    African Journals Online (AJOL)

    The findings therefore suggest that the policies adopted by the Ministry of Education concerning qualifications and subject majors of teachers that are employed make important difference in the students academic achievement in mathematics in Lesotho. African Journal of Cross-Cultural psychology and sport facilitation ...

  5. 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

  6. 47 CFR 73.4101 - Financial qualifications, TV stations.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 4 2010-10-01 2010-10-01 false Financial qualifications, TV stations. 73.4101 Section 73.4101 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) BROADCAST RADIO SERVICES..., TV stations. See Public Notice, FCC 79-299, dated May 11, 1979. 72 F.C.C. 2d 784; 44 FR 29160, May 18...

  7. 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)

  8. 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...

  9. 38 CFR 1.601 - Qualifications for access.

    Science.gov (United States)

    2010-07-01

    ...) An applicant for read-only access to VBA automated claims records from a location other than a VA... utilized to obtain access, as well as their location, must be approved in advance by VBA. (c) Each... 38 Pensions, Bonuses, and Veterans' Relief 1 2010-07-01 2010-07-01 false Qualifications for access...

  10. The IB Diploma and UK University Degree Qualifications

    Science.gov (United States)

    Frank-Gemmill, Gerda

    2013-01-01

    In recent years the International Baccalaureate (IB) Diploma has become widely accepted as a university-entry qualification in the UK, but there has been little quantitative research into the achievements of IB students at degree level. This study investigates IB students from one selective independent school who entered UK universities between…

  11. Developing, Approving and Maintaining Qualifications: Selected International Approaches. Research Report

    Science.gov (United States)

    Misko, Josie

    2015-01-01

    There are lessons for Australia in the key approaches to the development, approval, maintenance and quality assurance of qualifications adopted in countries overseas. This research takes into account a range of approaches used in selected European Union (EU) member states (Germany, Finland and Sweden), the United Kingdom (England, Northern Ireland…

  12. Teacher Qualification Guidelines, Ecological Literacy and Outdoor Education

    Science.gov (United States)

    Martin, Peter

    2008-01-01

    A key signpost to a profession is clarity of disciplinary knowledge. In this paper I describe the content and outcome of a process to refine the qualification guidelines for outdoor education teachers in Victorian, Australia. The guidelines, developed for the Victorian Institute of Teaching, include both practical skills and disciplinary…

  13. 78 FR 62935 - Qualification of Drivers; Exemption Applications; Vision

    Science.gov (United States)

    2013-10-22

    ..., his optometrist noted, ``Mr. Smith, despite having a prosthetic left eye, has fully functional vision...-0166] Qualification of Drivers; Exemption Applications; Vision AGENCY: Federal Motor Carrier Safety... announces receipt of applications from 26 individuals for exemption from the vision requirement in the...

  14. International Harmonization of Training and Qualification in the Manufacturing Industry

    Science.gov (United States)

    Quintino, L.; Fernandes, I.; Miranda, R. M.

    2011-01-01

    Purpose: The aim of this paper is to propose a model for international harmonization of the training and qualification of human resources for industrial professions. The outcome is a system based on training guidelines and a quality assurance methodology that is now in use in 42 countries around the world. Design/methodology/approach: The paper…

  15. Shaking table qualification tests of mechanical and electrical components

    International Nuclear Information System (INIS)

    Jurukovski, D.

    1993-01-01

    This presentation covers the experience of the Institute of Earthquake Engineering and Engineering Seismology, Skopje, Republic of Macedonia in seismic qualification of mechanical components by shaking table testing. The characteristics of the biaxial seismic and single component shaking tables used at the Institute are given. Some examples of the experience from performed test for reactor components are included

  16. 18 CFR 41.12 - Qualifications of accountants.

    Science.gov (United States)

    2010-04-01

    ... Regulations § 41.12 Qualifications of accountants. The Commission will not recognize any certified public accountant or public accountant through December 31, 1975, who is not in fact independent. Beginning January... accountants, or independent licensed public accountants who were licensed on or before December 31, 1970, who...

  17. 42 CFR 493.1469 - Standard: Cytology general supervisor qualifications.

    Science.gov (United States)

    2010-10-01

    ... 42 Public Health 5 2010-10-01 2010-10-01 false Standard: Cytology general supervisor... Nonwaived Testing Laboratories Performing High Complexity Testing § 493.1469 Standard: Cytology general supervisor qualifications. The cytology general supervisor must be qualified to supervise cytology services...

  18. 48 CFR 53.301-330 - Architect-Engineer Qualifications.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 2 2010-10-01 2010-10-01 false Architect-Engineer Qualifications. 53.301-330 Section 53.301-330 Federal Acquisition Regulations System FEDERAL ACQUISITION REGULATION (CONTINUED) CLAUSES AND FORMS FORMS Illustrations of Forms 53.301-330 Architect-Engineer...

  19. Impact of Qualification Framework in United Arab Emirates: A case ...

    African Journals Online (AJOL)

    2018-02-10

    Feb 10, 2018 ... education, Quality assurance, Competencies. This is an Open ... level, e.g., level 7 for a Bachelor's degree, level 9 for Master's, and level 10 for ... Master of Pharmacy (MPharm) curricula through several stages. .... with economic and social development .... 10] Available from: http://www.qualifications.ae/pdf/.

  20. Assessment Rocks? The Assessment of Group Composing for Qualification

    Science.gov (United States)

    Thorpe, Vicki

    2012-01-01

    Ensembles such as rock and pop bands are places of exciting creativity and intense, enjoyable music making for young people. A recent review of New Zealand's secondary school qualification, the National Certificates of Educational Achievement (NCEA), has resulted in a new composition assessment of individuals' achievement in groups. An analysis of…

  1. 21 CFR 111.12 - What personnel qualification requirements apply?

    Science.gov (United States)

    2010-04-01

    ... 21 Food and Drugs 2 2010-04-01 2010-04-01 false What personnel qualification requirements apply? 111.12 Section 111.12 Food and Drugs FOOD AND DRUG ADMINISTRATION, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED) FOOD FOR HUMAN CONSUMPTION CURRENT GOOD MANUFACTURING PRACTICE IN MANUFACTURING...

  2. Sustained qualification process for full scope nuclear power plant simulators

    International Nuclear Information System (INIS)

    Pirson, J.; Stubbe, E.; Vanhoenacker, L.

    1994-01-01

    In the past decade, simulator training for all nuclear power plant operators has evolved into a vital requirement. To assure a correct training, the simulator qualification process is an important issue not only for the initial validation but also following major simulator updates, which are necessary during the lifetime of the simulator. In order to avoid degradation of the simulator validated software, the modifications have to be introduced according to a rigorous methodology and a practical requalification process has to be applied. Such methodology has to be enforced at every phase of the simulator construction or updating process from plant data package constitution, over simulator software development to simulator response qualification. The initial qualification and requalification process is based on the 3 levels identified by the ANSI/ANS 3-5 standard for steady-state, operational transients and accident conditions. For the initial certification of the full scope simulators in Belgium, a practical qualification methodology has been applied, which has been adapted into a set of non regression tests for the requalification after major simulator updates. (orig.) (4 refs., 3 figs.)

  3. Biomarkers as drug development tools: discovery, validation, qualification and use.

    Science.gov (United States)

    Kraus, Virginia B

    2018-06-01

    The 21st Century Cures Act, approved in the USA in December 2016, has encouraged the establishment of the national Precision Medicine Initiative and the augmentation of efforts to address disease prevention, diagnosis and treatment on the basis of a molecular understanding of disease. The Act adopts into law the formal process, developed by the FDA, of qualification of drug development tools, including biomarkers and clinical outcome assessments, to increase the efficiency of clinical trials and encourage an era of molecular medicine. The FDA and European Medicines Agency (EMA) have developed similar processes for the qualification of biomarkers intended for use as companion diagnostics or for development and regulatory approval of a drug or therapeutic. Biomarkers that are used exclusively for the diagnosis, monitoring or stratification of patients in clinical trials are not subject to regulatory approval, although their qualification can facilitate the conduct of a trial. In this Review, the salient features of biomarker discovery, analytical validation, clinical qualification and utilization are described in order to provide an understanding of the process of biomarker development and, through this understanding, convey an appreciation of their potential advantages and limitations.

  4. 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

  5. 75 FR 1449 - Qualification of Drivers; Exemption Applications; Diabetes

    Science.gov (United States)

    2010-01-11

    ...-2009-0289] Qualification of Drivers; Exemption Applications; Diabetes AGENCY: Federal Motor Carrier... decision to exempt forty-one individuals from its rule prohibiting persons with insulin-treated diabetes... notice of receipt of Federal diabetes exemption applications from forty-one individuals and requested...

  6. 49 CFR 398.3 - Qualifications of drivers or operators.

    Science.gov (United States)

    2010-10-01

    ... possesses the following minimum qualifications: (1) No loss of foot, leg, hand or arm, (2) No mental..., impairment of use of foot, leg, fingers, hand or arm, or other structural defect or limitation, likely to... CARRIER SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION FEDERAL MOTOR CARRIER SAFETY REGULATIONS...

  7. Student Mobility, Qualifications and Academic Recognition in the EU

    Science.gov (United States)

    West, Anne; Barham, Eleanor

    2009-01-01

    This paper explores the relationship between student mobility, qualifications and academic recognition within Europe. It provides an outline of supranational legal instruments and policies in relation to academic recognition and student mobility. It then examines some of the difficulties associated with the different concepts underpinning the…

  8. 78 FR 65034 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2013-10-30

    ...-0190] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor Carrier... against persons with insulin- treated diabetes mellitus (ITDM) operating commercial motor vehicles (CMVs... individuals listed in this notice have recently requested such an exemption from the diabetes prohibition in...

  9. 78 FR 65031 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2013-10-30

    ...-2013-0182] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor... its decision to exempt 19 individuals from its rule prohibiting persons with insulin-treated diabetes... receipt of Federal diabetes exemption applications from 19 individuals and requested comments from the...

  10. 78 FR 76398 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2013-12-17

    ...-2013-0188] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor... its decision to exempt 29 individuals from its rule prohibiting persons with insulin-treated diabetes... receipt of Federal diabetes exemption applications from 29 individuals and requested comments from the...

  11. 78 FR 65754 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2013-11-01

    ...-2013-0183] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor...-treated diabetes mellitus (ITDM) from operating commercial motor vehicles (CMVs) in interstate commerce... a notice of receipt of Federal diabetes exemption applications from 23 individuals and requested...

  12. 78 FR 7855 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2013-02-04

    ...-2012-0349] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor... its decision to exempt 12 individuals from its rule prohibiting persons with insulin-treated diabetes... receipt of Federal diabetes exemption applications from 12 individuals and requested comments from the...

  13. 78 FR 76400 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2013-12-17

    ...-2013-0189] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor...-treated diabetes mellitus (ITDM) from operating commercial motor vehicles (CMVs) in interstate commerce... a notice of receipt of Federal diabetes exemption applications from 15 individuals and requested...

  14. 78 FR 77784 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2013-12-24

    ...-2013-0184] [4910-EX-P] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY...-treated diabetes mellitus (ITDM) from operating commercial motor vehicles (CMVs) in interstate commerce... a notice of receipt of Federal diabetes exemption applications from 26 individuals and requested...

  15. 78 FR 56988 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2013-09-16

    ...-0186] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor Carrier... against persons with insulin-treated diabetes mellitus (ITDM) operating commercial motor vehicles (CMVs... individuals listed in this notice have recently requested such an exemption from the diabetes prohibition in...

  16. 78 FR 60014 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2013-09-30

    ...-2013-0020] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor... its decision to exempt 16 individuals from its rule prohibiting persons with insulin-treated diabetes... of Federal diabetes exemption applications from 16 individuals and requested comments from the public...

  17. 78 FR 64267 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2013-10-28

    ...-0184] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor Carrier... against persons with insulin- treated diabetes mellitus (ITDM) operating commercial motor vehicles (CMVs... such an exemption from the diabetes prohibition in 49 CFR 391.41(b)(3), which applies to drivers of...

  18. 76 FR 9867 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2011-02-22

    ...-2010-0427] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor... diabetes mellitus (ITDM) from operating commercial motor vehicles (CMVs) in interstate commerce. The....pdf . Background On January 10, 2011, FMCSA published a notice of receipt of Federal diabetes...

  19. 78 FR 50140 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2013-08-16

    ...-2013-0019] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor... its decision to exempt 24 individuals from its rule prohibiting persons with insulin-treated diabetes... of Federal diabetes exemption applications from 24 individuals and requested comments from the public...

  20. 78 FR 1926 - Qualification of Drivers; Exemption Applications; Diabetes Mellitus

    Science.gov (United States)

    2013-01-09

    ...-2012-0347] Qualification of Drivers; Exemption Applications; Diabetes Mellitus AGENCY: Federal Motor... its decision to exempt 12 individuals from its rule prohibiting persons with insulin-treated diabetes....pdf . Background On October 31, 2012, FMCSA published a notice of receipt of Federal diabetes...