Characterization Of The As-Received Sludge Batch 9 Qualification Sample (Htf-51-15-81)

Energy Technology Data Exchange (ETDEWEB)

Pareizs, J. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2015-09-30

Savannah River National Laboratory (SRNL) personnel have been requested to qualify the next sludge batch (Sludge Batch 9 – SB9) for processing at the Defense Waste Processing Facility (DWPF). To accomplish this task, Savannah River Remediation (SRR) has sent SRNL a 3-L slurried sample of Tank 51H (HTF-51-15-81) to be characterized, washed, and then used in a lab-scale demonstration of the DWPF flowsheet (potentially after combining with Tank 40H sludge). This report documents the first steps of the qualification process – characterization of the as-received Tank 51H qualification sample. These results will be used to support a reprojection of SB9 by SRR from which final Tank 51H washing, frit development, and Chemical Processing Cell (CPC) activities will be based.

Logic qualification of FPGA-based safety-related I and C systems

International Nuclear Information System (INIS)

Hayashi, Toshifumi; Oda, Naotaka; Ito, Toshiaki; Miyazaki, Tadashi; Haren, Yasuhiko

2009-01-01

We established a logic qualification method for FPGA-Based I and C safety-related use in Nuclear Power Plants Systems. The FPGA is a programmable logic device and has advantages that the programming is rigorous, simple verifiable, and the technology is stable. However, logic qualification of FPGA had been an issue to be solved when it is used in the safety-related systems, because FPGA is relatively new technology for the nuclear power industry. We employed a software-life cycle approach, because its development process is similar to that of conventional computer-based systems. There are some differences between the FPGA-Based systems and the computer-based systems in the implementation and integration of logic. We examined the FPGA logic implementation and integration process to identify any FPGA-Based system specific hazards. The identified hazards are (1) small logic errors, (2) timing errors, (3) logic synthesis errors, (4) place and route errors, and (5) logic embedding errors. We took the appropriate countermeasures to mitigate these hazards, and employed this logic qualification method in the qualification of the Power Range Monitor System for BWR Power Plants. (author)

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.

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

International Nuclear Information System (INIS)

Jordan, W.G.

1978-01-01

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

The HTR modular power reactor system. Qualification of fuel elements and materials

International Nuclear Information System (INIS)

Heidenreich, U.; Breitling, H.; Nieder, R.; Ohly, W.; Mittenkuehler, A.; Ragoss, H.; Seehafer, H.J.; Wirtz, K.; Serafin, N.

1989-01-01

For further development of the HTR modular power reactor system (HTR-M-KW), the project activities for 'Qualification of fuel elements and materials' reported here cover the work for specifying the qualifications to be met by metallic and ceramic materials, taking into account the design-based requirements and the engineered safety requirements. The fission product retention data determined for the HTR modular reactor fuel elements could be better confirmed by evaluation of the experiments, and have been verified by various calculation methods for different operating conditions. The qualification of components was verified by strength analyses including a benchmark calculation for specified normal operation and emergencies; the results show a convenient behaviour of the components and their materials. In addition, a fuel element burnup measuring system was designed that applies Cs-137 gamma spectroscopy; its feasibility was checked by appropriate analyses, and qualification work is in progress. The installation of a prototype measurement system is the task for project No. 03 IAT 211. (orig.) [de

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

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.)

Qualification of the flight-critical AFTI/F-16 digital flight control system. [Advanced Fighter Technology Integration

Science.gov (United States)

Mackall, D. A.; Ishmael, S. D.; Regenie, V. A.

1983-01-01

Qualification considerations for assuring the safety of a life-critical digital flight control system include four major areas: systems interactions, verification, validation, and configuration control. The AFTI/F-16 design, development, and qualification illustrate these considerations. In this paper, qualification concepts, procedures, and methodologies are discussed and illustrated through specific examples.

Qualification of C and I systems using new technology components

International Nuclear Information System (INIS)

Gossner, S.

1986-01-01

Whereas one may find an almost complete change-over to microprocessor based automation and supervision systems in numerous industrial fields, a similar development did not yet take place in C and I systems of West German nuclear power plants. Neglecting some unimportant exceptions C and I systems of West German nuclear power plants are fully conventional. This situation, however, will not last forever. There is a growing understanding that by means of microcomputer-based C and I equipment it will be possible: to solve many problems more exactly, e.g. calculations of reactor power, power distribution, water levels, DNBR; to reduce the number of detailed informations and alarms concentrated in control rooms and control stations and to condense these informations into easily to understand pictorial displays, e.g. surveillance or trend pictures on graphic CRT-display units; to reduce cabling amount by using sequential data transmission, e.g. by means of bus-systems. It's clear in the near future microprocessors will enter not only operational C and I equipment but C and I systems important to safety as well. Therefore it's high time to analyse existing design and qualification requirements, qualification methods and qualification procedures whether or not to be suitable and sufficient

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

International Nuclear Information System (INIS)

Anon.

1980-01-01

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

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

International Nuclear Information System (INIS)

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

1997-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

Peters, T.; Fink, S.

2011-06-22

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

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

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

Development, structure and qualification of a new digital instrumentation and control system

International Nuclear Information System (INIS)

Hofmann, H.; Sauer, H.J.

1991-01-01

Introduction of digital instrumentation and control in nuclear power plants is characterized by the need to meet numerous requirements concerning reliability, ergonomic design of the main control room and comprehensive qualification. The system described here is distinguished by a hierarchical and modular structure, being redundant throughout. Ergonomic considerations dominate the layout of the screen-based main control room. Powerful computer-aided engineering tools are employed for planning of the entire system and for generation of the user software. Qualification is performed in step with the development of the system, based on the applicable national and international rules and regulations and in close cooperation with an independent expert. (orig.) [de

Qualification, certification and training systems of a Japanese nuclear power plant supplier

International Nuclear Information System (INIS)

Yoshijima, S.; Tomita, J.; Yoneda, Y.

1982-01-01

Training and indoctrination of personnel are very important for performing quality assurance activities in nuclear power plants. The paper presents policies, procedures and practices with regard to a training system for site construction workers, a training system for plant operation personnel at a special facility, and services and activities for operating plants. The training system for site workers and technicians offers basic training for all workers, and special training and qualification for field welders, cable-termination workers and non-destructive examination personnel. In addition to the qualification system for field welders applied by the regulatory body, a privat-company qualification system exists. Also, a training centre for BWR operators has been established. This facility has a simulator duplicating the main control room of an actual plant and a computer-assisted instruction system. Standard training courses, short-term basic courses, re-training courses, group training courses and special training courses are held at the training centre. Finally, the services and activities performed by Toshiba Corporation for operating plants are described. These activities of the plant supplier aim at keeping up and further enhancing the safety and reliability of operating plants and mainly consist of: (1) collection and evaluation of plant operation data, with re-evaluation and improvement of systems and components; (2) development of new maintenance techniques; (3) development of measures for reducing annual outage periods; and (4) plant emergency preparedness. (author)

Results of initial analyses of the salt (macro) batch 11 Tank 21H qualification samples

Energy Technology Data Exchange (ETDEWEB)

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

2017-10-23

Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Interim Salt Disposition Project (ISDP) Salt (Macro) Batch 11 for processing through the Actinide Removal Process (ARP) and the Modular Caustic-Side Solvent Extraction Unit (MCU). This document reports the initial results of the analyses of samples of Tank 21H. Analysis of the Tank 21H Salt (Macro) Batch 11 composite sample indicates that the material does not display any unusual characteristics or observations, such as floating solids, the presence of large amounts of solids, or unusual colors. Further sample results will be reported in a future document. This memo satisfies part of Deliverable 3 of the Technical Task Request (TTR).

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. ...

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)

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. ...

Design and qualification of HPD based designs for safety systems

International Nuclear Information System (INIS)

Sharma, Mukesh Kr.; Chavan, Madhavi A.; Sawhney, Pratibha A.; Mohanty, Ashutos; John, Ajith K.; Ganesh, G.

2014-01-01

Field Programmable Gate Arrays (FPGA) and Complex Programmable Logic Devices (CPLD) are increasingly being used in C and I system of NPPs. The function of such an integrated circuit is not defined by the supplier of the physical component or micro-electronic technology but by the C and I designer. The hardware subsystems implemented in these devices typically use Hardware Description Language (HDL) like VHDL or Verilog to describe the functionality at the design entry level. These circuits are commonly known as 'HDL-Programmed Devices', (HPD). RCnD has developed a set of hardware boards to be used in next generation C and I systems. The boards have been designed based on present day technology and components. The intelligence of these boards has been implemented in HPDs (FPGA/CPLD) using VHDL. Since these boards are used in the safety and safety related systems, they have undergone a rigorous V and V process and qualification tests. This paper discusses the design attributes and qualification of these HPD based designs for nuclear class safety systems. (author)

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. ...

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

Seismic qualification of the rotary relay for use in the solid state protection system

International Nuclear Information System (INIS)

Vogeding, E.L.; Jarecki, S.J.

1976-01-01

The seismic qualification of a rotary relay that can be used as a replacement for the type of relay located in the output section of the Solid State Protection System is described. The qualification test results indicate that the tested relays did not exhibit any contact bounce or abnormal operation; they performed satisfactorily before, during, and after the simulated seismic vibration tests

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

Energy Technology Data Exchange (ETDEWEB)

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

2017-02-23

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

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)

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

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)

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...

WTP Waste Feed Qualification: Hydrogen Generation Rate Measurement Apparatus Testing Report

Energy Technology Data Exchange (ETDEWEB)

Stone, M. E. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Newell, J. D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Smith, T. E. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Pareizs, J. M. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2016-06-01

The generation rate of hydrogen gas in the Hanford tank waste will be measured during the qualification of the staged tank waste for processing in the Hanford Tank Waste Treatment and Immobilization Plant. Based on a review of past practices in measurement of the hydrogen generation, an apparatus to perform this measurement has been designed and tested for use during waste feed qualification. The hydrogen generation rate measurement apparatus (HGRMA) described in this document utilized a 100 milliliter sample in a continuously-purged, continuously-stirred vessel, with measurement of hydrogen concentration in the vent gas. The vessel and lid had a combined 220 milliliters of headspace. The vent gas system included a small condenser to prevent excessive evaporative losses from the sample during the test, as well as a demister and filter to prevent particle migration from the sample to the gas chromatography system. The gas chromatograph was an on line automated instrument with a large-volume sample-injection system to allow measurement of very low hydrogen concentrations. This instrument automatically sampled the vent gas from the hydrogen generation rate measurement apparatus every five minutes and performed data regression in real time. The fabrication of the hydrogen generation rate measurement apparatus was in accordance with twenty three (23) design requirements documented in the conceptual design package, as well as seven (7) required developmental activities documented in the task plan associated with this work scope. The HGRMA was initially tested for proof of concept with physical simulants, and a remote demonstration of the system was performed in the Savannah River National Laboratory Shielded Cells Mockup Facility. Final verification testing was performed using non-radioactive simulants of the Hanford tank waste. Three different simulants were tested to bound the expected rheological properties expected during waste feed qualification testing. These

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

Analytical considerations in the code qualification of piping systems

International Nuclear Information System (INIS)

Antaki, G.A.

1995-01-01

The paper addresses several analytical topics in the design and qualification of piping systems which have a direct bearing on the prediction of stresses in the pipe and hence on the application of the equations of NB, NC and ND-3600 of the ASME Boiler and Pressure Vessel Code. For each of the analytical topics, the paper summarizes the current code requirements, if any, and the industry practice

Environmental qualification and functional issues for microprocessor-based reactor protection systems

International Nuclear Information System (INIS)

Korsah, K.; Kisner, R.; Wood, R.T.; Antonescu, C.

1992-01-01

Issues of obsolescence and lack of intrastructural support in (analog) spare parts, coupled with the potential benefits of digital systems, are driving the nuclear industry to retrofit analog instrumentation and control (I ampersand C) systems with digital and microprocessor-based systems. This movement away from analog can be expected to increase in advanced light-water reactors (ALWRs), which will make extensive use of fiber optic transmission, multiplexing techniques, and microprocessor-based technology. Although these technologies have several advantages and, in fact, have been in widespread use in the non-nuclear industry for several years, their application to safety-related systems in nuclear power plants raises key issues relating to the systems' environmental and functional reliability. For example, does the new hardware introduce additional system aging degradation mechanisms that could adversely impact the safety of the plant? Do the systems introduce the possibility of new and different malfunction scenarios or increase the probability of common-mode failures that could reduce the reliability of the safety system?. Are current environmental qualification standards adequate for microprocessor-based I ampersand C systems? Accordingly in 1991 the Nuclear Regulatory Commission (NRC) initiated the qualification of advanced Instrumentation and Control Systems program at ORNL to investigate issues that may arise with the use of advanced digital I ampersand C in ALWRs. The results of our studies to date are summarized in this paper

Qualification issues for advanced light-water reactor protection systems

International Nuclear Information System (INIS)

Korsah, K.; Clark, R.L.; Antonescu, C.

1993-01-01

The instrumentation and control (I ampersand C) systems in advanced reactors will make extensive use of digital controls, microprocessors, multiplexing, and fiber optic transmission. Elements of these advances in I ampersand C have been implemented on some current operating plants. However, the widespread use of the above technologies, as well as the use of artificial intelligence with minimum reliance on human operator control of reactors, highlights the need to develop standards for qualifying the I ampersand C used in the next generation of nuclear power plants. As a first step in this direction, the protection system I ampersand C for present-day plants was compared to that proposed for advanced light-water reactors (ALWRs). An evaluation template was developed by assembling a configuration of a safety channel instrument string for a generic ALWR, then comparing the impact of environmental stressors on that string to their effect on an equivalent instrument string from an existing light-water reactor. The template was then used to suggest a methodology for the qualification of microprocessor-based protection systems. The methodology identifies standards/regulatory guides (or lack thereof) for the qualification of microprocessor-based safety I ampersand C systems. This approach addresses in part issues raised in NRC policy document SECY-91-292, which recognizes that advanced I ampersand C systems for the nuclear industry are ''being developed without consensus standards. as the technology available for design is ahead of the technology that is well understood through experience and supported by application standards.''

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

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

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

International Nuclear Information System (INIS)

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

2010-01-01

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

SLUDGE BATCH 5 ACCEPTANCE EVALUATION RADIONUCLIDE CONCENTRATIONS IN TANK 51 SB5 QUALIFICATION SAMPLE PREPARED AT SRNL

International Nuclear Information System (INIS)

Bannochie, C; Ned Bibler, N; David Diprete, D

2008-01-01

Presented in this report are radionuclide concentrations required as part of the program of qualifying Sludge Batch Five (SB5) for processing in the Defense Waste Processing Facility (DWPF). Part of this SB5 material is currently in Tank 51 being washed and prepared for transfer to Tank 40. The acceptance evaluation needs to be completed prior to the transfer of the material in Tank 51 to Tank 40 to complete the formation of SB5. The sludge slurry in Tank 40 has already been qualified for DWPF and is currently being processed as SB4. The radionuclide concentrations were measured or estimated in the Tank 51 SB5 Qualification Sample prepared at Savannah River National Laboratory (SRNL). This sample was prepared from the three liter sample of Tank 51 sludge slurry taken on March 21, 2008. The sample was delivered to SRNL where it was initially characterized in the Shielded Cells. Under direction of the Liquid Waste Organization it was then modified by five washes, six decants, an addition of Pu/Be from Canyon Tank 16.4, and an addition of NaNO2. This final slurry now has a composition expected to be similar to that of the slurry in Tank 51 after final preparations have been made for transfer of that slurry to Ta Determining the radionuclide concentrations in this Tank 51 SB5 Qualification Sample is part of the work requested in Technical Task Request (TTR) No. HLW-DWPF-TTR-2008-0010. The work with this qualification sample is covered by a Task Technical and Quality Assurance Plan and an Analytical Study Plan. The radionuclides included in this report are needed for the DWPF Radiological Program Evaluation, the DWPF Waste Acceptance Criteria (TSR/WAC) Evaluation, and the DWPF Solid Waste Characterization Program (TTR Task 2). Radionuclides required to meet the Waste Acceptance Product Specifications (TTR Task 5) will be measured at a later date after the slurry from Tank 51 has been transferred to Tank 40. Then a sample of the as-processed SB5 will be taken and

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

Energy Technology Data Exchange (ETDEWEB)

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

2015-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2015-01-13

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

Qualification of UT methods and systems used for in-service inspections of VVER 440 vessels

International Nuclear Information System (INIS)

Skala, Z.; Vit, J.

2003-01-01

SKODA JS has been performing automated in-service inspections VVER reactor pressure vessels for more than twenty years. All of these inspections were performed by ultrasonic pulse echo method, combined from 1996 with eddy current testing. The Time of Flight Diffraction Method (TOFD) is one of modern methods of ultrasonic testing. The accuracy of sizing the through wall extent of a flaw by TOFD is much better than the accuracy achievable by the pulse echo method. A series of laboratory tests were performed by SKODA JS and confirmed the suitability of TOFD method for VVER reactor parts testing. The Czech Atomic law demands the qualification of systems and methods used for the in-service inspections of nuclear reactors. The qualification is done in accordance with ENIQ methodology and consists of preparation of the Technical Justification and practical tests made under the surveillance of Qualification Body. SKODA JS intends to qualify systems and methods used for the automated ultrasonic testing of VVER 440 and VVER 1000 reactor components from the inner as well as from the outer surface. The accuracy of the flaw through wall extent sizing by TOFD was confirmed by the qualification of methods and systems used for the testing of VVER 440 vessel circumferential weld and so the TOFD method shall be used routinely by SKODA JS for the inspection of vessel circumferential welds root area and for sizing of flaws exceeding the acceptance level. (author)

BWR reactor water cleanup system flexible wedge gate isolation valve qualification and high energy flow interruption test

International Nuclear Information System (INIS)

DeWall, K.G.; Steele, R. Jr.

1989-10-01

This report presents the results of research performed to develop technical insights for the NRC effort regarding Generic Issue 87, ''Failure of HPCI Steam Line Without Isolation.'' Volume III of this report contains the data and findings from the original research performed to assess the qualification of the valves and reported in EGG-SSRE-7387, ''Qualification of Valve Assemblies in High Energy BWR Systems Penetrating Containment.'' We present the original work here to complete the documentation trail. The recommendations contained in Volume III of this report resulted in the test program described in Volume I and II. The research began with a survey to characterize the population of normally open containment isolation valves in those process lines that connect to the primary system and penetrate containment. The qualification methodology used by the various manufacturers identified in the survey is reviewed and deficiencies in that methodology are identified. Recommendations for expanding the qualification of valve assemblies for high energy pipe break conditions are presented. 11 refs., 1 fig., 2 tabs

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)

Qualification of McCARD/MASTER Code System for Yonggwang Unit 4

International Nuclear Information System (INIS)

Park, Ho Jin; Shim, Hyung Jin; Joo, Han Gyu; Kim, Chang Hyo

2011-01-01

Recently, we have developed the new two-step procedure based on the Monte Carlo (MC) methods. In this procedure, one can generate the few group constants including the few-group diffusion constants by the MC method augmented by the critical spectrum, which is provided by the solution to the homogeneous 0-dimensional B1 equation. In order to examine the qualification of the few-group constants generated by MC method, we combine MASTER with McCARD to form McCARD/MASTER code system for two-step core neutronics calculations. In the fictitious PWR system problems, the core design parameters calculated by the two-step McCARD/MASTER analysis agree well with those from the direct MC calculations. In this paper, a neutronic design analysis for the initial core of Yonggwang Nuclear Unit 4 (YGN4) is conducted using McCARD/MASTER two-step procedure to examine the qualification of two group constants from McCARD in terms of a real PWR core problem. To compare with the results, the nuclear design report and measured data are chosen as the reference solutions

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2013-08-08

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

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

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.)

NFC based Inspection and Qualification Management (NIQM) System Preventing Counterfeit and Fraudulent Item

International Nuclear Information System (INIS)

Chang, Choong Koo; Kim, Young Joo

2013-01-01

Design, manufacturing, fabrication, transportation and installation of the devices and equipment for nuclear power plants shall be conducted under the thorough quality assurance program for the nuclear safety. However, from late in the 1980s, NRC began to issue a number of communications alerting licenses to issues involving counterfeit and fraudulent items. A number of incidents identified by the NRC in the 1980s and 1990s catalyzed the US nuclear industry to adopt standard precautions to guard against counterfeit items. The purpose of this paper is to develop the NFC (Near Field Communication) based Inspection and Qualification Management(NIQM) system preventing counterfeit and fraudulent items. NFC is one of the latest wireless communication technologies. As a short-range wireless connectivity technology, NFC offers safe-yet simple and intuitive-communication between electronic devices. As described above, NFC technology can be applied to the inspection and qualification management system very effectively to prevent counterfeit and fraudulent items. In addition, NIQM system can use existing data and information through the interface with legacy system

NFC based Inspection and Qualification Management (NIQM) System Preventing Counterfeit and Fraudulent Item

Energy Technology Data Exchange (ETDEWEB)

Chang, Choong Koo; Kim, Young Joo [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

2013-10-15

Design, manufacturing, fabrication, transportation and installation of the devices and equipment for nuclear power plants shall be conducted under the thorough quality assurance program for the nuclear safety. However, from late in the 1980s, NRC began to issue a number of communications alerting licenses to issues involving counterfeit and fraudulent items. A number of incidents identified by the NRC in the 1980s and 1990s catalyzed the US nuclear industry to adopt standard precautions to guard against counterfeit items. The purpose of this paper is to develop the NFC (Near Field Communication) based Inspection and Qualification Management(NIQM) system preventing counterfeit and fraudulent items. NFC is one of the latest wireless communication technologies. As a short-range wireless connectivity technology, NFC offers safe-yet simple and intuitive-communication between electronic devices. As described above, NFC technology can be applied to the inspection and qualification management system very effectively to prevent counterfeit and fraudulent items. In addition, NIQM system can use existing data and information through the interface with legacy system.

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

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

International Nuclear Information System (INIS)

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

2013-01-01

This paper describes the software qualification activities for the safety-critical software of the digital reactor safety system in nuclear power plants. The main activities of the software qualification processes are the preparation of software planning documentations, verification and validation (V and V) of the software requirements specifications (SRS), software design specifications (SDS) and codes, and the testing of the integrated software and integrated system. Moreover, the software safety analysis and software configuration management are involved in the software qualification processes. The V and V procedure for SRS and SDS contains a technical evaluation, licensing suitability evaluation, inspection and traceability analysis, formal verification, software safety analysis, and an evaluation of the software configuration management. The V and V processes for the code are a traceability analysis, source code inspection, test case and test procedure generation. Testing is the major V and V activity of the software integration and system integration phases. The software safety analysis employs a hazard operability method and software fault tree analysis. The software configuration management in each software life cycle is performed by the use of a nuclear software configuration management tool. Through these activities, we can achieve the functionality, performance, reliability, and safety that are the major V and V objectives of the safety-critical software in nuclear power plants. (author)

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

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.

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

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

Boat sampling technique for assessment of ageing of components

International Nuclear Information System (INIS)

Kumar, Kundan; Shyam, T.V.; Kayal, J.N.; Rupani, B.B.

2006-01-01

Boat sampling technique (BST) is a surface sampling technique, which has been developed for obtaining, in-situ, metal samples from the surface of an operating component without affecting its operating service life. The BST is non-destructive in nature and the sample is obtained without plastic deformation or without thermal degradation of the parent material. The shape and size of the sample depends upon the shape of the cutter and the surface geometry of the parent material. Miniature test specimens are generated from the sample and the specimens are subjected to various tests, viz. Metallurgical Evaluation, Metallographic Evaluation, Micro-hardness Evaluation, sensitisation test, small punch test etc. to confirm the integrity and assessment of safe operating life of the component. This paper highlights design objective of boat sampling technique, description of sampling module, sampling cutter and its performance evaluation, cutting process, boat samples, operational sequence of sampling module, qualification of sampling module, qualification of sampling technique, qualification of scooped region of the parent material, sample retrieval system, inspection, testing and examination to be carried out on the boat samples and scooped region. (author)

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

International Nuclear Information System (INIS)

Anon.

1992-01-01

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

Qualification of a Human-System Interface to Meet IEC 61513

International Nuclear Information System (INIS)

Malcom, Scott; Kim, Sun Ho; Macdonald, Marienna

2011-01-01

This paper describes the steps Atomic Energy of Canada Limited (AECL TM ) undertook to qualify its Advanced Control Centre Information System (ACCIS TM ) to meet the requirements of IEC 61513. It will address the different strategies used for software versus hardware. As well, the paper will discuss the steps that have been taken to qualify third-party commercial-off-the-shelf products that are used in conjunction with a qualified product. ACCIS is a display, monitoring and supervisory control system that is designed to be readily configurable and scalable to satisfy the display requirements for single functions or complex industrial plant systems. The ACCIS software services are configured and deployed across a distributed computing environment to meet the needs of a given implementation. From small single-node applications to large, complex, multi-node configurations, system behaviour is largely configured via data specifications. This design reduces the costs associated with development of custom software and allows the user to have greater control of behavioral attributes of the system, including data sampling and storage rates, the appearance and behaviour of displays, alarm annunciation features, and the configuration of system health checks. Utilities and regulators are demanding that these computer-based systems are developed and maintained with an appropriate amount of engineering rigor. To meet this challenge, AECL is qualifying its ACCIS HSI, which is intended for use in all future CANada Nuclear Deuterium (CANDU TM ) nuclear power plants, to meet the requirements of the International Electrotechnical Commission's (IEC) standard for instrumentation and control systems important to safety, IEC 61513. Transitioning to the IEC standards has not been without its challenges. While AECL previously used a software development model very similar to the IEC model, absorbing the volume of the IEC standards and understanding how they should be applied has been

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

Functional issues and environmental qualification of digital protection systems of advanced light-water nuclear reactors

Energy Technology Data Exchange (ETDEWEB)

Korsah, K.; Clark, R.L.; Wood, R.T. [Oak Ridge National Lab., TN (United States)

1994-04-01

Issues of obsolescence and lack of infrastructural support in (analog) spare parts, coupled with the potential benefits of digital systems, are driving the nuclear industry to retrofit analog instrumentation and control (I&C) systems with digital and microprocessor-based systems. While these technologies have several advantages, their application to safety-related systems in nuclear power plants raises key issues relating to the systems` environmental qualification and functional reliability. To bound the problem of new I&C system functionality and qualification, the authors focused this study on protection systems proposed for use in ALWRs. Specifically, both functional and environmental qualification issues for ALWR protection system I&C were addressed by developing an environmental, functional, and aging data template for a protection division of each proposed ALWR design. By using information provided by manufacturers, environmental conditions and stressors to which I&C equipment in reactor protection divisions may be subjected were identified. The resulting data were then compared to a similar template for an instrument string typically found in an analog protection division of a present-day nuclear power plant. The authors also identified fiber-optic transmission systems as technologies that are relatively new to the nuclear power plant environment and examined the failure modes and age-related degradation mechanisms of fiber-optic components and systems. One reason for the exercise of caution in the introduction of software into safety-critical systems is the potential for common-cause failure due to the software. This study, however, approaches the functionality problem from a systems point of view. System malfunction scenarios are postulated to illustrate the fact that, when dealing with the performance of the overall integrated system, the real issues are functionality and fault tolerance, not hardware vs. software.

Functional issues and environmental qualification of digital protection systems of advanced light-water nuclear reactors

International Nuclear Information System (INIS)

Korsah, K.; Clark, R.L.; Wood, R.T.

1994-04-01

Issues of obsolescence and lack of infrastructural support in (analog) spare parts, coupled with the potential benefits of digital systems, are driving the nuclear industry to retrofit analog instrumentation and control (I ampersand C) systems with digital and microprocessor-based systems. While these technologies have several advantages, their application to safety-related systems in nuclear power plants raises key issues relating to the systems' environmental qualification and functional reliability. To bound the problem of new I ampersand C system functionality and qualification, the authors focused this study on protection systems proposed for use in ALWRs. Specifically, both functional and environmental qualification issues for ALWR protection system I ampersand C were addressed by developing an environmental, functional, and aging data template for a protection division of each proposed ALWR design. By using information provided by manufacturers, environmental conditions and stressors to which I ampersand C equipment in reactor protection divisions may be subjected were identified. The resulting data were then compared to a similar template for an instrument string typically found in an analog protection division of a present-day nuclear power plant. The authors also identified fiber-optic transmission systems as technologies that are relatively new to the nuclear power plant environment and examined the failure modes and age-related degradation mechanisms of fiber-optic components and systems. One reason for the exercise of caution in the introduction of software into safety-critical systems is the potential for common-cause failure due to the software. This study, however, approaches the functionality problem from a systems point of view. System malfunction scenarios are postulated to illustrate the fact that, when dealing with the performance of the overall integrated system, the real issues are functionality and fault tolerance, not hardware vs. software

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

Development of the personnel training and qualification system of the Russian Federation Nuclear Regulatory Authority

International Nuclear Information System (INIS)

Kapralov, E.; Kapralov, Y.; Kozlov, V.

2006-01-01

The new personnel training and qualification system is being developed for russian regulatory body, having a very big number of employees and invited experts and widly territorially distributed structure. (author)

Space optical materials and space qualification of optics; Proceedings of the Meeting, Orlando, FL, Mar. 30, 31, 1989

Science.gov (United States)

Hale, Robert R.

1989-10-01

The present conference on space optical materials discusses current metals and nonmetals-related processing R&D efforts, investigations of space optical effects, and the spaceborne qualification of optical components and systems. Attention is given to CVD SiC for optical applications, optical materials for space-based lasers, the high-efficiency acoustooptic and optoelectronic crystalline material Tl3AsSe3, HIPed Be for low-scatter cryogenic optics, durable solar-reflective surfacing for Be optics, thermal effects on Be mirrors, contamination effects on optical surfaces in the monolayer regime, and IR background signature survey experiment results. Also discussed are the contamination-control program for the EUE instrument, an optical multipass radiation system for the heating of levitated samples, optical sample-position sensing for electrostatic levitation, and the qualification of space lighting systems.

Remote Qualification of HLS and WPS Systems in the LHC Tunnel

CERN Document Server

Mainaud Durand, Helene; Marin, Antonio; Rousseau, Michel; Sosin, Mateusz

2014-01-01

The position of the inner triplets of the LHC is monitored using Hydrostatic Levelling System (HLS) and Wire Positioning System (WPS). A regulation of these systems is needed to guarantee the sensors’ function. Such a regulation was done in-situ up to now, but the level of residual radiation at the level of the inner triplets will significantly increase with the next steps of LHC operation. Two systems have been designed to perform such a remote qualification: a filling/purging system for the HLS system and a wire displacer system for the WPS. In the paper, the requirements and the solutions proposed are described, with the emphasis on the conceptual design and the results obtained.

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.)

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.)

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...

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

International Nuclear Information System (INIS)

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

1987-01-01

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

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

Qualification and issues with space flight laser systems and components

Science.gov (United States)

Ott, Melanie N.; Coyle, D. B.; Canham, John S.; Leidecker, Henning W., Jr.

2006-02-01

The art of flight quality solid-state laser development is still relatively young, and much is still unknown regarding the best procedures, components, and packaging required for achieving the maximum possible lifetime and reliability when deployed in the harsh space environment. One of the most important issues is the limited and unstable supply of quality, high power diode arrays with significant technological heritage and market lifetime. Since Spectra Diode Labs Inc. ended their involvement in the pulsed array business in the late 1990's, there has been a flurry of activity from other manufacturers, but little effort focused on flight quality production. This forces NASA, inevitably, to examine the use of commercial parts to enable space flight laser designs. System-level issues such as power cycling, operational derating, duty cycle, and contamination risks to other laser components are some of the more significant unknown, if unquantifiable, parameters that directly effect transmitter reliability. Designs and processes can be formulated for the system and the components (including thorough modeling) to mitigate risk based on the known failures modes as well as lessons learned that GSFC has collected over the past ten years of space flight operation of lasers. In addition, knowledge of the potential failure modes related to the system and the components themselves can allow the qualification testing to be done in an efficient yet, effective manner. Careful test plan development coupled with physics of failure knowledge will enable cost effect qualification of commercial technology. Presented here will be lessons learned from space flight experience, brief synopsis of known potential failure modes, mitigation techniques, and options for testing from the system level to the component level.

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

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.

Seismic qualification of a commercial grade emergency diesel generator system in high seismic zones

International Nuclear Information System (INIS)

Khan, Mohsin R.; Chen, Wayne W.H.; Chu, Winnie S.

2004-01-01

The paper presents the seismic qualification of a commercially procured emergency diesel generator (EDG) system for use in a nuclear power plant. Response spectrum analyses of finite element models, validated using in situ vibration test data, were performed to qualify the skid and floor mounted mechanical components whose functional capacity and structural integrity can be analyzed. Time history analyses of these models were also performed to obtain the amplified response spectra for seismic testing of small valves, electrical and electro-mechanical components whose functional capacity can not be analyzed to establish the seismic qualification. The operational loads were obtained by in-plant vibration monitoring. Full scale shake table testing was performed for auxiliary electrical cabinets. It is concluded that with some minor structural modifications, a commercial grade EDG system can be qualified for safety-related applications in nuclear power plants located in high seismic zones. (author)

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

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…

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

International Nuclear Information System (INIS)

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

1977-01-01

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

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.

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

Development of equipment qualification requirements for NPP instrumentation and control systems

International Nuclear Information System (INIS)

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

2012-01-01

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

Qualification of NEXUS/ANC Nuclear Design System for PWR Analyses

International Nuclear Information System (INIS)

Mayhue, Larry; Milanova, Radka; Huria, Harish; Zhang, Baocheng; Franceschini, Fausto; Ouisloumen, Mohamed; Mueller, Erwin; Forslun Guimaraes, Petri

2008-01-01

NEXUS is a new cross section and nuclear data generation system for core simulators developed by Westinghouse. This system generates once-through, full temperature range nuclear data for both PWRs and BWRs. The system has been implemented for PWRs in the NEXUS/ANC code system. A brief description of the methodology and the codes comprising this system is presented. The qualification for NEXUS/ANC has been completed and a summary of some of the results is presented for 10 plants and 45 cycles of operation. These results include startup data and at-power axial offset performance. Results for low temperature calculations are also presented. The NEXUS/ANC system includes new methodology to cover the operation of AP1000 plants including a new pin power recovery method and a method to capture the effects of control rod depletion. A brief summary of these methods is also presented. (authors)

Generic test procedure for the qualification of a nuclear emergency generator

International Nuclear Information System (INIS)

Simonis, J.C.; Bowman, S.W.

1985-01-01

This paper describes the proposed analytical and experimental procedures for the qualification of the standby generators and exciters used in the Emergency Diesel Generator Systems in a nuclear power plant. The components which require qualification are identified through a failure mode analysis of the systems conducted using engineering drawings updated to include all field changes. The qualification of each component includes the margins given in IEEE Std. 323-1974, ''Qualifying Class 1E Equipment for Nuclear Power Generating Stations.'' These margins are combined with the plant specific data to define an enveloping set of environmental parameters. This set of enveloping parameters, plus margin, form the bases for the analysis or test qualification tasks. Proposed qualification of the composite electrical insulation systems used in the generator and exciter on the form or random wound coils is by traceable testing. However, before testing the thermal and radiation degradation data used in the design of the generator and exciter are evaluated to identify if these data are sufficiently traceable to eliminate the need for additional insulation tests. The required tests are guided by applicable standards

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)

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...

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)

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).

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).

Teachers' Educational Qualification, Rank Level, Working Duration, Age, Work Motivation and Work Effectiveness

OpenAIRE

Wiyono, Bambang Budi

2009-01-01

Teachers’ Educational Qualification, Rank Level, Working Duration, Age, Working Mo­tivation, and Working Effectiveness The study investigated the effects of educational qualification, rank level, working duration and age on the elementary school teachers’ working motivation and working ef­fectiveness. The sample of the study consisted of 438 elementary school teachers in Malang which were selected through cluster sampling technique. The study was conducted using explanatory design in the form...

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...

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.

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

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)

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.)

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

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...

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

Qualification testing of fiber-based laser transmitters and on-orbit validation of a commercial laser system

Science.gov (United States)

Wright, M. W.; Wilkerson, M. W.; Tang, R. R.

2017-11-01

Qualification testing of fiber based laser transmitters is required for NASA's Deep Space Optical Communications program to mature the technology for space applications. In the absence of fully space qualified systems, commercial systems have been investigated in order to demonstrate the robustness of the technology. To this end, a 2.5 W fiber based laser source was developed as the transmitter for an optical communications experiment flown aboard the ISS as a part of a technology demonstration mission. The low cost system leveraged Mil Standard design principles and Telcordia certified components to the extent possible and was operated in a pressure vessel with active cooling. The laser was capable of high rate modulation but was limited by the mission requirements to 50 Mbps for downlinking stored video from the OPALS payload, externally mounted on the ISS. Environmental testing and space qualification of this unit will be discussed along with plans for a fully space qualified laser transmitter.

Qualification Approach for the CMC Nose Cap of X-38

Science.gov (United States)

Weihs, H.; Gülhan, A.

2002-01-01

given by the predicted re-entry loads. Discrete tests on smaller samples representing cut outs of the structure were performed for further qualification which could not be done at the complete assembly due to the limitations of the test facilities (e.g. plasma channel test). In addition to the qualification of the material or coating capability, arc jet tests were performed to check the steps and gaps influence and qualify sealing function at the interfaces between the CMC parts. This paper will give an overview of the thermal and mechanical qualification of the nose cap system. This includes the vibration loads, thermal cycling, mechanical pressure and steps and gaps arc jet tests.

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

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

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)

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

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

International Nuclear Information System (INIS)

Korsah, K.

2001-01-01

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

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

Verification Of The Defense Waste Processing Facility's (DWPF) Process Digestion Methods For The Sludge Batch 8 Qualification Sample

International Nuclear Information System (INIS)

Click, D. R.; Edwards, T. B.; Wiedenman, B. J.; Brown, L. W.

2013-01-01

This report contains the results and comparison of data generated from inductively coupled plasma atomic emission spectroscopy (ICP-AES) analysis of Aqua Regia (AR), Sodium Peroxide/Sodium Hydroxide Fusion Dissolution (PF) and Cold Chem (CC) method digestions and Cold Vapor Atomic Absorption analysis of Hg digestions from the DWPF Hg digestion method of Sludge Batch 8 (SB8) Sludge Receipt and Adjustment Tank (SRAT) Receipt and SB8 SRAT Product samples. The SB8 SRAT Receipt and SB8 SRAT Product samples were prepared in the SRNL Shielded Cells, and the SRAT Receipt material is representative of the sludge that constitutes the SB8 Batch or qualification composition. This is the sludge in Tank 51 that is to be transferred into Tank 40, which will contain the heel of Sludge Batch 7b (SB7b), to form the SB8 Blend composition

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.)

TEACHERS’ EDUCATIONAL QUALIFICATION, RANK LEVEL, WORKING DURATION, AGE, WORK MOTIVATION AND WORK EFFECTIVENESS

Directory of Open Access Journals (Sweden)

Bambang Budi Wiyono

2016-02-01

Full Text Available Teachers’ Educational Qualification, Rank Level, Working Duration, Age, Working Mo­tivation, and Working Effectiveness The study investigated the effects of educational qualification, rank level, working duration and age on the elementary school teachers’ working motivation and working ef­fectiveness. The sample of the study consisted of 438 elementary school teachers in Malang which were selected through cluster sampling technique. The study was conducted using explanatory design in the form of causal model. The data were collected using questionnaire and documentation, and were analyzed descrip­tively employing structural equation technique. The study revealed that that the effect of the educational qualification, rank level, working duration and age on teachers’ working motivation and working effec­tiveness, both directly and indirectly, was not significant.

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

International Nuclear Information System (INIS)

Melmer, J.; Waters, M.

1995-01-01

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

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.

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.

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

Discrete Data Qualification System and Method Comprising Noise Series Fault Detection

Science.gov (United States)

Fulton, Christopher; Wong, Edmond; Melcher, Kevin; Bickford, Randall

2013-01-01

A Sensor Data Qualification (SDQ) function has been developed that allows the onboard flight computers on NASA s launch vehicles to determine the validity of sensor data to ensure that critical safety and operational decisions are not based on faulty sensor data. This SDQ function includes a novel noise series fault detection algorithm for qualification of the output data from LO2 and LH2 low-level liquid sensors. These sensors are positioned in a launch vehicle s propellant tanks in order to detect propellant depletion during a rocket engine s boost operating phase. This detection capability can prevent the catastrophic situation where the engine operates without propellant. The output from each LO2 and LH2 low-level liquid sensor is a discrete valued signal that is expected to be in either of two states, depending on whether the sensor is immersed (wet) or exposed (dry). Conventional methods for sensor data qualification, such as threshold limit checking, are not effective for this type of signal due to its discrete binary-state nature. To address this data qualification challenge, a noise computation and evaluation method, also known as a noise fault detector, was developed to detect unreasonable statistical characteristics in the discrete data stream. The method operates on a time series of discrete data observations over a moving window of data points and performs a continuous examination of the resulting observation stream to identify the presence of anomalous characteristics. If the method determines the existence of anomalous results, the data from the sensor is disqualified for use by other monitoring or control functions.

Developing a Qualifications Structure for the Finance Services Industry in Malaysia and Beyond

Science.gov (United States)

Manshor, Amat Taap; Chong, Siong Choy; Cameron, Roslyn

2014-01-01

The development of qualifications systems and frameworks assists in promoting lifelong learning and work-based recognition systems. Several nations in the Asian Pacific region have established national qualifications frameworks across their respective educational sectors (e.g., Australia, New Zealand, Hong Kong, Malaysia and the Philippines),…

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...

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

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

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

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).

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...

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...

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

Energy Technology Data Exchange (ETDEWEB)

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

2017-06-26

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

Qualification tests and facilities for the ITER superconductors

International Nuclear Information System (INIS)

Bruzzone, P.; Wesche, R.; Stepanov, B.; Cau, F.; Bagnasco, M.; Calvi, M.; Herzog, R.; Vogel, M.

2009-01-01

All the ITER superconductors are tested as short length samples in the SULTAN test facility at CRPP. Twenty-four TF conductor samples with small layout variations were tested since February 2007 with the aim of verifying the design and qualification of the manufacturers. The sample assembly and the measurement techniques at CRPP are discussed. Starting in 2010, another test facility for ITER conductors, named EDIPO, will be operating at CRPP to share with SULTAN the load of the samples for the acceptance tests during the construction of ITER.

Qualification of flat welding of nuclear fuel bars

International Nuclear Information System (INIS)

Romero C, J.; Rivera M, H.

2001-01-01

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

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)

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

International Nuclear Information System (INIS)

Anderson, N.

1985-01-01

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

Sludge Batch 7B Qualification Activities With SRS Tank Farm Sludge

International Nuclear Information System (INIS)

Pareizs, J.; Click, D.; Lambert, D.; Reboul, S.

2011-01-01

Waste Solidification Engineering (WSE) has requested that characterization and a radioactive demonstration of the next batch of sludge slurry - Sludge Batch 7b (SB7b) - be completed in the Shielded Cells Facility of the Savannah River National Laboratory (SRNL) via a Technical Task Request (TTR). This characterization and demonstration, or sludge batch qualification process, is required prior to transfer of the sludge from Tank 51 to the Defense Waste Processing Facility (DWPF) feed tank (Tank 40). The current WSE practice is to prepare sludge batches in Tank 51 by transferring sludge from other tanks. Discharges of nuclear materials from H Canyon are often added to Tank 51 during sludge batch preparation. The sludge is washed and transferred to Tank 40, the current DWPF feed tank. Prior to transfer of Tank 51 to Tank 40, SRNL typically simulates the Tank Farm and DWPF processes with a Tank 51 sample (referred to as the qualification sample). With the tight schedule constraints for SB7b and the potential need for caustic addition to allow for an acceptable glass processing window, the qualification for SB7b was approached differently than past batches. For SB7b, SRNL prepared a Tank 51 and a Tank 40 sample for qualification. SRNL did not receive the qualification sample from Tank 51 nor did it simulate all of the Tank Farm washing and decanting operations. Instead, SRNL prepared a Tank 51 SB7b sample from samples of Tank 7 and Tank 51, along with a wash solution to adjust the supernatant composition to the final SB7b Tank 51 Tank Farm projections. SRNL then prepared a sample to represent SB7b in Tank 40 by combining portions of the SRNL-prepared Tank 51 SB7b sample and a Tank 40 Sludge Batch 7a (SB7a) sample. The blended sample was 71% Tank 40 (SB7a) and 29% Tank 7/Tank 51 on an insoluble solids basis. This sample is referred to as the SB7b Qualification Sample. The blend represented the highest projected Tank 40 heel (as of May 25, 2011), and thus, the highest

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

Development of a software for the ASME code qualification of class-I nuclear piping systems

International Nuclear Information System (INIS)

Mishra, Rajesh; Umashankar, C.; Soni, R.S.; Kushwaha, H.S.; Venkat Raj, V.

1999-11-01

In nuclear industry, the designer often comes across the requirements of Class-1 piping systems which need to be qualified for various normal and abnormal loading conditions. In order to have quick design changes and the design reviews at various stages of design, it is quite helpful if a dedicated software is available for the qualification of Class-1 piping systems. BARC has already purchased a piping analysis software CAESAR-II and has used it for the life extension of heavy water plant, Kota. CAESAR-II facilitates the qualification of Class-2 and Class-3 piping systems among others. However, the present version of CAESAR-II does not have the capability to perform stress checks for the ASME Class-1 nuclear piping systems. With this requirement in mind and the prohibitive costs of commercially available software for the Class-1 piping analyses, it was decided to develop a separate software for this class of piping in such a way that the input and output details of the piping from the CAESAR-II software can be made use of. This report principally contains the details regarding development of a software for codal qualification of Class-1 nuclear piping as per ASME code section-III, NB-3600. The entire work was carried out in three phases. The first phase consisted of development of the routines for reading the output files obtained from the CAESAR-II software, and converting them into required format for further processing. In this phase, the nodewise informations available from the CAESAR-II output file were converted into element-wise informations. The second phase was to develop a general subroutine for reading the various input parameters such as diameter, wall thickness, corrosion allowance, bend radius and also to recognize the bend elements based on the bend radius, directly from the input file of CAESAR-II software. The third phase was regarding the incorporation of the required steps for performing the ASME codal checks as per NB-3600 for Class-1 piping

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)

Boat sampling

International Nuclear Information System (INIS)

Citanovic, M.; Bezlaj, H.

1994-01-01

This presentation describes essential boat sampling activities: on site boat sampling process optimization and qualification; boat sampling of base material (beltline region); boat sampling of weld material (weld No. 4); problems accompanied with weld crown varieties, RPV shell inner radius tolerance, local corrosion pitting and water clarity. The equipment used for boat sampling is described too. 7 pictures

Design and qualification of a RTOS for safety class nuclear C and I applications

International Nuclear Information System (INIS)

Wakankar, A.; Khan, Arindam; Kalra, Mohit; Mitra, Raka; Aravamuthan, G.; Bhattacharjee, A.K.; Vaidya, U.W.; Mayya, Anuradha

2014-01-01

Real Time Operating System (RTOS) is a critical component of embedded systems. International standards such as IEC60880 used for development of Instrumentation and Control (I and C) system in nuclear power plants require rigorous qualification of all software components. In this paper, we describe our experience in the design and qualification of ESOS; an in-house configured RTOS from a commodity RTOS available with source code. The qualification activities include static and dynamic analysis, timing analysis and rigorous program analysis. We discuss how rigorous program analysis was used to uncover a subtle bug in the implementation. We also discuss the applications where this qualified RTOS has been successfully used. (author)

Relationship between resist outgassing and EUV witness sample contamination in NXE outgas qualification using electrons and EUV photons

Science.gov (United States)

Pollentier, I.; Tirumala Venkata, A.; Gronheid, R.

2014-04-01

EUV photoresists are considered as a potential source of optics contamination, since they introduce irradiation-induced outgassing in the EUV vacuum environment. Therefore, before these resists can be used on e.g. ASML NXE:3100 or NXE:3300, they need to be tested in dedicated equipment according to a well-defined procedure, which is based on exposing a witness sample (WS) in the vicinity of a simultaneously exposed resist as it outgasses. Different system infrastructures are used at multiple sites (e.g. NIST, CNSE, Sematech, EIDEC, and imec) and were calibrated to each other by a detailed test plan. Despite this detailed tool qualifications, a first round robin comparison of identical materials showed inconsistent outgas test results, and required further investigation by a second round robin. Since the resist exposure mode is different at the various locations (some sites are using EUV photons while others use E-gun electrons), this difference has always a point of concern for variability of test results. In this work we compare the outgas test results from EUV photon and electron exposure using the resist materials of the second round robin. Since the imec outgas tester allows both exposure methods on the resist, a within-system comparison is possible and showed limited variation between photon and electron exposure mode. Therefore the system-to-system variability amongst the different outgas test sites is expected to be related to other parameters than the electron/photon exposure mode. Initial work showed that the variability might be related to temperature, E-gun emission excursion, and/or residual outgassing scaled by different wafer areas at the different sites.

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)

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)

Qualification and Flight Test of Non-Chrome Primers for C-130 Aircraft

Science.gov (United States)

2011-08-17

system  Significant hexavalent chrome reduction in finish system  Potential exposure level of spray applied chromated conversion coating not as...Lockheed Martin Aeronautics Company Qualification and Flight Test of Non- Chrome Primers for C-130 Aircraft Scott Jones Lockheed Martin...00-2011 to 00-00-2011 4. TITLE AND SUBTITLE Qualification and Flight Test of Non- Chrome Primers for C-130 Aircraft 5a. CONTRACT NUMBER 5b. GRANT

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

Detection system qualification for direct measurement of thyroid internal contamination by radioiodine

International Nuclear Information System (INIS)

Tiberi, V.; Battisti, P.; Gualdrini, G.

1999-01-01

The work deals with a detection system qualification for direct measurements of thyroid internal contamination by radioiodine. The isotopes 131 I and 125 I are the most frequently used in nuclear medicine. Because of their volatility they are very dangerous for thyroid contamination by inhalation. The system has been projected to be easily and fast used and above all transportable where the control is necessary. These characteristic make it able to realise supervision programs of internal contamination by radioiodine. In fact due the very high control frequencies (each 15 days for 131 I), these programs are usually very expensive and demanding when they are executed in external measurement laboratories. The following steps are described: devices presentation, calculation of energy and efficiency parameters, minimum detectable activity, time system reliability, best operative conditions in the measurements. At the end an application example of the system is reported [it

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...

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

Professional Exam as a Tool for Forming the Trajectory of Improving the Qualification of an Employee

Directory of Open Access Journals (Sweden)

Egorov I.

2017-11-01

Full Text Available The results of the study of the provisions of the Federal Law "On Independent Qualification Assessment", of an explanatory note to the draft of the Federal Law "On Independent Qualification Assessment", of a number of other normative legal acts regarding the objectives and procedure for the implementation of an independent assessment of qualifications, including a professional exam, the use of its results, are described. On the basis of the analysis of a number of research works on the improvement of the qualifications of employees and the development of the system of continuous education, conclusions were drawn on an objective assessment by the legislator of a permanent increase in the requirements for the qualification of workers and the consequent need for continuous improvement of their qualifications, including the development of a continuous education system. Proposals have been formulated to introduce amendments to the legislation of the Russian Federation aimed at forming a recommendation for an employee to select existing resources for the self-alignment of an individual set of competences with a personalized offer of support options from the educational and professional structures - the trajectory of improving the qualification of an employee..

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

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

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...

International Space Station (ISS) Internal Active Thermal Control System (IATCS) New Biocide Selection, Qualification and Implementation

Science.gov (United States)

Wilson, Mark E.; Cole, Harold E.; Rector, Tony; Steele, John; Varsik, Jerry

2011-01-01

The Internal Active Thermal Control System (IATCS) aboard the International Space Station (ISS) is primarily responsible for the removal of heat loads from payload and system racks. The IATCS is a water based system which works in conjunction with the EATCS (External ATCS), an ammonia based system, which are interfaced through a heat exchanger to facilitate heat transfer. On-orbit issues associated with the aqueous coolant chemistry began to occur with unexpected increases in CO2 levels in the cabin. This caused an increase in total inorganic carbon (TIC), a reduction in coolant pH, increased corrosion, and precipitation of nickel phosphate. These chemical changes were also accompanied by the growth of heterotrophic bacteria that increased risk to the system and could potentially impact crew health and safety. Studies were conducted to select a biocide to control microbial growth in the system based on requirements for disinfection at low chemical concentration (effectiveness), solubility and stability, material compatibility, low toxicity to humans, compatibility with vehicle environmental control and life support systems (ECLSS), ease of application, rapid on-orbit measurement, and removal capability. Based on these requirements, ortho-phthalaldehyde (OPA), an aromatic dialdehyde compound, was selected for qualification testing. This paper presents the OPA qualification test results, development of hardware and methodology to safely apply OPA to the system, development of a means to remove OPA, development of a rapid colorimetric test for measurement of OPA, and the OPA on-orbit performance for controlling the growth of microorganisms in the ISS IATCS since November 3, 2007.

On the way of only one fundamental information layer for everything within new paradigm sense; ecosystem qualification mapping

Directory of Open Access Journals (Sweden)

Kürşad Özkan

2016-07-01

Full Text Available The study was carried out to attract attention to the importance of holistic approach in ecological research studies and provide information about ecosystem qualification mapping, the fundamental layer for ecosystem-based management plans, by means of a case study example. In the study, species richness, potential energy footprint, resilience, rarity and dissimilarity were accepted as qualification components and the statistical analysis was performed by using 107 sample plot data taken from Yazılı Canyon Nature Park, located in the transition zone of the Mediterranean region, Turkey. All components were calculated for each sample plot. Then, Principle Component Analysis (PCA was applied to the components. As a result of the PCA applied, it was found that all components, except for dissimilarity, correspond with each other. Therefore, the formula for qualification index was created by taking species richness, potential energy footprint, resilience and rarity components into consideration. At the second phase of the study, qualification index and the dissimilarity component were modeled according to environmental factors taken as explanatory variables by using regression tree technique. With the regression tree models obtained, distribution maps of qualification index and the dissimilarity component were formed and group distinctions of the maps were drawn. Finally, by combining the groups of qualification index and the dissimilarity components, numerical values were assigned to the newly combined groups by using if-then rules. Thus, ecosystem based qualification value map of Yazılı Canyon Nature Park was formed.

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.

Assessment of Electro-Mechanic Technician Qualifications in the Context of European Transparency Tools

Science.gov (United States)

Ozcan, Mustafa; Vuranok, Turan Tolga; Ball, Claudia

2017-01-01

Purpose: This study explores the applicability and transferability of tools developed for the realization of comparability and transparency of qualifications across Europe. It relates to the implementation of the European Credit System for Vocational Education and Training (ECVET) and the European Qualifications Framework (EQF) in the automotive…

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)

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

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

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

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

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...

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.

Qualification of a Method to Calculate the Irrecoverable Pressure Loss in High Reynolds Number Piping Systems

Energy Technology Data Exchange (ETDEWEB)

Sigg, K. C.; Coffield, R. D.

2002-09-01

High Reynolds number test data has recently been reported for both single and multiple piping elbow design configurations at earlier ASME Fluid Engineering Division conferences. The data of these studies ranged up to a Reynolds number of 42 x 10[sup]6 which is significantly greater than that used to establish design correlations before the data was available. Many of the accepted design correlations, based on the lower Reynolds number data, date back as much as fifty years. The new data shows that these earlier correlations are extremely conservative for high Reynolds number applications. Based on the recent high Reynolds number information a new recommended method has been developed for calculating irrecoverable pressure loses in piping systems for design considerations such as establishing pump sizing requirements. This paper describes the recommended design approach and additional testing that has been performed as part of the qualification of the method. This qualification testing determined the irrecoverable pressure loss of a piping configuration that would typify a limiting piping section in a complicated piping network, i.e., multiple, tightly coupled, out-of-plane elbows in series under high Reynolds number flow conditions. The overall pressure loss measurements were then compared to predictions, which used the new methodology to assure that conservative estimates for the pressure loss (of the type used for pump sizing) were obtained. The recommended design methodology, the qualification testing and the comparison between the predictions and the test data are presented. A major conclusion of this study is that the recommended method for calculating irrecoverable pressure loss in piping systems is conservative yet significantly lower than predicted by early design correlations that were based on the extrapolation of low Reynolds number test data.

The Humanitarian Action Qualifications Framework: a quality assurance tool for the Humanitarian Sector

Directory of Open Access Journals (Sweden)

Bastiaan L. Aardema

2014-07-01

Full Text Available The article presents the European Universities on Professionalisation on Humanitarian Action (EUPRHA Project as an initiative that seeks to contribute to the professionalisation and quality assurance of the humanitarian sector. Its purpose is to explain the approach and the process leading to the development of the Humanitarian Action Qualifications Framework as an example of good practice for other sectors aiming at improving the recognition of qualifications as a precondition of academic and professional mobility. With this aim, it introduces the educational and humanitarian trends that led to this project: the move from transnational qualifications frameworks of which the European Qualifications Framework for Lifelong Learning (EQF is the best example to sectoral qualifications frameworks and the increasing demand from the sector seeking to determine the competencies and required skills of a professional humanitarian aid worker. Based on the EQF and the Tuning methodology the framework will act as a translating device to make national and sectoral qualifications more readable and promote humanitarian workers’ and learners’ mobility between countries and organisations. It will facilitate inter-system transparency and recognition of (non-formal and informal learning by linking occupations, skills, competences, and qualifications, thus benefiting the Humanitarian Sector as a whole.

Sludge Washing And Demonstration Of The DWPF Flowsheet In The SRNL Shielded Cells For Sludge Batch 8 Qualification

Energy Technology Data Exchange (ETDEWEB)

Pareizs, J. M.; Crawford, C. L.

2013-04-26

The current Waste Solidification Engineering (WSE) practice is to prepare sludge batches in Tank 51 by transferring sludge from other tanks to Tank 51. Tank 51 sludge is washed and transferred to Tank 40, the current Defense Waste Processing Facility (DWPF) feed tank. Prior to transfer of Tank 51 to Tank 40, the Savannah River National Laboratory (SRNL) typically simulates the Tank Farm and DWPF processes using a Tank 51 sample (referred to as the qualification sample). WSE requested the SRNL to perform characterization on a Sludge Batch 8 (SB8) sample and demonstrate the DWPF flowsheet in the SRNL shielded cells for SB8 as the final qualification process required prior to SB8 transfer from Tank 51 to Tank 40. A 3-L sample from Tank 51 (the SB8 qualification sample; Tank Farm sample HTF-51-12-80) was received by SRNL on September 20, 2012. The as-received sample was characterized prior to being washed. The washed material was further characterized and used as the material for the DWPF process simulation including a Sludge Receipt and Adjustment Tank (SRAT) cycle, a Slurry Mix Evaporator (SME) cycle, and glass fabrication and chemical durability measurements.

Data Qualification Report: Pore Water Data for Use on the Yucca Mountain Project

International Nuclear Information System (INIS)

H. Miller; R. Monks; C. Warren; W. Wowak

2000-01-01

Pore water data associated with Data Tracking Number (DTN) No.LL990702804244.100 are referenced in the Analysis and Model Reports (AMRs) prepared to support the Site Recommendation in determining the suitability of the Yucca Mountain, Nevada as a repository for high-level nuclear waste. It has been determined, in accordance with procedure AP-3.15Q Rev. 1, ICN 1, ''Managing Technical Product Inputs'', Attachment 6 , that the DTN-referenced data are used in AMRs that provide a direct calculation of ''Principal Factors'' for the Post-closure Safety Case or Potentially Disruptive Processes or Events. Therefore, in accordance with the requirements of procedure AP-SIII.2Q, Rev 0, ICN 2, ''Qualification of Unqualified Data and the Documentation of Rationale for Accepted Data'', Section 5.3.1 .a, a Data Qualification Report has been prepared for submittal to the Assistant Manager, Office of Project Execution for concurrence. This report summarizes the findings of the Data Qualification Team assembled to evaluate unqualified ''pore water data'' represented by DTN No. LL990702804244.100. This DTN is currently used in the following AMRs: Drift-Scale Coupled Processes (DST and THC Seepage) Models (CRWMS M and O 2000a), Environment of the Surfaces of the Drip Shield and Waste Package Outer Barrier (CRWMS M and O 2000b), and Engineered Barrier System: Physical and Chemical Environment Model (CRWMS M and O 2000c). Mineral composition of pore water submitted to the Technical Data Management System (TDMS) using the subject DTN were acquired data from the analysis pore water samples sent to Lawrence Livermore National Laboratory's (LLNL) by UFA Ventures, Inc. and analyzed by LLNL's Analytical Sciences/Analytical and Nuclear Chemistry Division (ASD). The purpose and scope of the AMRs that reference the subject DTN and the potential application of pore water data is described below. These AMRs use only that data associated with the specific samples: ESF-HD-PERM-1, ESF-HD-PERM-2, and

Data Qualification Report: Pore Water Data for Use on the Yucca Mountain Project

Energy Technology Data Exchange (ETDEWEB)

H. Miller; R. Monks; C. Warren; W. Wowak

2000-06-09

Pore water data associated with Data Tracking Number (DTN) No.LL990702804244.100 are referenced in the Analysis and Model Reports (AMRs) prepared to support the Site Recommendation in determining the suitability of the Yucca Mountain, Nevada as a repository for high-level nuclear waste. It has been determined, in accordance with procedure AP-3.15Q Rev. 1, ICN 1, ''Managing Technical Product Inputs'', Attachment 6 , that the DTN-referenced data are used in AMRs that provide a direct calculation of ''Principal Factors'' for the Post-closure Safety Case or Potentially Disruptive Processes or Events. Therefore, in accordance with the requirements of procedure AP-SIII.2Q, Rev 0, ICN 2, ''Qualification of Unqualified Data and the Documentation of Rationale for Accepted Data'', Section 5.3.1 .a, a Data Qualification Report has been prepared for submittal to the Assistant Manager, Office of Project Execution for concurrence. This report summarizes the findings of the Data Qualification Team assembled to evaluate unqualified ''pore water data'' represented by DTN No. LL990702804244.100. This DTN is currently used in the following AMRs: Drift-Scale Coupled Processes (DST and THC Seepage) Models (CRWMS M&O 2000a), Environment of the Surfaces of the Drip Shield and Waste Package Outer Barrier (CRWMS M&O 2000b), and Engineered Barrier System: Physical and Chemical Environment Model (CRWMS M&O 2000c). Mineral composition of pore water submitted to the Technical Data Management System (TDMS) using the subject DTN were acquired data from the analysis pore water samples sent to Lawrence Livermore National Laboratory's (LLNL) by UFA Ventures, Inc. and analyzed by LLNL's Analytical Sciences/Analytical and Nuclear Chemistry Division (ASD). The purpose and scope of the AMRs that reference the subject DTN and the potential application of pore water data is described below. These AMRs use only that

CLASSIFICATION OF SPECIALTIES AND QUALIFICATIONS IN REPUBLIC OF BELARUS: TENDENCIES AND PROSPECTS

Directory of Open Access Journals (Sweden)

O. A. Oleks

2016-01-01

Full Text Available In the present publication short data on the system of specialties and qualifications functioning in Republic of Belarus, her features, scope of application are given. The purpose and problems of the revision of the National classifier of the Republic of Belarus «Specialties and qualifications», its orientation to reduce the gap between the content of education and content of activity of graduates of establishments of education are described. The main tendencies of change of the operating classification – on the basis of types of economic activity and international standard classification of education taking into account requirements of employers, minimization of economic expenses for education, including due to minimization of classification units, rapprochement of positions with educational systems of other states are revealed. Prospects of development of national system of specialties and qualifications are disclosed. Tendencies and prospects of the expected changes are shown on the examples of the certain specialties offered by BNTU (Belarusian National Technical University.

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.

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.

Optimal sample size for probability of detection curves

International Nuclear Information System (INIS)

Annis, Charles; Gandossi, Luca; Martin, Oliver

2013-01-01

Highlights: • We investigate sample size requirement to develop probability of detection curves. • We develop simulations to determine effective inspection target sizes, number and distribution. • We summarize these findings and provide guidelines for the NDE practitioner. -- Abstract: The use of probability of detection curves to quantify the reliability of non-destructive examination (NDE) systems is common in the aeronautical industry, but relatively less so in the nuclear industry, at least in European countries. Due to the nature of the components being inspected, sample sizes tend to be much lower. This makes the manufacturing of test pieces with representative flaws, in sufficient numbers, so to draw statistical conclusions on the reliability of the NDT system under investigation, quite costly. The European Network for Inspection and Qualification (ENIQ) has developed an inspection qualification methodology, referred to as the ENIQ Methodology. It has become widely used in many European countries and provides assurance on the reliability of NDE systems, but only qualitatively. The need to quantify the output of inspection qualification has become more important as structural reliability modelling and quantitative risk-informed in-service inspection methodologies become more widely used. A measure of the NDE reliability is necessary to quantify risk reduction after inspection and probability of detection (POD) curves provide such a metric. The Joint Research Centre, Petten, The Netherlands supported ENIQ by investigating the question of the sample size required to determine a reliable POD curve. As mentioned earlier manufacturing of test pieces with defects that are typically found in nuclear power plants (NPPs) is usually quite expensive. Thus there is a tendency to reduce sample sizes, which in turn increases the uncertainty associated with the resulting POD curve. The main question in conjunction with POS curves is the appropriate sample size. Not

From qualification design to training design using ECVET principles

International Nuclear Information System (INIS)

Ceclan, Mihail; Wastin, Franck

2017-01-01

The Joint Research Centre of European Commission was designated in 2009 as Operating agent of European Human Resources Observatory - in Nuclear (EHRO@N). EHRO@N identified the nuclear sector's major challenges: to fill@in the 30 % gap between HR demand and supply in decommissioning and to adapt nuclear E and T system to comply more to the labour market demands. The process of nuclear training system adaptation to the labour market needs is based on the design of the flexible qualifications (unit based qualifications) using European Credit system for Vocational Education and Training (ECVET) principles. The process of ECVET implementation in the nuclear energy sector is ongoing since 2011 and is based on the strategy and road map developed by EHRO-N. The current paper presents the latest developments on the designing of training programs based on exit outcomes.

From qualification design to training design using ECVET principles

Energy Technology Data Exchange (ETDEWEB)

Ceclan, Mihail; Wastin, Franck [European Commission Joint Research Centre, Petten (Netherlands). Directorate Nuclear Safety and Security

2017-05-15

The Joint Research Centre of European Commission was designated in 2009 as Operating agent of European Human Resources Observatory - in Nuclear (EHRO@N). EHRO@N identified the nuclear sector's major challenges: to fill@in the 30 % gap between HR demand and supply in decommissioning and to adapt nuclear E and T system to comply more to the labour market demands. The process of nuclear training system adaptation to the labour market needs is based on the design of the flexible qualifications (unit based qualifications) using European Credit system for Vocational Education and Training (ECVET) principles. The process of ECVET implementation in the nuclear energy sector is ongoing since 2011 and is based on the strategy and road map developed by EHRO-N. The current paper presents the latest developments on the designing of training programs based on exit outcomes.

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)

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.

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.

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 ...

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

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...

Non-destructive testing. The current state of standards and qualification and certification for leak testing

International Nuclear Information System (INIS)

Tamura, Yoshikazu

2011-01-01

Domestic standards of the leak testing are enacted as one of Japan Industrial Standards. The conformity is advanced between these domestic standards and ISO (International Organization for Standardization) standard. ISO9712 (Non-destructive testing-Qualification and certification of personnel) was revised to include the leak testing of qualification and certification in 2005. The preparation working group of qualification and certification for leak testing is planning start aiming at the system in one and a half years. (author)

Test-qualification experience with non-destructive material analysis system performed at Paks Nuclear Power Plant and its usage in non-nuclear fields

International Nuclear Information System (INIS)

Somogyi, Gy.; Szabo, D.

2003-01-01

The need for qualification of non-destructive material analysis has been recognised in controlling nuclear energy production process. This test-qualification has been performed as first of its kind after the task has been assigned by the National Nuclear Energy Agency. The input documents for the test were. Technical Specification, Analysis Technology, Technical Justification. Test-qualification has been performed with real form control bodies developed by the Rez Nuclear Research Institute, in which the planned defects has been produced by spark-chipping. The qualification procedure has been summarized in a Qualification Folder and given to the national agency to issue a qualification certificate. The procedure might be interesting mostly for companies delivering nuclear power plant assemblies. Similar needs are formulated in standards relative to the qualification of non-nuclear material testing methods (MSZ EN 17025 and EU). (Gy.M.)

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

Qualification test for ITER HCCR-TBS mockups with high heat flux test facility

Energy Technology Data Exchange (ETDEWEB)

Kim, Suk-Kwon, E-mail: skkim93@kaeri.re.kr [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Park, Seong Dae; Jin, Hyung Gon; Lee, Eo Hwak; Yoon, Jae-Sung; Lee, Dong Won [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Cho, Seungyon [National Fusion Research Institute, Daejeon (Korea, Republic of)

2016-11-01

Highlights: • The test mockups for ITER HCCR (Helium Cooled Ceramic Reflector) TBS (Test Blanket System) in Korea were designed and fabricated. • A thermo-hydraulic analysis was performed using a high heat flux test facility by using electron beam. • The plan for qualification tests was developed to evaluate the thermo-hydraulic efficiency in accordance with the requirements of the ITER Organization. - Abstract: The test mockups for ITER HCCR (Helium Cooled Ceramic Reflector) TBS (Test Blanket System) in Korea were designed and fabricated, and an integrity and thermo-hydraulic performance test should be completed under the same or similar operation conditions of ITER. The test plan for a thermo-hydraulic analysis was developed by using a high heat flux test facility, called the Korean heat load test facility by using electron beam (KoHLT-EB). This facility is utilized for a qualification test of the plasma facing component (PFC) for the ITER first wall and DEMO divertor, and for the thermo-hydraulic experiments. In this work, KoHLT-EB will be used for the plan of the performance qualification test of the ITER HCCR-TBS mockups. This qualification tests should be performed to evaluate the thermo-hydraulic efficiency in accordance with the requirements of the ITER Organization (IO), which describe the specifications and qualifications of the heat flux test facility and test procedure for ITER PFC.

Contributions to the qualification of the ''CRISTAL'' criticality calculi scheme: interpretation of critical experiments. Elaboration of a characterization system of neutronic configurations; Contributions a la qualification du schema de calcul de criticite ''cristal'': interpretation d'experiences critiques. Elaboration d'un systeme de caracterisation des configurations neutroniques

Energy Technology Data Exchange (ETDEWEB)

Gagnier, E

1999-06-01

This thesis work is about the validation of the new criticality-safety package CRISTAL and contributes to the modernization and the improvement of the computational tools. The first part presents neutronic elements, the objectives of safety criticality studies and the package CRISTAL. Then, the validation work concerned two series of experiments involving uranyl solutions (UO{sub 2}F{sub 2}) and UO{sub 2} powders. For these experiments, the differences between the computation results and the experimental results were analysed. It was highlighted interesting physical phenomena such of the compensations of errors between the approximate representation by the 99 energy group structure on the first resonance of oxygen and the anisotropy of the diffusion simulation as well as the influence of uranium 234 in high enriched solutions in uranium 235. Once the work of the experimental qualification carried out, raises the question of the use the base of qualification and the ''calculation-experiment'' variations which are referred to it. It is often difficult to establish the link between the ''studied configuration'' and the experiments of the base of qualification. The presented characterisation system proposes to answer in a way automatic and quantified this difficulty: - in bringing an answer on the package qualification for the studied configuration, - in giving an estimate of the package bias. To answer these points, it was defined a set of 35 characteristic neutronic parameters representing the behaviour of the medium. To process the information brought by these parameters and to use it to answer the objectives of the system, we called upon statistical methods (Principal Components Analysis and Sliced Inverse Regression). The results obtained in the feasibility studies showed the relevance of these methods for the considered objectives. (author)

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

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.

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

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

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)

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

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

Qualification of NDT systems for in-service inspections of nuclear power plant pressure vessels; Ydinvoimalaitosten paineastioiden maeaeraeaikaistarkastuksissa kaeytettaevien NDT-jaerjestelmien paetevoeinti

Energy Technology Data Exchange (ETDEWEB)

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 24 refs.

[Additional qualification in health economics--a pre-condition for ENT leadership positions?].

Science.gov (United States)

Lehnerdt, G; Schöffski, O; Mattheis, S; Hoffmann, T K; Lang, S

2013-11-01

The increasing medical-technical progress as well as the dramatic demographic changes cause problems with regard to rapid enlargement of medical service offers, allocation of resources and a financing shortfall in the German public health system. The economization in the German Health System can also be perceived in ENT departments. After performing an internet search about the rapidly growing market for qualifications measures in health economics, we hence conducted an anonymous survey for ENT senior doctors and directors of the 34 German University Departments to evaluate their attitude towards, as well as their expectation of such an add-on qualification. Since the German government finalized the health care reform in the year 2000 such qualification measures rapidly developed: amongst others, 26 postgraduate, extra-occupational master programs have been inaugurated. The anonymous survey was answered by 105 ENT doctors (63 senior doctors, 27 vice professors and 15 directors). 63% out of these 105 colleagues considered such an add-on qualification to be mandatory. 41% of the colleagues were already "add-on qualified" in that field, only 10 of them by means of a study program. 71 of 105 colleagues (68%) considered the add-on qualification to be advantageous for their future personal career. With regard to the designated contents of the study program, "Staff Management" was even prioritized to "Hospital Financing" and "Cost Accounting". Aspects of management and a (health-) economical basic knowledge became an integral part of the daily routine for "first-line management doctors" also in (University) ENT-departments. © Georg Thieme Verlag KG Stuttgart · New York.

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

Energy Technology Data Exchange (ETDEWEB)

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

2013-07-01

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

DATA QUALIFICATION REPORT: MAJOR ION AND PH DATA FOR USE ON THE YUCCA MOUNTAIN PROJECT

International Nuclear Information System (INIS)

C. WILSON; D.M. JENKINS; T. STEINBORN; R. WEMHEUER

2000-01-01

This data qualification report uses technical assessment and corroborating data methods according to Attachment 2 of AP-SIII.2Q, Rev. 0, ICN 2, ''Qualification of Unqualified Data and the Documentation of Rationale for Accepted Data'', to qualify major ion and pH data. This report was prepared in accordance with Data Qualification Plan TDP-NBS-GS-00003 1, Revision 2. Additional reports will be prepared to address isotopic and precipitation-related data. Most of the data considered in this report were acquired and developed by the U.S. Geological Survey (USGS). The data qualification team considers the sampling and analytical protocols employed by the USGS over the time period of data acquisition to be state-of-the-art. The sample collection methodologies have evolved with no significant change that could affect the quality of the data considered in this report into the currently used Hydrologic Procedures that support the Yucca Mountain Project-approved USGS Quality Assurance Program Plan. Consequently, for USGS data, the data collection methods, documentation, and results are reasonable and appropriate in view of standard practice at the time the data were collected. A small number of data sets were collected by organizations other than the USGS and were reviewed along with the other major ion and pH data using corroborating data methods. Hydrochemical studies reviewed in this qualification report indicate that the extent and quality of corroborating data are sufficient to support qualification of both USGS and non-USGS major ion and pH data for generalized hydrochemical studies. The corroborating data included other major ion and pH data, isotope data, and independent hydrological data. Additionally, the analytical adequacy of the major ion data was supported by a study of anion-cation charge balances. Charge balance errors for USGS and non-USGS data were under 10% and acceptable for all data. This qualification report addresses the specific major ion data sets

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.

Seismic functional qualification of active mechanical and electrical components based on shaking table testing

International Nuclear Information System (INIS)

Jurukovski, D.

1999-01-01

The seismic testing for qualification of one sample of the NPP Kozloduy Control Panel type YKTC was carried out under Research Contract no: 8008/Rl, entitled: 'Seismic Functional Qualification of Active Mechanical and Electrical Components Based on Shaking Table Testing'. The tested specimen was selected by the Kozloduy NPP staff, Section 'TIA-2' (Technical Instrumentation and Automatics), however the seismic input parameters were selected by the NPP Kozloduy staff, Section HTS and SC (Hydro-Technical Systems and Engineering Structures). The applied methodology was developed by the Institute of Earthquake Engineering and Engineering Seismology staff. This report presents all relevant items related to the selected specimen seismic testing for seismic qualification such as: description of the tested specimen, mounting conditions on the shaking table, selection of seismic input parameters and creation of seismic excitations, description of the testing equipment, explanation of the applied methodology, 'on line' and 'off line' monitoring of the tested specimen, functioning capabilities, discussion of the results and their presentation and finally conclusions and recommendations. In this partial project report, two items are presented. The first item presents a review of the existing and used regulations for performing of the seismic and vibratory withstand testing of electro-mechanical equipment. The selection is made based on MEA, IEEE, IEC and former Soviet Union regulations. The second item presents the abstracts of all the tests performed at the Institute of Earthquake Engineering and Engineering Seismology in Skopje. The selected regulations, the experience of the Institute that has been gathered for the last seventeen years and some theoretical and experimental research will be the basis for further investigations for development of a synthesised methodology for seismic qualification of differently categorized equipment for nuclear power plants

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

International Nuclear Information System (INIS)

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

1998-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

1998-01-01

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

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...

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.

The multiple gas-liquid subsea separation system: development and qualification of a novel solution for deep water field production

Energy Technology Data Exchange (ETDEWEB)

Abrand, Stephanie; Butin, Nicolas; Shaiek, Sadia; Hallot, Raymond [Saipem S.p.A., Milano (Italy)

2012-07-01

Subsea processing is more and more considered as a viable solution for the development of deep and ultra deep water fields. SAIPEM has developed a deep water gas separation and liquid boosting system, based on its proprietary 'Multi pipe' separator concept, providing a good flexibility in handling a wide range of steady and un-steady multiphase input streams using a relatively simple mechanical arrangement. The Multi pipe Concept features an array of vertical pipes for gas/liquid separation by gravity and adequate liquid hold up volumes. The operating principle is the same as standard gravity vessels. Specific inlet pipe arrangements have been worked out to enhance the separation efficiency and internals can be implemented to further optimize the performances. The limited diameter and wall thickness of the vertical pipes make the Multi pipe Concept particularly suited for deep and ultra-deep water applications and/or high pressure conditions where the selection of a single separator vessel could lead to unpractical wall thicknesses. In most cases, standard API or ASME pipes can be utilized for the Multi pipe Separator, thus enabling conventional fabrication methods, and in turn reducing cost and delivery time and opening opportunities for local content. The qualification testing program has seen two subsequent phases. The first qualification phase aimed at the confirmation of the hydrodynamic behavior of the system. In particular, the homogeneous distribution of the multiphase stream into the pipes and the stability of the liquid levels under un-steady inlet conditions were continuously assessed during the tests. This first qualification phase gave confidence in the viability of the Multi pipe and in its good hydrodynamic behavior under the different inlet conditions that can be encountered during field production. It proved that, having the same liquid level in all the separator pipes, whatever the inlet conditions are, the Multi pipe separator can be

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

International Nuclear Information System (INIS)

1978-06-01

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

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)

Contributions to the qualification of the ''CRISTAL'' criticality calculi scheme: interpretation of critical experiments. Elaboration of a characterization system of neutronic configurations

International Nuclear Information System (INIS)

Gagnier, E.

1999-06-01

This thesis work is about the validation of the new criticality-safety package CRISTAL and contributes to the modernization and the improvement of the computational tools. The first part presents neutronic elements, the objectives of safety criticality studies and the package CRISTAL. Then, the validation work concerned two series of experiments involving uranyl solutions (UO 2 F 2 ) and UO 2 powders. For these experiments, the differences between the computation results and the experimental results were analysed. It was highlighted interesting physical phenomena such of the compensations of errors between the approximate representation by the 99 energy group structure on the first resonance of oxygen and the anisotropy of the diffusion simulation as well as the influence of uranium 234 in high enriched solutions in uranium 235. Once the work of the experimental qualification carried out, raises the question of the use the base of qualification and the ''calculation-experiment'' variations which are referred to it. It is often difficult to establish the link between the ''studied configuration'' and the experiments of the base of qualification. The presented characterisation system proposes to answer in a way automatic and quantified this difficulty: - in bringing an answer on the package qualification for the studied configuration, - in giving an estimate of the package bias. To answer these points, it was defined a set of 35 characteristic neutronic parameters representing the behaviour of the medium. To process the information brought by these parameters and to use it to answer the objectives of the system, we called upon statistical methods (Principal Components Analysis and Sliced Inverse Regression). The results obtained in the feasibility studies showed the relevance of these methods for the considered objectives. (author)

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

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

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

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

International Nuclear Information System (INIS)

1996-03-01

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

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

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-03-01

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

Importance of the European qualification frame (EQF) and its tools for radiation protection

International Nuclear Information System (INIS)

Schmitt-Hannig, Annemarie

2013-01-01

The harmonization of different radiation protection education and training systems in Europe and the mutual approval of the qualifications acquired abroad are discussed since years. Due to large national differences the mutual approval is usually based on case approaches instead of a standardized procedure. With the European qualification frame for life learning and EVCET (European credit system for vocational education and training) there are tools that could also be used in the sector of radiation protection education and training. The draft of the EURATOM basic safety standards (BSS) guideline includes the requirement of an approval of radiation protection officer certifications.

Radiated EMC& EMI Management During Design Qualification and Test Phases on LEO Satellites Constellation

Science.gov (United States)

Blondeaux, H.; Terral, M.; Gutierrez-Galvan, R.; Baud, C.

2016-05-01

The aim of the proposed paper is to present the global radiated EMC/EMI approach applied by Thales Alenia Space in the frame of a telecommunication Low Earth Orbit (LEO) satellites constellation program. The paper will present this approach in term of analyses, of specific characterisation and of sub-system and satellite tests since first design reviews up-to satellite qualification tests on Prototype Flight Model (PFM) and to production tests on reduced FMs. The global aim is : 1 - to reduce risk and cost (units EMC delta qualification, EMC tests at satellite level for the 81 Space Vehicles (SV) through appropriated EMC analyses (in term of methodologies and contours) provided in the frame of design reviews.2 - to early anticipate potential critical case to reduce the impact in term of engineering/qualification/test extra cost and of schedule.3 - to secure/assure the payload and SV design/layout.4 - to define and optimize the EMC/EMI test campaigns to be performed on Prototype Flight Model (PFM) for complete qualification and on some FMs for industrial qualification/validation.The last part of the paper is dedicated to system Bite Error Rate (BER) functional test performed on PFM SV to demonstrate the final compatibility between the three on-board payloads and to the Internal EMC tests performed on PFM and some FMs to demonstrate the SV panel RF shielding efficiency before and after environmental tests and the Thales Alenia Space (TAS) and Orbital AKT (OATK) workmanships reproducibility.

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...

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.

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

Recent activities within Nuclear Electric related to the qualification of digital systems and the extension of maintenance intervals

International Nuclear Information System (INIS)

Holt, G.P.

1993-01-01

Nuclear Electric is pursuing a program of modernization and enhancement of existing control and safety (C ampersand I) systems to improve power plant availability and increase power output. This paper describes recent experience in qualifying digital systems for safety applications. Also, described is the work currently in hand to reduce the frequency of maintenance periods for safety C ampersand I equipment. The qualification of digital systems is shown to be a more rigorous and much more extensive (and thus costly) exercise than the qualification of conventional equipment. This is illustrated by brief references to two software-based safety systems, the Single Channel Trip System at the Dungeness open-quotes Bclose quotesAGR and the Primary Protection System for the new PWR at Sizewell open-quotes Bclose quotes. The emphasis of the paper is on the use of Application Specific Integrated Circuits (ASICs) in safety systems, to reduce, or eliminate dependence on software for the fulfillment of requirements which need implementations that are complex or of a high functional density. Recent experience in the development of a prototype safety system based on ASICs, The Gaseous Activity Monitor and Trip Equipment (GAM), is used to illustrate their possible benefits and potential problems. When using complex integrated circuits like microprocessors or ASICs in digital systems a difficulty arises in analyzing the failure modes of the system. Efforts to overcome this difficulty led to the development of a method for performing failure analyses based on functional blocks. The techniques and benefits of such an approach are outlined. Finally, efforts to reduce maintenance costs, yet at the same time enhance safety, are leading towards an extension of maintenance intervals, for some safety equipment, from 3 months to 4 months and also towards lengthening the period between AGR outages from 2 years to 3 years

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.

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)

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.

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.

Design and qualification of an UHV system for operation on sounding rockets

Energy Technology Data Exchange (ETDEWEB)

Grosse, Jens, E-mail: jens.grosse@dlr.de; Braxmaier, Claus [Center of Applied Space Technology and Microgravity (ZARM), University of Bremen, Bremen, 28359, Germany and German Aerospace Center (DLR) Bremen, Bremen, 28359 (Germany); Seidel, Stephan Tobias; Becker, Dennis; Lachmann, Maike Diana [Institute of Quantum Optics, Leibniz University Hanover, Hanover, 30167 (Germany); Scharringhausen, Marco [German Aerospace Center (DLR) Bremen, Bremen, 28359 (Germany); Rasel, Ernst Maria [Institute of Quantum Optics, Leibniz University Hanover, Hanover, 30167, Bremen (Germany)

2016-05-15

The sounding rocket mission MAIUS-1 has the objective to create the first Bose–Einstein condensate in space; therefore, its scientific payload is a complete cold atom experiment built to be launched on a VSB-30 sounding rocket. An essential part of the setup is an ultrahigh vacuum system needed in order to sufficiently suppress interactions of the cooled atoms with the residual background gas. Contrary to vacuum systems on missions aboard satellites or the international space station, the required vacuum environment has to be reached within 47 s after motor burn-out. This paper contains a detailed description of the MAIUS-1 vacuum system, as well as a description of its qualification process for the operation under vibrational loads of up to 8.1 g{sub RMS} (where RMS is root mean square). Even though a pressure rise dependent on the level of vibration was observed, the design presented herein is capable of regaining a pressure of below 5 × 10{sup −10} mbar in less than 40 s when tested at 5.4 g{sub RMS}. To the authors' best knowledge, it is the first UHV system qualified for operation on a sounding rocket.

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.

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

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...

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

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

Portfolio of qualifications: a tool for evaluating academic productivity at the Karolinska Institutet.

Science.gov (United States)

Dahllöf, G; Ekstrand, J; Nordenström, J

1999-02-01

A Portfolio of Qualifications for academic appointments at the Karolinska Institutet has been developed to define more clearly the competence and qualifications which are given high priority for academic appointments at the Karolinska Institutet. The major fields of application are for new appointments and promotions, providing guidelines for the individual for improving his/her proficiency, and as a basis for determining individual salary rates. Four portfolios have been developed, a pedagogical, a clinical, a scientific, and a leadership, development and workplace relations portfolio. Attached to the portfolios are assessment forms. We consider the Qualifications Portfolio to be a reflection of changes in attitudes and values at the Karolinska Institutet. The system offers a method for the recognition of faculty productivity in different dimensions. This may be beneficial for the university in view of the increasing diversity and complexity of academic institutions. The Qualifications portfolio can be obtained from the world wide web, http:/(/)www.ki.se/ki/merit.se.html (in Swedish), http:/(/)www.ki.se/ki/merit.html (in English).

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

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...

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.

Methodology for qualification of in-service inspection systems for WWER nuclear power plants. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

International Nuclear Information System (INIS)

1998-03-01

Program was initiated by IAEA in 1990 with the aim to assist the countries of Central and Eastern Europe and former Soviet Union in evaluating the safety of their first generation WWER-440/230 nuclear power plants. The main objectives were: to identify major design and operational safety issues; to establish international consensus on priorities for safety improvements; and to provide assistance in the review of the competence and and adequacy of safety improvement programs. The scope was extended in 1992 to include RBMK, WWER-440/312 and WWER-1000 plants in operation and under construction. Integrity of primary circuit is fundamental for the safe operation of any nuclear power plant. In-service inspection (ISI) in general terms and in particular, non-destructive tests (NDT) play a key role in maintaining primary circuit integrity. This report provides a methodology for qualification of ISI systems which might be used by WWER operating countries as a commonly accepted basis for further development of the necessary qualification related infrastructures. It also provides several qualification principles defining the administrative framework needed for the practical implementation of the methodology, a description of the process of qualification of an inspection system, specifying its minimum technical and documentation related requirements, as well as specific requirements with regard to the NDT procedures, equipment and personnel to be qualified and the test specimen to be used in practical trials. Finally, the report suggests an appropriate distribution of responsibilities among all the parties involved in a qualification process, based on international practice

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

Nodalization qualification process of the PSBVVER facility for the Cathare2 thermal-hydraulic code

International Nuclear Information System (INIS)

Del Nevo, A.; Araneo, D.; D'Auria, F.; Galassi, G.

2004-01-01

The present document deals with the nodalization qualification process of the PSB-VVER test facility for Cathare2 code. PSB-VVER facility is a 1/300 volume scale model of a VVER-1000, reactor installed at Electrogorsk Research and Engineering Centre in 1998. The version V1.5b of the Cathare2 code has been used. In order to evaluate the nodalization performance, the qualifying procedure set up at the DIMNP of Pisa University (UNIPI) has been applied that foresees two qualification levels: a 'steady state' level and an 'on transient' level. After the steady state behavior check of the nodalization, it has been preformed the on transient qualification the PSB-VVER test 2. It is a 11% equivalent break in Upper Plenum with the actuation of one high pressure injection system, connected to the hot leg of the loop 4, and 4 passive systems (ECCS hydro-accumulators), connected to the outlet plenum and to the inlet chamber of the downcomer. The low-pressure injection system is not available in the test. The goal of this paper is to demonstrate that the first step of the nodalization qualification adopted for the PSB test analyses is achieved and the PSB facility input deck is available and ready to use. The quantitative accuracy of the performed calculation has been evaluated by using the FFT-BM tool developed at the University of Pisa.(author)

The Indicators of Gytariai Secondary School teachers' qualification in the context of restructure of Lithuanian and Šiauliai region's educational system

OpenAIRE

Tamošiūnas, Teodoras; Minkuvienė, Edita

2005-01-01

Having investigated the body of statistical data of teachers qualification of the 2002-2003 and 2002-2003 educational activities of Lithuania and Šiauliai city/municipality, the following was established: About 80 per cent of teachers of Lithuanian schools of general education are certified. Pedagogues having the qualification of a senior teacher prevail (56%). The dominant of teachers having high qualification (that of a methodologist or an expert) at secondary schools accounts for 13-23%, i...

Major activities of the association ''Arbeitsgemeinschaft Solar NRW''. Decentralized energy systems development, trial and qualification

International Nuclear Information System (INIS)

Meliss, M.

1996-01-01

In North-Rhine Westphalia, the Ministry for Science and Research and the Ministry for Economic Affairs, Medium-Sized Companies and Technology (MWF) in 1991 decided to jointly establish a research and technology association called AG Solar NRW, intended to function as a central body for promotion and coordination of existing but dispersed projects and activities in North-Rhine Westphalia for research into and development of solar technology and energy systems, and for promotion of demonstration projects and training programmes supporting enhanced use of solar energy. The total budget made available for activities of the AG Solar in phase 1 (1991 - 1995) was approx. DM 60 million. The article in hand summarizes the main activities and results achieved in this first phase which was committed to decentralized energy systems, performance testing and qualification. (orig.) [de

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

The qualification of electrical components and instrumentations relevant to safety

CERN Document Server

Zambardi, F

1989-01-01

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

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.

The construction and space qualification of the control electronics for the tracker detector cooling system of the AMS-02 experiment

International Nuclear Information System (INIS)

Menichelli, M.; Accardo, L.; Alberti, G.; Bardet, M.; Battiston, R.; Blasko, S.; He, Z.; Koutsenko, V.; Lebedev, A.; Ni, J.; Papi, A.; Pauw, A.; Van Ess, J.; Wang, Z.; Zhang, D.; Zwartbol, T.

2010-01-01

This article describes the control electronics for the silicon tracker cooling system in the AMS-02 apparatus. It also contains a brief description of the cooling system itself necessary for the description of the electronics. The tracker cooling system includes a set of various sensors and actuators which are necessary for bringing the tracker detector to a uniform temperature at which it can operate correctly. In order to test the system performing the various qualification activities we have built also an Electronic Ground support equipment (EGSE). The EGSE should simulate the behaviour of all sensors and actuators previously mentioned.

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

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

KAEC experience in development of the regulatory framework for training and qualification

International Nuclear Information System (INIS)

Kim, A.; Idrissova, M.; Kossilov, Al.; Pryakhin, A.

2002-01-01

Full text: Since 1991, after getting of the sovereignty, Kazakhstan started developing of its own legislative and regulatory system in the field of atomic energy use. In accordance with the Decrees of the President appropriate structures in Kazakhstan were created. They are: Atomic Energy Committee, as a main supervising governmental body, National Nuclear Centre combining all nuclear related scientific institutes, and National Atomic Company Kazatomprom. On 14 February 1994 Kazakhstan joined the International Atomic Energy Agency. Also a lot of enterprises use radioactive sources for the different application in medicine, research, industry, agriculture and etc. Infrastructure of the using of atomic energy in Kazakhstan includes: One power fast reactor BN-350 (now it is shut down and prepared for the decommissioning); Four Research reactors of the National Nuclear Centre; Uranium mining and milling enterprises; Fuel fabrication plant; Storage facilities for nuclear materials, radiation substances and radioactive waste; Organizations using radiation sources; Transport organizations. According to this the Republic of Kazakhstan needs the effective system for the assurance and guarantees for protection of population and environment against the possible negative influence of atomic energy usage. One of the important parts of that is a system of training and qualification of personnel involved in the nuclear activity. In the legislative field of the safely use of nuclear energy several Laws of the Republic of Kazakhstan have been elaborated and adopted. They are: Law on Atomic Energy Use (14 April 1997, Law on Radiation Protection of Population (23 April 1998), Law on Licensing. Those documents formed the first level of the structure of the national system for reliable training, qualification and authorization of the personnel involved in the nuclear activities. The second level is formed by the Legal Acts of the Government of Kazakhstan. The other levels of the

Development of the environmental qualification safety requirement matrix for the containment system of in-service CANDU reactors

International Nuclear Information System (INIS)

Chun, R.M.; Low, J.; Sobolewski, J.

1994-01-01

Over the last several years, Ontario Hydro Nuclear (OHN) has placed increasing emphasis on environmental qualification (EQ) at its Pickering and Bruce NGS A and B nuclear generating stations (NGSs). The program currently underway (at the time of the conference) builds upon the experience gained from the extensive Darlington NGS EQ experience and from EQ programs conducted by other utilities. Some of the major steps of the OHN EQ program include: defining Safety Requirement Matrices (SRMs), establishing environmental conditions, developing an EQ List, conducting an EQ Assessment and maintaining Operational EQ Assurance during the plant life. The SRM identifies safety related components, their required safety functions and their mission times for each postulated design basis accident (DBA). This is a critical step, as the SRM defines the equipment that requires assurance of EQ and precise requirements must be provided to ensure a cost effective EQ program. This paper describes the development of the SRMs for the containment system of the Bruce stations. The introductory section briefly discusses how the industry has dealt with equipment qualification as it has evolved and the role of the SRMs in the OHN EQ Program. In Section 2, the preparation of the SRM is described along with the applicable ground rules used. The results of the application of the SRM preparation guidelines to the containment system are discussed in Section 3. A summary of the major findings and conclusions is presented. 3 refs., 3 figs

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.

Optimal Sample Size for Probability of Detection Curves

International Nuclear Information System (INIS)

Annis, Charles; Gandossi, Luca; Martin, Oliver

2012-01-01

The use of Probability of Detection (POD) curves to quantify NDT reliability is common in the aeronautical industry, but relatively less so in the nuclear industry. The European Network for Inspection Qualification's (ENIQ) Inspection Qualification Methodology is based on the concept of Technical Justification, a document assembling all the evidence to assure that the NDT system in focus is indeed capable of finding the flaws for which it was designed. This methodology has become widely used in many countries, but the assurance it provides is usually of qualitative nature. The need to quantify the output of inspection qualification has become more important, especially as structural reliability modelling and quantitative risk-informed in-service inspection methodologies become more widely used. To credit the inspections in structural reliability evaluations, a measure of the NDT reliability is necessary. A POD curve provides such metric. In 2010 ENIQ developed a technical report on POD curves, reviewing the statistical models used to quantify inspection reliability. Further work was subsequently carried out to investigate the issue of optimal sample size for deriving a POD curve, so that adequate guidance could be given to the practitioners of inspection reliability. Manufacturing of test pieces with cracks that are representative of real defects found in nuclear power plants (NPP) can be very expensive. Thus there is a tendency to reduce sample sizes and in turn reduce the conservatism associated with the POD curve derived. Not much guidance on the correct sample size can be found in the published literature, where often qualitative statements are given with no further justification. The aim of this paper is to summarise the findings of such work. (author)

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...

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

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...

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...

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.)

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

Data qualification summary for 1985 L-Area AC Flow Tests

International Nuclear Information System (INIS)

Edwards, T.B.; Eghbali, D.A.; Liebmann, M.L.; Shine, E.P.

1992-03-01

The 1985 L-Area AC Flow Tests were conducted to provide an extended data base for upgrading the reactor system models employed in predicting normal process water flows. This report summarizes the results of the recently completed, formal, technical review of the data from the 1985 L-Area AC Flow Tests as detailed in document SCS-CMAS-910045. The purpose of that review was to provide corroborating technical information as to the quality (fitness for use) of these experimental data. Reference [1] required three volumes to fully document the results of that Data Qualification process. This report has been prepared to provide the important conclusions from that process in a manageable and understandable format. Consult reference [1] if any additional information or detail is needed. This report provides highlights from that study: an overview of the tests and data, a description of the instrumentation used, an explanation of the data qualification methods employed to review the data, and the important conclusions reached from the study. Reference 1: Edwards, T.B., D.A. Eghbali, M.L. Liebmann, and E.P. Shine, open-quotes Data Qualification for 1985 L-Area AC Flow Tests,close quotes SCS-CMAS-910045, December 31, 1991

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...

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...

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...

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.

Implementation and qualification of MCNP 5 through the intercomparison with the benchmark for the calculation of critical systems Godiva and Jezebel

International Nuclear Information System (INIS)

Lara, Rafael G.; Maiorino, Jose R.

2013-01-01

This work aimed at the implementation and qualification of MCNP code in a supercomputer of the Universidade Federal do ABC, so that may be available a next-generation simulation tool for precise calculations of nuclear reactors and systems subject to radiation. The implementation of this tool will have multidisciplinary applications, covering various areas of engineering (nuclear, aerospace, biomedical), radiation physics and others

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.

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 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 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...

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…

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...

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.

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)

NASA Electronic Parts and Packaging (NEPP): Space Qualification Guidelines of Optoelectronic and Photonic Devices for Optical Communication Systems

Science.gov (United States)

Kim, Quiesup

2001-01-01

Key elements of space qualification of opto-electric and photonic optical devices were overviewed. Efforts were concentrated on the reliability concerns of the devices needed for potential applications in space environments. The ultimate goal for this effort is to gradually establish enough data to develop a space qualification plan of newly developed specific photonic parts using empirical and numerical models to assess the life-time and degradation of the devices for potential long term space missions.

Developing pre-qualification inter-professional education for nursing and medical students: sampling student attitudes to guide development.

Science.gov (United States)

Morison, Sue; Boohan, Mairead; Moutray, Marianne; Jenkins, John

2004-03-01

Teamwork and collaboration are regarded as important goals for health and social care education and inter-professional education (IPE) the vehicle to achieve this. However, there is debate concerning the best strategies for implementation, location and delivery of IPE. This exploratory study was undertaken to anticipate some of the problems of implementing a pre-qualification IPE programme for Children's Branch nursing students and medical students undertaking a Paediatrics module and to identify strategies to maximise success. A modified version of the readiness for inter-professional learning scale (RIPLS), including additional open-ended questions, was used with a convenient, purposeful sample of 20 medical and 10 nursing students. Both groups regarded learning team-working skills as important. Medical students regarded IPE as a means to learn about team-work and professional roles otherwise they indicated a preference for a discipline-based approach. Both groups were found to have acquired a strong sense of their own professional role. Both perceived IPE as disadvantageous if it impeded their own professional learning. Results also highlighted the importance of class size, stage of learning, appropriate skills and subject in IPE planning. We conclude that a small exploratory study can provide a useful guide for programme planning and additional qualitative data can enable a more comprehensive explanation of results.

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...

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...

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...

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.

The Qualification Experiences for Safety-critical Software of POSAFE-Q

Energy Technology Data Exchange (ETDEWEB)

Kim, Jang Yeol; Son, Kwang Seop; Cheon, Se Woo; Lee, Jang Soo; Kwon, Kee Choon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2009-05-15

Programmable Logic Controllers (PLC) have been applied to the Reactor Protection System (RPS) and the Engineered Safety Feature (ESF)-Component Control System (CCS) as the major safety system components of nuclear power plants. This paper describes experiences on the qualification of the safety-critical software including the pCOS kernel and system tasks related to a safety-grade PLC, i.e. the works done for the Software Verification and Validation, Software Safety Analysis, Software Quality Assurance, and Software Configuration Management etc.

Development of a Univariate Membrane-Based Mid-Infrared Method for Protein Quantitation and Total Lipid Content Analysis of Biological Samples

Directory of Open Access Journals (Sweden)

Ivona Strug

2014-01-01

Full Text Available Biological samples present a range of complexities from homogeneous purified protein to multicomponent mixtures. Accurate qualification of such samples is paramount to downstream applications. We describe the development of an MIR spectroscopy-based analytical method offering simultaneous protein quantitation (0.25–5 mg/mL and analysis of total lipid or detergent species, as well as the identification of other biomolecules present in biological samples. The method utilizes a hydrophilic PTFE membrane engineered for presentation of aqueous samples in a dried format compatible with fast infrared analysis. Unlike classical quantification techniques, the reported method is amino acid sequence independent and thus applicable to complex samples of unknown composition. By comparison to existing platforms, this MIR-based method enables direct quantification using minimal sample volume (2 µL; it is well-suited where repeat access and limited sample size are critical parameters. Further, accurate results can be derived without specialized training or knowledge of IR spectroscopy. Overall, the simplified application and analysis system provides a more cost-effective alternative to high-throughput IR systems for research laboratories with minimal throughput demands. In summary, the MIR-based system provides a viable alternative to current protein quantitation methods; it also uniquely offers simultaneous qualification of other components, notably lipids and detergents.

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 ...

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...

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

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

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...

Qualification of Electrical Components in Nuclear Power Plants. Management of Ageing

Energy Technology Data Exchange (ETDEWEB)

Spaang, Kjell [Ingemansson Technology AB, Goeteborg (Sweden); Staahl, Gunnar [Westinghouse Atom, Vaesteraas (Sweden)

2002-05-01

This report reviews R and D results and experiences forming the bases for the preparation of a report on management of ageing. It includes basic information and descriptions of value for persons who work with the questions and some data from investigations of the ageing characteristics of various materials: limit levels, dose-rate effects, activation energies, methods for condition monitoring, etc. This report is restricted to safety related components containing ageing sensitive parts, mainly organic materials (polymers). For components located in the containment, the possibilities of continuous supervision are limited. The accessibility for regular inspections is also limited in many cases. Therefore, the main part of this report deals with the qualification of such components. In addition, some material is given on qualification located outside containment with better possibilities for frequent inspection and supervision. A survey is made of activities, programs and tools for ageing qualification in connection with initial environmental qualification (type testing) as well as after installation (condition monitoring, extension of qualified life through on-going qualification). Tools are also given for supplementary ageing qualification of already installed components.

Qualification of Electrical Components in Nuclear Power Plants. Management of Ageing

International Nuclear Information System (INIS)

Spaang, Kjell; Staahl, Gunnar

2002-05-01

This report reviews R and D results and experiences forming the bases for the preparation of a report on management of ageing. It includes basic information and descriptions of value for persons who work with the questions and some data from investigations of the ageing characteristics of various materials: limit levels, dose-rate effects, activation energies, methods for condition monitoring, etc. This report is restricted to safety related components containing ageing sensitive parts, mainly organic materials (polymers). For components located in the containment, the possibilities of continuous supervision are limited. The accessibility for regular inspections is also limited in many cases. Therefore, the main part of this report deals with the qualification of such components. In addition, some material is given on qualification located outside containment with better possibilities for frequent inspection and supervision. A survey is made of activities, programs and tools for ageing qualification in connection with initial environmental qualification (type testing) as well as after installation (condition monitoring, extension of qualified life through on-going qualification). Tools are also given for supplementary ageing qualification of already installed components

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

Contributions to the qualification of the ''CRISTAL'' criticality calculi scheme: interpretation of critical experiments. Elaboration of a characterization system of neutronic configurations; Contributions a la qualification du schema de calcul de criticite ''cristal'': interpretation d'experiences critiques. Elaboration d'un systeme de caracterisation des configurations neutroniques

Energy Technology Data Exchange (ETDEWEB)

Gagnier, E

1999-06-01

This thesis work is about the validation of the new criticality-safety package CRISTAL and contributes to the modernization and the improvement of the computational tools. The first part presents neutronic elements, the objectives of safety criticality studies and the package CRISTAL. Then, the validation work concerned two series of experiments involving uranyl solutions (UO{sub 2}F{sub 2}) and UO{sub 2} powders. For these experiments, the differences between the computation results and the experimental results were analysed. It was highlighted interesting physical phenomena such of the compensations of errors between the approximate representation by the 99 energy group structure on the first resonance of oxygen and the anisotropy of the diffusion simulation as well as the influence of uranium 234 in high enriched solutions in uranium 235. Once the work of the experimental qualification carried out, raises the question of the use the base of qualification and the ''calculation-experiment'' variations which are referred to it. It is often difficult to establish the link between the ''studied configuration'' and the experiments of the base of qualification. The presented characterisation system proposes to answer in a way automatic and quantified this difficulty: - in bringing an answer on the package qualification for the studied configuration, - in giving an estimate of the package bias. To answer these points, it was defined a set of 35 characteristic neutronic parameters representing the behaviour of the medium. To process the information brought by these parameters and to use it to answer the objectives of the system, we called upon statistical methods (Principal Components Analysis and Sliced Inverse Regression). The results obtained in the feasibility studies showed the relevance of these methods for the considered objectives. (author)

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…

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...

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

When 'national innovation system' meet 'varieties of capitalism' arguments on labour qualifications: On the skill types and scientific knowledge needed for radical and incremental product innovations

NARCIS (Netherlands)

Herrmann, A.M.; Peine, A.

2011-01-01

The literatures on 'varieties of capitalism' (VoC) and 'national innovation systems' (NIS) propose very similar arguments about how firms require different types of labour qualifications to pursue strategies of radical product innovation (RPI), incremental product innovation (IPI), and product

Raman laser spectrometer optical head: qualification model assembly and integration verification

Science.gov (United States)

Ramos, G.; Sanz-Palomino, M.; Moral, A. G.; Canora, C. P.; Belenguer, T.; Canchal, R.; Prieto, J. A. R.; Santiago, A.; Gordillo, C.; Escribano, D.; Lopez-Reyes, G.; Rull, F.

2017-08-01

Raman Laser Spectrometer (RLS) is the Pasteur Payload instrument of the ExoMars mission, within the ESA's Aurora Exploration Programme, that will perform for the first time in an out planetary mission Raman spectroscopy. RLS is composed by SPU (Spectrometer Unit), iOH (Internal Optical Head), and ICEU (Instrument Control and Excitation Unit). iOH focuses the excitation laser on the samples (excitation path), and collects the Raman emission from the sample (collection path, composed on collimation system and filtering system). Its original design presented a high laser trace reaching to the detector, and although a certain level of laser trace was required for calibration purposes, the high level degrades the Signal to Noise Ratio confounding some Raman peaks. So, after the bread board campaign, some light design modifications were implemented in order to fix the desired amount of laser trace, and after the fabrication and the commitment of the commercial elements, the assembly and integration verification process was carried out. A brief description of the iOH design update for the engineering and qualification model (iOH EQM) as well as the assembly process are briefly described in this papers. In addition, the integration verification and the first functional tests, carried out with the RLS calibration target (CT), results are reported on.

12 CFR 208.35 - Qualification requirements for transactions in certain securities. [Reserved

Science.gov (United States)

2010-01-01

... requirements for transactions in certain securities. [Reserved] ... 12 Banks and Banking 2 2010-01-01 2010-01-01 false Qualification requirements for transactions in certain securities. [Reserved] 208.35 Section 208.35 Banks and Banking FEDERAL RESERVE SYSTEM BOARD OF...

[Transfer of the AGnES concept to the regular German health-care system: legal evaluation, reimbursement, qualification].

Science.gov (United States)

van den Berg, N; Kleinke, S; Heymann, R; Oppermann, R F; Jakobi, B; Hoffmann, W

2010-05-01

According to an amendment of German social security legislation, the AGnES concept of delegation of certain tasks of medical care, especially house calls, by general practitioners (GPs) to qualified practice employees (AGnES employees), will be transferred into the regular German health care system from January 2009 onward. The concept was developed to support GPs in regions with imminent gaps in primary care. Patient data, the specifically delegated and all other activities carried out by the AGnES employees in the AGnES projects were digitally documented. Additionally, the participating GPs, AGnES employees and patients underwent a set of standardised interviews. A curriculum to qualify the AGnES employees and to define the requirements needed was developed. A legal assessment of all delegated activities was carried out, and an economical model to calculate the necessary allowance was calculated. In seven model projects in four federal states in Germany, 11,228 house calls were carried out involving 1,424, mostly multimorbid, patients (mean age: 78.6 years). A modular structured curriculum, considering the basic education and acquired competences, was developed. It allows for an individual qualification of the AGnES employees. The result of the legal assessment was the central relevance of the qualification of the practice employees according to the AGnES curriculum as the essential condition for carrying out the entire range of activities of the AGnES concept. The economic model revealed euro 21.58 for a house call by an AGnES employee. The underlying model referred to underserved regions. A successful transfer of the AGnES concept with a high standard of quality into regular health-care depends on several factors. Of particular importance is the specific qualification of the practice employees, which is a central legal condition for the delegation of medical tasks from GPs to AGnEs employees. A second determining factor is also an adequate reimbursement within

Graduates from dual qualification courses, registered nurse and health visitor: a career history study.

Science.gov (United States)

Drennan, Vari M; Porter, Elizabeth M J; Grant, Robert L

2013-08-01

Educationalists and managers internationally are challenged to find ways of preparing, recruiting early in their careers, and retaining nurses into public health roles in primary care. Public health nursing qualifications are post-initial nurse registration in the United Kingdom as in some other countries. In the mid twentieth century there were a number of innovative programmes of dual qualification: registered nurse and health visitor (the United Kingdom term for public health nurse). To investigate the career histories of graduates from courses integrating both nursing and health visitor qualifications. An observational, survey study. The United Kingdom. A purposive sample of graduates from integrated registered nurse and health visitor programmes, 1959-1995, from one University. Self completed, anonymous, survey sent to graduates, with contact details known to the University and through snowballing techniques, in 2011. Forty five women (56%), graduates in all four decades, returned the survey. A significant majority (82%) had taken up health visitor posts on completing the course. Over their careers, 42% of all jobs held were as health visitors. Only four never worked in a post that required a health visiting qualification. Most had undertaken paid work throughout their careers that focused on aspects of public health, often linked to child, maternal and/or family wellbeing. Many held teaching/lecturing and management posts at some point in their career. Those holding management posts were more likely to report leaving them as a result of organisational re-structuring or redundancy than those in non-management posts. Courses that prepare students to be both nurses and health visitors result in a majority of graduates who take up posts as health visitors on qualification and subsequently. Nurse education planners may find this evidence of value in determining ways of providing a future workforce for public health nursing. Copyright © 2012 Elsevier Ltd. All

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…

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...

Methods for qualification of highly reliable software - international procedure

International Nuclear Information System (INIS)

Kersken, M.

1997-01-01

Despite the advantages of computer-assisted safety technology, there still is some uneasyness to be observed with respect to the novel processes, resulting from absence of a body of generally accepted and uncontentious qualification guides (regulatory provisions, standards) for safety evaluation of the computer codes applied. Warranty of adequate protection of the population, operators or plant components is an essential aspect in this context, too - as it is in general with reliability and risk assessment of novel technology - so that, due to appropriate legislation still missing, there currently is a licensing risk involved in the introduction of digital safety systems. Nevertheless, there is some extent of agreement within the international community and utility operators about what standards and measures should be applied for qualification of software of relevance to plant safety. The standard IEC 880/IEC 86/ in particular, in its original version, or national documents based on this standard, are applied in all countries using or planning to install those systems. A novel supplement to this standard, document /IEC 96/, is in the process of finalization and defines the requirements to be met by modern methods of software engineering. (orig./DG) [de

Employers’ View on Problems Related to Workforce Skills and Qualification

Directory of Open Access Journals (Sweden)

Klimplová Lenka

2012-12-01

Full Text Available The aim of this exploratory study is to reveal employers’ views on problems related to workforce human capital (skills and qualification. Where do employers themselves view the core of difficulties with ensuring adequately skilled workforce? Do they assign them to technological and organizational changes (a functional concept of job-specific human capital obsolescence, or do they see these problems as a result of other circumstances, such as macro-structural conditions or institutional settings? To answer these questions selected employers in mechanical engineering and information technology sectors in the Czech Republic were interviewed. The results show that the employers see the problems: 1 on the side of workforce – insufficient abilities and skills, exaggerated demands and low motivation; 2 as inadequate capacities and capabilities of the organization itself; 3 at macro-level as institutional shortcomings in the initial educational system and social benefits system. The problems related to workforce skills and qualification cannot be, thus, interpreted only in the functionalist view as job-specific human capital obsolescence, but the formulation of the problems is significantly affected by the institutional framework.

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...

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

Qualifications manual for Inspection and Enforcement personnel. Volume I. Detailed data sheets

International Nuclear Information System (INIS)

Bartley, H.J.; Heyer, F.H.K.; Schwartz, E.G.; Harrison, O.J.; Krass, I.W.; Welsh, D.M.

1978-06-01

This document is the General Research Corporation (GRC) final report on Task I Job/Position Qualifications Statements for the Headquarters and regional position of NRC/IE. It reflects the results of upgrading, expanding, and reformating the preliminary Task I report. To accomplish this, GRC made a thorough examination of all data developed during Task I, Task II (Career Fields), Task III (Training Evaluation), and Task IV (Hiring Qualifications), to include NRC/IE comments and management decisions received. The reformated Job/Position Qualifications Statements resulting from this effort (Appendix A) identify three job qualifications categories for each position--performance, attributes, and knowledge. Two formats are provided: a summarized one for manpower management in Volume I and a detailed one for career and training management in Volume II. In addition to recommending approval of the job/position qualifications, GRC proposes their use in conjunction with the hiring qualifications in the Task IV report to update NRC/IE job descriptions

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…

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

Accreditation proposal for control systems in electrical engineering for 6th level in European Qualification Framework (EQF)

DEFF Research Database (Denmark)

Tsirigotis, Georgios; Friesel, Anna

2013-01-01

The progress of science and technology emphasizes the connection between different domains and disciplines. The technology development and changing demands of the labour market require upgrading and renewing of learning outcomes in higher education, especially in engineering fields. The Life Long...... Learning (LLL) procedure must be the platform offering the required qualifications for the demands of companies and engineering professionals all over the world in order to support their competitiveness. In this paper we describe an improved proposal for accreditation of one important subject...... in engineering, namely Control Systems. The described procedure could be applied in the frame of LLL and also in classical engineering education systems, such as university and college education, in order to harmonize the recognition of engineering degrees in Europe and outside the Europe. Furthermore we state...

Development and Commissioning Results of the Hybrid Sensor Bus Engineering Qualification Model

Science.gov (United States)

Hurni, Andreas; Putzer, Phillipp; Roner, Markus; Gurster, Markus; Hulsemeyer, Christian; Lemke, Norbert M. K.

2016-08-01

In order to reduce mass, AIT effort and overall costs of classical point-to-point wired temperature sensor harness on-board spacecraft OHB System AGhas introduced the Hybrid Sensor Bus (HSB) system which interrogates sensors connected in a bus architecture. To use the advantages of electrical as wellas of fiber-optical sensing technologies, HSB is designed as a modular measurement system interrogating digital sensors connected on electricalsensor buses based on I2C and fiber-optical sensor buses based on fiber Bragg grating (FBG) sensors inscribed in optical fibers. Fiber-optical sensor bus networks on-board satellites are well suited for temperature measurement due to low mass, electro-magnetic insensitivity and the capability to embed them inside structure parts. The lightweight FBG sensors inscribed in radiation tolerant fibers can reach every part of the satellite. HSB has been developed in the frame of the ESA ARTES program with European and German co- funding and will be verified as flight demonstrator on- board the German Heinrich Hertz satellite (H2Sat).In this paper the Engineering Qualification Model (EQM) development of HSB and first commissioning results are presented. For the HSB development requirements applicable for telecommunication satellite platforms have been considered. This includes an operation of at least 15 years in a geostationary orbit.In Q3/2016 the qualification test campaign is planned to be carried out. The HSB EQM undergoes a full qualification according to ECSS. The paper concludes with an outlook regarding this HSB flight demonstrator development and its in-orbit verification (IOV) on board H2Sat.

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

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

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…

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

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

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

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)

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

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,…

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.

Qualification and certification of nondestructive testing personnel. Vol. 1

Energy Technology Data Exchange (ETDEWEB)

Aly, E A [Quality Assurance Department, national Center for Nuclear Safety and Radiation Control, Atomic Energy Authority, Cairo, (Egypt)

1996-03-01

Nondestructive testing and inspection are functions in achieving the goals of quality and efficiency at an acceptable cost. All quality assurance systems necessitate that engineers, technicians and craftsmen are able to demonstrate that they have the required level of knowledge and skill. This applies particularly to nondestructive testing (NDT) and inspection. The paper presented highlights most important national and international standards and guidelines addressing training, qualification and certification of NDT personnel.

Qualification and certification of nondestructive testing personnel. Vol. 1

International Nuclear Information System (INIS)

Aly, E.A.

1996-01-01

Nondestructive testing and inspection are functions in achieving the goals of quality and efficiency at an acceptable cost. All quality assurance systems necessitate that engineers, technicians and craftsmen are able to demonstrate that they have the required level of knowledge and skill. This applies particularly to nondestructive testing (NDT) and inspection. The paper presented highlights most important national and international standards and guidelines addressing training, qualification and certification of NDT personnel

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

International Nuclear Information System (INIS)

Sun Haipeng; Liu Zhijun; Li Tianshu

2013-01-01

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

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

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

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

Qualification of uranium-molybdenum alloy fuel - conclusions of an international workshop

International Nuclear Information System (INIS)

Snelgrove, J.L.; Languille, A.

2000-01-01

Thirty-one participants representing 21 reactors, fuel developers, fuel fabricators, and fuel reprocessors in 11 countries discussed the requirements for qualification of U-Mo alloy fuel at a workshop held at Argonne National Laboratory on January 17-18, 2000. Consensus was reached that the qualification plans of the U.S. RERTR program and the French U-Mo fuel development program are valid. The items to be addressed during qualification are summarized in the paper. (author)

The implementing of the training, examination and qualification for QA auditor

International Nuclear Information System (INIS)

Ma Xiaozheng; Han Peicong; Zhang Zhongyuan; Zhu Guoliang

2007-01-01

China Power Investment Corporation has implemented the training, examination and qualification for QA auditor based on the related requirements of the nuclear safety documents. The bases, planning of the procedure, implementing procedure and suggestions for implementing the training, examination and qualification are described in this article. That can be used as the reference for implementing the training, examination and qualification for QA auditor, as well as for establishment of the related guide. (authors)

Understanding to requirements for educational level in qualification of reactor operators

International Nuclear Information System (INIS)

Zhang Chi; Yang Di; Zhou Limin

2007-01-01

Requirements for qualification of reactor operators in nuclear safety regulations were discussed in this paper. The new issue was described in the confirmation of education level of reactor operators. The understanding to the requirements for Educational Level in Qualification of Reactor Operators was provided according to Higher Education Law of the People's Republic of China. It was proposed to improve the confirmation of qualification of reactor operators as soon as possible. (authors)

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

Mechanical properties used for the qualification of transport casks

International Nuclear Information System (INIS)

Salzbrenner, R.; Crenshaw, T.B.; Sorenson, K.B.

1993-01-01

The qualification process that should be sufficient for qualification of a specific cask (material/geometry combination) has been examined. The prototype cask should be tested to determine its overall variation in microstructure, chemistry, and mechanical properties. This prototype may also be subjected to 'proof testing' to demonstrate the validity of the design analysis (including the mechanical properties used in the analysis). The complete mechanical property mapping does not necessarily have to precede the proof testing (i.e., portions of the cask which experience only low (elastic) loads during the drop test are suitable for mechanical test specimens). The behavior of the prototype cask and the production casks are linked by assuring that each cask possesses at least the minimum level of one or more critical mechanical properties. This may be done by measuring the properties of interest directly, or by relying on a secondary measurement (such as subsize mechanical test results or microstructure/compositional measurements) which has been statistically correlated to the critical properties. The database required to show the correlation between the secondary measurement and the valid design property may be established by tests on the material from the prototype cask. The production controls must be demonstrated as being adequate to assure that a uniform product is produced. The testing of coring (or test block or prolongation) samples can only be viewed as providing a valid link to the benchmark results provided by the prototype cask if the process used to create follow-on casks remains essentially similar. The MOSAIK Test Program has demonstrated the qualification method through the benchmarking stage. The program did not establish for qualifying serial production casks through, for example, a correlation between small specimen parameters and valid design fracture toughness properties. Such a correlation would require additional experimental work. (J.P.N.)

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2013-02-25

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

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...

PROBLEMS OF COMPETENCY-BASED ASSESSMENT OF APPLIED QUALIFICATIONS

Directory of Open Access Journals (Sweden)

S. A. Efimova

2017-01-01

Full Text Available Introduction. The search of the unified tools of competences measurement of vocational training institutions graduates and identification of mechanisms of interrelation of these competences with requirements of professional standards imposed to workers of various levels are brought into focus in the context of formation of National system of qualifications of the Russian Federation, introduction of the Third-generation Federal State Educational Standards and transition of professional education to the modular, and competence-based model of the organization of training. The aim of the article is to justify the content, structure and technology of competency-based assessment, as a set of interrelated activities and regulated procedures performed on the basis of the standardized interdisciplinary evaluation materials. Methodology and research methods. The present investigation is based on systematic-activity and competency-based approaches, analysis, systematization, and generalization. Results. The place of competencies, as a part of educational outcomes of vocational education programs, is justified. Critical analysis of typical methodological solutions that are typical for the modern pedagogical practices of the competency-based assessment is performed. The content and organizational design of the process of competency-based assessment is described. Scientific novelty. The conceptual apparatus of competency-based assessment is supplemented with the «sub-competence» category - component of competence, which retains all of its properties due to human activities. Factors of objects choice and methods of assessment in identifying the professional competences are proved. Practical significance. Results of the study can be used by researchers involved with assessment procedures; methodologists and teachers of professional educational organizations, training institutes, independent centers of the qualifications evaluation for the organization of

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...

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

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

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.

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

Positive and Negative Perceptions of Bumiputra And Non-Bumiputra Students on Professional Qualification

Directory of Open Access Journals (Sweden)

Abd. Rashid Noor Asidah

2017-01-01

Full Text Available Bumiputra and non-Bumiputra students may come from various economic backgrounds and culture. This may influence their perception on their career choice of pursuing a professional accounting qualification. Thus, this study investigates the difference in positive and negative perceptions of Bumiputra and non-Bumiputra students on pursuing a professional qualification upon graduation. A questionnaire survey method was used to collect the data from final year accounting students from five public and three private universities in Malaysia. Means and independent sample t-tests results were analysed. Results indicated that there are only a few significant differences between Bumiputra and non-Bumiputra students on positive and negative perceptions on becoming professional accountants. As perception frames action, these findings would be useful to the Malaysian Institute of Accountants as well as professional bodies to attract both Bumiputra and non-Bumiputra graduates to become professional accountants.

48 CFR 14.202-4 - Bid samples.

Science.gov (United States)

2010-10-01

... be described adequately in the specification or purchase description. (2) Bid samples will be used... the bidder's intention was to qualify the bid. (See 14.404-2(d) if the qualification does not conform...

Qualification of non-destructive examination for belgian nuclear reactor pressure vessel inspection

International Nuclear Information System (INIS)

Couplet, D.; Francoise, T.

2001-01-01

In Service Inspection (ISI) participates to the assessment of Nuclear Reactor Pressure Vessel Integrity. The performance of Non Destructive Examination (NDE) techniques must be demonstrated according to predefined objectives. The qualification process is essential to trust the reliability of the information provided by NDE. In Belgian Nuclear Power Plants, the qualification was conducted through a collaboration between the vendor and a technical group from the Electricity Utility. The important facts of this qualification will be presented: - the detailed definition of the inspection and qualifications objectives, based on a combination of the ASME code and the European Methodology for Qualification; - the systematic verification of the NDE performance and limitations, for each ISI objective, through an adequate combination of tests on blocks and technical justification; - the continuous improvement of the NDE procedure; - the feedback and the lessons learnt from site experience; - the necessary multi-disciplinary approach (NDE, degradation mechanisms, structural integrity)

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

International Nuclear Information System (INIS)

Isgro, J.R.

1982-01-01

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

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

46 CFR 2.75-70 - Welding procedure and performance qualifications.

Science.gov (United States)

2010-10-01

... 46 Shipping 1 2010-10-01 2010-10-01 false Welding procedure and performance qualifications. 2.75... for Construction Personnel § 2.75-70 Welding procedure and performance qualifications. (a) Welding... requirements for the welding of pressure piping, boilers, pressure vessels, and nonpressure vessel type tanks...

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...

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...

Seismic qualification of equipment by means of probabilistic risk assessment

International Nuclear Information System (INIS)

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

1982-01-01

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

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…

Re-qualification of MTR-type fuel plates fabrication process

International Nuclear Information System (INIS)

Elseaidy, I.M.; Ghoneim, M.M.

2010-01-01

The fabricability issues with increased uranium loading due to use low enrichment of uranium (LEU), i.e. less than 20 % of U 235 , increase the problems which occur during compact manufacturing, roll bonding of the fuel plates, potential difficulty in forming during rolling process, mechanical integrity of the core during fabrication, potential difficulty in meat homogeneity, and the ability to fabricate plates with thicker core as a means of increasing total uranium loading. To produce MTR- type fuel plates with high uranium loading (HUL) and keep the required quality of these plates, many of qualification process must be done in the commissioning step of fuel fabrication plant. After that any changing of the fabrication parameters, for example changing of any of the raw materials, devises, operators, and etc., a re- qualification process should be done in order to keep the quality of produced plates. Objective of the present work is the general description of the activities to be accomplished for re-qualification of manufacturing MTR- type nuclear fuel plates. For each process to be re-qualified, a detailed of re-qualification process were established. (author)

Synergistic Development, Test, and Qualification Approaches for the Ares I and V Launch Vehicles

Science.gov (United States)

Cockrell, Charles E.; Taylor, James L.; Patterson, Alan; Stephens, Samuel E.; Tyson, Richard W.; Hueter, Uwe

2009-01-01

The U.S. National Aeronautics and Space Administration is designing and developing the Ares I and Ares V launch vehicles for access to the International Space Station (ISS) and human exploration of the Moon. The Ares I consists of a first stage reusable five-segment solid rocket booster, a upper stage using a J-2X engine derived from heritage experience (Saturn and Space Shuttle External Tank programs), and the Orion crew exploration vehicle (CEV). The Ares V is designed to minimize the development and overall life-cycle costs by leveraging off of the Ares I design. The Ares V consists of two boosters, a core stage, an earth departure stage (EDS), and a shroud. The core stage and EDS use LH2/LO2 propellants, metallic propellant tanks, and composite dry structures. The core stage has six RS-68B upgraded Delta IV engines while the EDS uses a J-2X engine for second stage ascent and trans-lunar injection (TLI) burn. System and propulsion tests and qualification approaches for Ares V elements are being considered as follow-on extensions of the Ares I development program. Following Ares I IOC, testing will be conducted to verify the J-2X engine's orbital restart and TLI burn capability. The Ares I upper stage operation will be demonstrated through integrated stage development and acceptance testing. The EDS will undergo similar development and acceptance testing with additional testing to verify aspects of cryogenic propellant management, operation of sub-systems in a space simulation environment, and orbital re-start of the main propulsion system. RS-68B certification testing will be conducted along with integrated core stage development and acceptance testing. Structural testing of the Ares V EDS and core stage propellant tanks will be conducted similar to the Ares I upper stage. The structural qualification testing may be accomplished with separate propellant tank test articles. Structural development and qualification testing of the dry structure will be pursued as

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...

Testing of Small Graphite Samples for Nuclear Qualification

Energy Technology Data Exchange (ETDEWEB)

Julie Chapman

2010-11-01

Accurately determining the mechanical properties of small irradiated samples is crucial to predicting the behavior of the overal irradiated graphite components within a Very High Temperature Reactor. The sample size allowed in a material test reactor, however, is limited, and this poses some difficulties with respect to mechanical testing. In the case of graphite with a larger grain size, a small sample may exhibit characteristics not representative of the bulk material, leading to inaccuracies in the data. A study to determine a potential size effect on the tensile strength was pursued under the Next Generation Nuclear Plant program. It focuses first on optimizing the tensile testing procedure identified in the American Society for Testing and Materials (ASTM) Standard C 781-08. Once the testing procedure was verified, a size effect was assessed by gradually reducing the diameter of the specimens. By monitoring the material response, a size effect was successfully identified.

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.

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

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.

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...

SLUDGE WASHING AND DEMONSTRATION OF THE DWPF FLOWSHEET IN THE SRNL SHIELDED CELLS FOR SLUDGE BATCH 5 QUALIFICATION

Energy Technology Data Exchange (ETDEWEB)

Pareizs, J; Cj Bannochie, C; Damon Click, D; Dan Lambert, D; Michael Stone, M; Bradley Pickenheim, B; Amanda Billings, A; Ned Bibler, N

2008-11-10

Sludge Batch 5 (SB5) is predominantly a combination of H-modified (HM) sludge from Tank 11 that underwent aluminum dissolution in late 2007 to reduce the total mass of sludge solids and aluminum being fed to the Defense Waste Processing Facility (DWPF) and Purex sludge transferred from Tank 7. Following aluminum dissolution, the addition of Tank 7 sludge and excess Pu to Tank 51, Liquid Waste Operations (LWO) provided the Savannah River National Laboratory (SRNL) a 3-L sample of Tank 51 sludge for SB5 qualification. SB5 qualification included washing the sample per LWO plans/projections (including the addition of a Pu/Be stream from H Canyon), DWPF Chemical Process Cell (CPC) simulations, waste glass fabrication (vitrification), and waste glass chemical durability evaluation. This report documents: (1) The washing (addition of water to dilute the sludge supernatant) and concentration (decanting of supernatant) of the Tank 51 qualification sample to adjust sodium content and weight percent insoluble solids to Tank Farm projections. (2) The performance of a DWPF CPC simulation using the washed Tank 51 sample. This includes a Sludge Receipt and Adjustment Tank (SRAT) cycle, where acid is added to the sludge to destroy nitrite and remove mercury, and a Slurry Mix Evaporator (SME) cycle, where glass frit is added to the sludge in preparation for vitrification. The SME cycle also included replication of five canister decontamination additions and concentrations. Processing parameters for the CPC processing were based on work with a non radioactive simulant. (3) Vitrification of a portion of the SME product and Product Consistency Test (PCT) evaluation of the resulting glass. (4) Rheology measurements of the initial slurry samples and samples after each phase of CPC processing. This work is controlled by a Task Technical and Quality Assurance Plan (TTQAP) , and analyses are guided by an Analytical Study Plan. This work is Technical Baseline Research and Development (R

47 CFR 25.140 - Qualifications of fixed-satellite space station licensees.

Science.gov (United States)

2010-10-01

... 47 Telecommunication 2 2010-10-01 2010-10-01 false Qualifications of fixed-satellite space station licensees. 25.140 Section 25.140 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) COMMON CARRIER SERVICES SATELLITE COMMUNICATIONS Applications and Licenses Space Stations § 25.140 Qualifications...

Radiological Risk Assessment and Cask Materials Qualification for Disposed Sealed Radioactive Sources Transport

International Nuclear Information System (INIS)

Margeanu, C.A.; Olteanu, G.; Bujoreanu, D.

2009-01-01

The hazardous waste problem imposes to respect national and international agreed regulations regarding their transport, taking into account both for maintaining humans, goods and environment exposure under specified limits, during transport and specific additional operations, and also to reduce impact on the environment. The paper follows to estimate the radiological risk and cask materials qualification according to the design specifications for disposed sealed radioactive sources normal transport situation. The shielding analysis has been performed by using Oak Ridge National Laboratory's SCALE 5 programs package. For thermal analysis and cask materials qualification ANSYS computer code has been used. Results have been obtained under the framework of Advanced system for monitoring of hazardous waste transport on the Romanian territory Research Project which main objective consists in implementation of a complex dual system for on-line monitoring both for transport special vehicle and hazardous waste packages, with data automatic transmission to a national monitoring center

Students' qualification in environmental and sustainability education—epistemic gaps or composites of critical thinking?

Science.gov (United States)

Hasslöf, Helen; Lundegård, Iann; Malmberg, Claes

2016-01-01

In an 'age of measurement' where students' qualification is a hot topic on the political agenda, it is of interest to ask what the function of qualification might implicate in relation to a complex issue as Education for Sustainable Development (ESD) and what function environmental and sustainability issues serve in science education. This paper deals with how secondary and upper secondary teachers in discussions with colleagues articulate qualification in relation to educational aims of ESD. With inspiration from discourse theory, the teachers' articulations of qualification are analysed and put in relation to other functions of education (qualification, socialisation and subjectification). The results of this study show three discourses of qualification: scientific reasoning, awareness of complexity and to be critical. The discourse of 'qualification as to be critical' is articulated as a composite of differing epistemological views. In this discourse, the teachers undulate between rationalistic epistemological views and postmodern views, in a pragmatic way, to articulate a discourse of critical thinking which serves as a reflecting tool to bring about different ways of valuing issues of sustainability, which reformulates 'matter of facts' towards 'matter of concerns'

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

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,…

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...

Test Plan for Rotary Mode Core Sample Truck Grapple Hoist Level Wind System

International Nuclear Information System (INIS)

BOGER, R.M.

1999-01-01

A Grapple Hoist Assembly is currently used on the Rotary Mode Core Sampling Trucks (RMCSTs) to actuate the sampler and retrieve the pintle rod during sampling operations. The hoist assembly includes a driven drum approximately two inches wide and six inches in diameter that rotates to pay out or reel in the 5/32-in. cable The current Grapple Hoist Assembly, detailed on drawing H-2-690057, is prone to ''bird nesting'' the cable on the drum. ''Bird nesting'' is a condition in which the cable does not wind onto the drum in a uniformly layered manner, but winds in a random fashion where the cable essentially ''piles up'' inappropriately on the drum and, on some occasions, winds on the drum drive shaft. A system to help control this ''bird nesting'' problem has been designed as an addition to the existing components of the Grapple Hoist Assembly. The new design consists of a mechanism that is timed with, and driven by, the shaft that drives the drum. This mechanism traverses back and forth across the width of the drum to lay the cable on the drum in a uniformly layered manner. This test plan establishes the acceptance criteria, test procedure and test conditions It also describes the test apparatus necessary to verify the adequacy of the level wind system design. The test is defined as qualification testing (LMHC 1999b) and as such will be performed at conditions beyond the parameters that the Grapple Hoist Assembly is allowed to operate by the Safety Equipment List (SEL)(LMHC 1998)

Test Plan for Rotary Mode Core Sample Truck Grapple Hoist Level Wind System

International Nuclear Information System (INIS)

BOGER, R.M.

1999-01-01

A Grapple Hoist Assembly is currently used on the Rotary Mode Core Sampling Trucks (RMCSTs) to actuate the sampler and retrieve the pintle rod during sampling operations. The hoist assembly includes a driven drum approximately two inches wide and six inches in diameter that rotates to pay out or reel in the 5/32-in. cable. The current Grapple Hoist Assembly, detailed on drawing H-2-690057, is prone to ''bird nesting'' the cable on the drum. ''Bird nesting'' is a condition in which the cable does not wind onto the drum in a uniformly layered manner, but winds in a random fashion where the cable essentially ''piles up'' inappropriately on the drum and, on some occasions, winds on the drum drive shaft. A system to help control this ''bird nesting'' problem has been designed as an addition to the existing components of the Grapple Hoist Assembly. The new design consists of a mechanism that is timed with, and driven by, the shaft that drives the drum. This mechanism traverses back and forth across the width of the drum to lay the cable on the drum in a uniformly layered manner. This test plan establishes the acceptance criteria, test procedure and test conditions. It also describes the test apparatus necessary to verify the adequacy of the level wind system design. The test is defined as qualification testing (LMHC 1999b) and as such will be performed at conditions beyond the parameters that the Grapple Hoist Assembly is allowed to operate by the Safety Equipment List

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

International Nuclear Information System (INIS)

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

2014-01-01

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

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.

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.)

NbTi Strands Verification for ITER PF CICC Process Qualification of CNDA

Science.gov (United States)

Liu, F.; Liu, H.; Liu, S.; Liu, B.; Lei, L.; Wu, Y.

2014-05-01

China is in charge of most of Poloidal Field (PF) conductors production for the International Thermonuclear Experimental Reactor (ITER). The execution for PF conductors shall be in three main phases. According to ITER Procurement Arrangement (PA), the Domestic Agency (DA) shall be required to verify the room and low temperature acceptance tests carried out by the strand suppliers. As the reference laboratory of Chinese DA (CNDA), the superconducting strands test laboratory of Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP) was undertaking the task of strands verification for ITER conductors. The verification test includes: diameter, Nickel plating thickness, copper-to-non-copper volume ratio, twist pitch direction and length, standard critical current (IC) and resistive transition index (n), residual resistance ration (RRR), and hysteresis loss. 48 NbTi strands with 7 billets were supplied for the PF Cable-In-Conduit Conductor (CICC) process qualification. In total, 54 samples were measured. The verification level for PF CICC process qualification was 100%. The test method, facility and results of each item are described in detail in this publication.

Guidelines for training and qualification of radiological protection technicians

International Nuclear Information System (INIS)

1987-08-01

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

Recommendations for fluorescence instrument qualification: the new ASTM Standard Guide.

Science.gov (United States)

DeRose, Paul C; Resch-Genger, Ute

2010-03-01

Aimed at improving quality assurance and quantitation for modern fluorescence techniques, ASTM International (ASTM) is about to release a Standard Guide for Fluorescence, reviewed here. The guide's main focus is on steady state fluorometry, for which available standards and instrument characterization procedures are discussed along with their purpose, suitability, and general instructions for use. These include the most relevant instrument properties needing qualification, such as linearity and spectral responsivity of the detection system, spectral irradiance reaching the sample, wavelength accuracy, sensitivity or limit of detection for an analyte, and day-to-day performance verification. With proper consideration of method-inherent requirements and limitations, many of these procedures and standards can be adapted to other fluorescence techniques. In addition, procedures for the determination of other relevant fluorometric quantities including fluorescence quantum yields and fluorescence lifetimes are briefly introduced. The guide is a clear and concise reference geared for users of fluorescence instrumentation at all levels of experience and is intended to aid in the ongoing standardization of fluorescence measurements.

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.       

7 CFR 4290.360 - Initial review of Applicant's management team's qualifications.

Science.gov (United States)

2010-01-01

... 7 Agriculture 15 2010-01-01 2010-01-01 false Initial review of Applicant's management team's...'s management team's qualifications. The Secretary will review the information submitted by the Applicant concerning the qualifications of the Applicant's management team to determine in his or her sole...

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

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)

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)

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

Nuclear power reactor security personnel training and qualification plan reviewer workbook

International Nuclear Information System (INIS)

1979-06-01

The Training and Qualification Plan Reviewer Workbook has been developed to provide the information required for evaluating the adequacy of the Training and Qualification (T and Q) Plans developed to meet the requirements of 10 CFR 73.55(b)(4) and 10 CFR 73, Appendix B

Recent developments in methodology for dynamic qualification of nuclear plant equipment

International Nuclear Information System (INIS)

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

1984-01-01

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

A continuous flow from sample collection to data acceptability determination using an automated system

International Nuclear Information System (INIS)

Fisk, J.F.; Leasure, C.; Sauter, A.D.

1993-01-01

In its role as regulator, EPA is the recipient of enormous reams of analytical data, especially within the Superfund Program. In order to better manage the volume of paper that comes in daily, Superfund has required its laboratories to provide data that is contained on reporting forms to be delivered also on a diskette for uploading into data bases for various purposes, such as checking for contractual compliance, tracking quality assurance parameters, and, ultimately, for reviewing the data by computer. This last area, automated review of the data, has generated programs that are not necessarily appropriate for use by clients other than Superfund. Such is the case with Los Alamos National Laboratory's Environmental Chemistry Group and its emerging subcontractor community, designed to meet the needs of the remedial action program at LANL. LANL is in the process of implementing an automated system that will be used from the planning stage of sample collection to the production of a project-specific report on analytical data quality. Included are electronic scheduling and tracking of samples, data entry, checking and transmission, data assessment and qualification for use, and report generation that will tie the analytical data quality back to the performance criteria defined prior to sample collection. Industry standard products will be used (e.g., ORACLE, Microsoft Excel) to ensure support for users, prevent dependence on proprietary software, and to protect LANL's investment for the future

46 CFR 68.7 - Qualification as an 883-1 corporation.

Science.gov (United States)

2010-10-01

... 46 Shipping 2 2010-10-01 2010-10-01 false Qualification as an 883-1 corporation. 68.7 Section 68.7... Trade § 68.7 Qualification as an 883-1 corporation. (a) To be formally qualified as an 883-1 corporation for all purposes under the Act, a corporation which meets the requirements of § 68.5 must file with...

Reference to the Safety Engineering Undergraduate Courses to Improve the Subjects and Contents of the Certified Safety Engineer Qualification and Examination System of China

OpenAIRE

Haibin Qiu; Shanghong Shi; Tingdi Zhao; Yiwei Qiao; Jiangshi Zhang

2013-01-01

The aim of this paper is to recommend that the subjects and contents of certified safety engineers use safety engineering undergraduate curriculum system for reference. Human resources play an important role in accident prevention and loss control. Education on safety engineering develops quickly in China. Moreover, the State Administration of Work Safety and the National Human Resources and Social Security Ministry have implemented a certified safety engineer qualification and examination sy...

Current activities and challenges of the European network for inspection and qualification (ENIQ)

Energy Technology Data Exchange (ETDEWEB)

Martin, Oliver [European Commission, Joint Research Centre (JRC), Petten (Netherlands). Institute for Energy and Transport (IET); Martin, Etienne [EDF, St Denis (France). Direction Production Ingenierie; Booler, Russ [AMEC Clean Energy Europe, Warrington (United Kingdom); Zetterwall, Tommy [Swedish Qualification Centre, Taeby (Sweden); Walker, Tony [Rolls-Royce Submarines, Derby (United Kingdom)

2014-10-15

This article describes the development of the European Network for Inspection and Qualification (ENIQ) since the previous presentation of the network in the 2011 April/May edition of this journal, covering mainly the new technical challenges facing the network and resulting projects as well as the establishment of the new Task Group for Inspection Qualification Bodies. ENIQ is a utility-driven network dealing with the reliability and effectiveness of non-destructive testing (NDT) for nuclear power plants (NPP). ENIQ is recognised as one of the main contributors to today's global qualification codes and guidelines for in-service inspection (ISI) and has published nearly 50 documents. Among them are the 'European Methodology for Qualification of Non-Destructive Testing', the first qualification methodology based on technical justifications, the 'European Framework Document for Risk-Informed In-Service Inspection (RI-ISI)', and various recommend practices. In addition ENIQ has carried out two pilot studies and a number of surveys. In 2012, ENIQ joined the European based R and D association on Gen II and III reactors, NUGENIA, making ENIQ its 8{sup th} technical area. Following the entry into NUGENIA, ENIQ members have updated the ENIQ roadmap and included a number of new technical challenges facing its members in the near future. Also ENIQ established a third task group in 2013, the Task Group for Inspection Qualification Bodies (TGIQB), which should serve as an exchange forum for inspection qualification bodies. ENIQ is currently preparing or performing new projects and studies to tackle these challenges and new recommended practices and reports are likely to evolve from these projects, which will enable ENIQ to maintain its role as one of the main contributors to today's global qualification codes and guidelines for ISI.

Current activities and challenges of the European network for inspection and qualification (ENIQ)

International Nuclear Information System (INIS)

Martin, Oliver; Martin, Etienne; Zetterwall, Tommy; Walker, Tony

2014-01-01

This article describes the development of the European Network for Inspection and Qualification (ENIQ) since the previous presentation of the network in the 2011 April/May edition of this journal, covering mainly the new technical challenges facing the network and resulting projects as well as the establishment of the new Task Group for Inspection Qualification Bodies. ENIQ is a utility-driven network dealing with the reliability and effectiveness of non-destructive testing (NDT) for nuclear power plants (NPP). ENIQ is recognised as one of the main contributors to today's global qualification codes and guidelines for in-service inspection (ISI) and has published nearly 50 documents. Among them are the 'European Methodology for Qualification of Non-Destructive Testing', the first qualification methodology based on technical justifications, the 'European Framework Document for Risk-Informed In-Service Inspection (RI-ISI)', and various recommend practices. In addition ENIQ has carried out two pilot studies and a number of surveys. In 2012, ENIQ joined the European based R and D association on Gen II and III reactors, NUGENIA, making ENIQ its 8 th technical area. Following the entry into NUGENIA, ENIQ members have updated the ENIQ roadmap and included a number of new technical challenges facing its members in the near future. Also ENIQ established a third task group in 2013, the Task Group for Inspection Qualification Bodies (TGIQB), which should serve as an exchange forum for inspection qualification bodies. ENIQ is currently preparing or performing new projects and studies to tackle these challenges and new recommended practices and reports are likely to evolve from these projects, which will enable ENIQ to maintain its role as one of the main contributors to today's global qualification codes and guidelines for ISI.

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)

Qualification of the system for thermal coating rehabilitation in situ of oil pipeline in operation; Qualificacao de sistema de reabilitacao in situ de revestimento termico para oleodutos

Energy Technology Data Exchange (ETDEWEB)

Koebsch, Andre; Correa, Anyr Rosa; Cabral, Glaucia Brazuna; Castanheiras Junior, Wilson Gil [PETROBRAS, Rio de Janeiro, RJ (Brazil); Oliver, Joao Hipolito de Lima; Pinto, Mucio Eduardo Amarante Costa [PETROBRAS Transporte S.A. (TRANSPETRO), Rio de Janeiro, RJ (Brazil)

2005-07-01

The transfer of some derived products of petroleum with high viscosity is accomplished with the same ones heated up. These buried pipelines are provided of Thermal Isolation System (TIS). Those TIS are composed with a polyurethane foam layer (PU) that is externally protected by polyethylene layer (PE). The acids production was generated by the deterioration of TIS. This associated with an absence of anticorrosive coating on the pipeline cause the corrosion with its thickness loss and consequently it's endangered. The rehabilitation of the existent TIS was done necessary to control this corrosive process, by reason of the Cathodic Protection System usually used in complement to the anticorrosive coating does not work on this TIS. A TIS rehabilitation process with the pipeline in operation was specified by PETROBRAS - ENGINEER and TRANSPETRO. It's qualified and was composed by two stages: Pre-qualification: tests in factory using pipes with original TIS and operating with hot water to 85 deg C. This stage was composed by the removal of original TIS, pipe surface preparation, application and tests on the anticorrosive coating, application and tests of the PU foam and application and tests of the PE casing. Qualification: stage composed by the application in field of the new TIS in a thousand meters of the pipeline OBATI-SP, operated by TRANSPETRO, and tests of the pipe assembly. This work presents the results of the Qualification for the rehabilitation of the thermal coating. It achieves the quality level demanded by PETROBRAS - Engineer and TRANSPETRO. (author)

Data Qualification Report For: Thermodynamic Data File, DATA0.YMP.R0 For Geochemical Code, EQ3/6?

International Nuclear Information System (INIS)

P.L. Cloke

2000-09-01

The objective of this work is to evaluate the adequacy of chemical thermodynamic data provided by Lawrence Livermore National Laboratory (LLNL) as DataO.ymp.ROA in response to an input request submitted under AP-3.14Q. This request specified that chemical thermodynamic data available in the file, Data0.com.R2, be updated, improved, and augmented for use in geochemical modeling used in Process Model Reports (PMRs) for Engineered Barrier Systems, Waste Form, Waste Package, Unsaturated Zone, and Near Field Environment, as well as for Performance Assessment. The data are qualified in the temperature range 0 to 100 C. Several Data Tracking Numbers (DTNs) associated with Analysis/Model Reports (AMR) addressing various aspects of the post-closure chemical behavior of the waste package and the Engineered Barrier System that rely on EQ316 outputs to which these data are used as input, are Principal Factor affecting. This qualification activity was accomplished in accordance with the AP-SIII.2Q using the Technical Assessment method. A development plan, TDP-EBS-MD-000044, was prepared in accordance with AP-2.13Q and approved by the Responsible Manager. In addition, a Process Control Evaluation was performed in accordance with AP-SV.1Q. The qualification method, selected in accordance with AP-SIII.2Q, was Technical Assessment. The rationale for this approach is that the data in File Data0.com.R2 are considered Handbook data and therefore do not themselves require qualification. Only changes to Data0.com.R2 required qualification. A new file has been produced which contains the database Data0.ymp.R0, which is recommended for qualification as a result of this action. Data0.ymp.R0 will supersede Data0.com.R2 for all Yucca Mountain Project (YMP) activities

Results of the PRDA 35 qualification tests of the Motorola concentrating photovoltaic module

Energy Technology Data Exchange (ETDEWEB)

Pritchard, D.A.

1981-10-01

A passively-cooled, Fresnel lens, concentrating photovoltaic module, designed and built by Motorola, Incorporated, was tested to the PRDA 35 specifications. The PRDA 35 module test program is described. Physical, electrical, and thermal characteristics of the module are presented. Module performance is shown using multiple linear regression techniques: some change was measured after environmental exposure. In addition, sample cell assemblies were evaluated for effects of severe environmental conditions. Results presented herein show the module has met the qualification goals.

SLUDGE WASHING AND DEMONSTRATION OF THE DWPF FLOWSHEET IN THE SRNL SHIELDED CELLS FOR SLUDGE BATCH 7A QUALIFICATION

Energy Technology Data Exchange (ETDEWEB)

Pareizs, J.; Billings, A.; Click, D.

2011-07-08

Waste Solidification Engineering (WSE) has requested that characterization and a radioactive demonstration of the next batch of sludge slurry (Sludge Batch 7a*) be completed in the Shielded Cells Facility of the Savannah River National Laboratory (SRNL) via a Technical Task Request (TTR). This characterization and demonstration, or sludge batch qualification process, is required prior to transfer of the sludge from Tank 51 to the Defense Waste Processing Facility (DWPF) feed tank (Tank 40). The current WSE practice is to prepare sludge batches in Tank 51 by transferring sludge from other tanks. Discharges of nuclear materials from H Canyon are often added to Tank 51 during sludge batch preparation. The sludge is washed and transferred to Tank 40, the current DWPF feed tank. Prior to transfer of Tank 51 to Tank 40, SRNL simulates the Tank Farm and DWPF processes with a Tank 51 sample (referred to as the qualification sample). Sludge Batch 7a (SB7a) is composed of portions of Tanks 4, 7, and 12; the Sludge Batch 6 heel in Tank 51; and a plutonium stream from H Canyon. SRNL received the Tank 51 qualification sample (sample ID HTF-51-10-125) following sludge additions to Tank 51. This report documents: (1) The washing (addition of water to dilute the sludge supernate) and concentration (decanting of supernate) of the SB7a - Tank 51 qualification sample to adjust sodium content and weight percent insoluble solids to Tank Farm projections. (2) The performance of a DWPF Chemical Process Cell (CPC) simulation using the washed Tank 51 sample. The simulation included a Sludge Receipt and Adjustment Tank (SRAT) cycle, where acid was added to the sludge to destroy nitrite and reduce mercury, and a Slurry Mix Evaporator (SME) cycle, where glass frit was added to the sludge in preparation for vitrification. The SME cycle also included replication of five canister decontamination additions and concentrations. Processing parameters were based on work with a non

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

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.

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.

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

Energy Technology Data Exchange (ETDEWEB)

Deaton, K.

1995-02-01

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

The qualification of electrical components and instrumentations relevant to safety; La qualificazione dei componenti elettrici e di strumentazione rilevanti per la sicurezza

Energy Technology Data Exchange (ETDEWEB)

Zambardi, F [ENEA - Direzione Sicurezza Nucleare e Protezione Sanitaria, Divisione Sistemi Elettrici e Strumentazione, Rome (Italy)

1989-03-15

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

The new lattice code Paragon and its qualification for PWR core applications

International Nuclear Information System (INIS)

Ouisloumen, M.; Huria, H.C.; Mayhue, L.T.; Smith, R.M.; Kichty, M.J.; Matsumoto, H.; Tahara, Y.

2003-01-01

Paragon is a new two-dimensional transport code based on collision probability with interface current method and written entirely in Fortran 90/95. The qualification of Paragon has been completed and the results are very good. This qualification included a number of critical experiments. Comparisons to the Monte Carlo code MCNP for a wide variety of PWR assembly lattice types were also performed. In addition, Paragon-based core simulator models have been compared against PWR plant startup and operational data for a large number of plants. Some results of these calculations and also comparisons against models developed with a licensed Westinghouse lattice code, Phoenix-P, are presented. The qualification described in this paper provided the basis for the qualification of Paragon both as a validated transport code and as the nuclear data source for core simulator codes

Staffing, qualification and organization for centralized and decentralized training

International Nuclear Information System (INIS)

Holyoak, R.H.

1985-01-01

This paper covers an extensive area. First a brief history of the training at Commonwealth Edison is presented so that the reader can get some idea of why some of the problems mentioned exist. Next is a discussion of the centralized and decentralized Commonwealth Edison production training organization. A brief review of the development of the Instructor Qualification Program and the training of instructors follows. Finally, a review of the problems and some solutions related to managing a centralized/decentralized training system is included

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

International Nuclear Information System (INIS)

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

2002-01-01

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

Rover Low Gain Antenna Qualification for Deep Space Thermal Environments

Science.gov (United States)

Ramesham, Rajeshuni; Amaro, Luis R.; Brown, Paula R.; Usiskin, Robert; Prater, Jack L.

2013-01-01

A method to qualify the Rover Low Gain Antenna (RLGA) for use during the Mars Science Laboratory (MSL) mission has been devised. The RLGA antenna must survive all ground operations, plus the nominal 670 Martian sol mission that includes the summer and winter seasons of the Mars thermal environment. This qualification effort was performed to verify that the RLGA design, its bonding, and packaging processes are adequate. The qualification test was designed to demonstrate a survival life of three times more than all expected ground testing, plus a nominal 670 Martian sol missions. Baseline RF tests and a visual inspection were performed on the RLGA hardware before the start of the qualification test. Functional intermittent RF tests were performed during thermal chamber breaks over the course of the complete qualification test. For the return loss measurements, the RLGA antenna was moved to a test area. A vector network analyzer was calibrated over the operational frequency range of the antenna. For the RLGA, a simple return loss measurement was performed. A total of 2,010 (3 670 or 3 times mission thermal cycles) thermal cycles was performed. Visual inspection of the RLGA hardware did not show any anomalies due to the thermal cycling. The return loss measurement results of the RLGA antenna after the PQV (Package Qualification and Verification) test did not show any anomalies. The antenna pattern data taken before and after the PQV test at the uplink and downlink frequencies were unchanged. Therefore, the developed design of RLGA is qualified for a long-duration MSL mission.

Leaving school without qualifications and mental health problems to age 30.

Science.gov (United States)

Fergusson, David M; McLeod, Geraldine F H; Horwood, L John

2015-03-01

To examine the associations between leaving school without qualifications and subsequent mental health to age 30, using data gathered over the course of a 30-year longitudinal study. Data were gathered over the course of a 30-year study (Christchurch Health and Development Study) of a birth cohort of 1265 children, born in Christchurch in 1977. This cohort has been studied on 22 occasions from birth to age 30. As part of this study, information was gathered on: (a) school leaving qualifications, (b) mental health problems from 18 to 30; and (c) prospectively assessed childhood and adolescent factors including: child and family background; family violence and child abuse; and adolescent mental health problems. Leaving school without qualifications was associated with increased risks of subsequent: major depression (OR = 1.37 at 95 % CI 1.05-1.78, p = 0.019); anxiety disorder (OR = 1.99 at 95 % CI 1.55-2.57, p mental health problems) reduced these associations substantially and to the point of statistical non-significance. The findings of this study suggest that there was no direct causal association between leaving school without qualifications and subsequent mental health problems. Associations were explained by the linkages between leaving school without qualifications and: child and family social background; and mental health around the point of school leaving.

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…

PROJECT, MANUFACTURING AND QUALIFICATION OF MACHINE TO ROTARY BENDING OF NITI SUPERELASTIC WIRES IN FATIGUE TESTS

Directory of Open Access Journals (Sweden)

William Marcos Muniz Menezes

2014-03-01

Full Text Available In this work it was developed a rotating bending apparatus for fatigue tests of superelastic NiTi wires, and other materials with high elasticity. It was evaluated the performance, robustness, operability, and reliability through testing of 1 mm thick stainless steel wires. This device is mounted on a steel frame and features semiautomatic rotation speed control, time and testing bath temperature for sample immersion. The equipment qualification tests were performed controlling the following parameters: deformation of the wire, power level and ambient temperature. The results indicated lower discrepancies for the following parameters evaluated: number of cycles in fatigue life, rotation speed, the bath temperature and arc angle of rupture. Besides the reliability, the robustness and operability of the equipment also meet the purpose of the research as evidenced by the small number of failures in the qualification tests and calibration.

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

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...

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.

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

Analysis System (NDMAS). The AGR 3/4 data streams addressed in this report include thermocouple (TC) temperatures, sweep gas data (flow rates, pressure, and moisture content), and Fission Product Monitoring System (FPMS) data (release rates, release to birth rate ratios [R/Bs], and particle failure counts) for each of the twelve capsules in the AGR 3/4 experiment. During Outage Cycle 155A, fourteen flow meters were installed downstream from fourteen FPMS monitors to measure flows from the monitors; qualification status of these data are also included in the report. The final data qualification status for these data streams is determined by a Data Review Committee (DRC) composed of AGR technical leads, Sitewide Quality Assurance (QA), and NDMAS analysts. For ATR Cycles 151A through 154B, the DRC convened on February 12, 2014, reviewed the data acquisition process, and considered whether the data met the requirements for data collection as specified in QA approved INL ART TDO data collection plans. The DRC also examined the results of NDMAS data testing and statistical analyses, and confirmed the qualification status of the data as given in this report. The qualification status of AGR-3/4 irradiation data during the first six cycles were previously reported in INL/EXT-14-31186 document. This report presents data qualification status for the entire AGR-3/4 irradiation.

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

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.

Design and qualification testing of a strontium-90 fluoride heat source

International Nuclear Information System (INIS)

Fullam, H.T.

1981-12-01

The Strontium Heat Source Development Program began at the Pacific Northwest Laboratory (PNL) in 1972 and is scheduled to be completed by the end of FY-1981. The program is currently funded by the US Department of Energy (DOE) By-Product Utilization Program. The primary objective of the program has been to develop the data and technology required to permit the licensing of power systems for terrestrial applications that utilize 90 SrF 2 -fueled radioisotope heat sources. A secondary objective of the program has been to design and qualification-test a general purpose 90 SrF 2 -fueled heat source. The effort expended in the design and testing of the heat source is described. Detailed information is included on: heat source design, licensing requirements, and qualification test requirements; the qualification test procedures; and the fabrication and testing of capsules of various materials. The results obtained in the qualification tests show that the outer capsule design proposed for the 90 SrF 2 heat source is capable of meeting current licensing requirements when Hastelloy S is used as the outer capsule material. The data also indicate that an outer capsule of Hastelloy C-4 would probably also meet licensing requirements, although Hastelloy S is the preferred material. Therefore, based on the results of this study, the general purpose 90 SrF 2 heat source will consist of a standard WESF Hastelloy C-276 inner capsule filled with 90 SrF 2 and a Hastelloy S outer capsule having a 2.375-in. inner diameter and 0.500-in. wall thickness. The end closures for this study, the general purpose 90 SrF 2 heat a Hastelloy S outer capsule having a 2.375-in. inner diameter and 0.500-in. wall thickness. The end closures for the outer capsule will utilize an interlocking joint design requiring a 0.1-in. penetration closure weld

14 CFR 91.1089 - Qualifications: Check pilots (aircraft) and check pilots (simulator).

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 2 2010-01-01 2010-01-01 false Qualifications: Check pilots (aircraft) and check pilots (simulator). 91.1089 Section 91.1089 Aeronautics and Space FEDERAL AVIATION ADMINISTRATION... RULES Fractional Ownership Operations Program Management § 91.1089 Qualifications: Check pilots...

Test Plan for Rotary Mode Core Sample Truck Grapple Hoist Level Wind System

Energy Technology Data Exchange (ETDEWEB)

BOGER, R.M.

1999-12-09

A Grapple Hoist Assembly is currently used on the Rotary Mode Core Sampling Trucks (RMCSTs) to actuate the sampler and retrieve the pintle rod during sampling operations. The hoist assembly includes a driven drum approximately two inches wide and six inches in diameter that rotates to pay out or reel in the 5/32-in. cable The current Grapple Hoist Assembly, detailed on drawing H-2-690057, is prone to ''bird nesting'' the cable on the drum. ''Bird nesting'' is a condition in which the cable does not wind onto the drum in a uniformly layered manner, but winds in a random fashion where the cable essentially ''piles up'' inappropriately on the drum and, on some occasions, winds on the drum drive shaft. A system to help control this ''bird nesting'' problem has been designed as an addition to the existing components of the Grapple Hoist Assembly. The new design consists of a mechanism that is timed with, and driven by, the shaft that drives the drum. This mechanism traverses back and forth across the width of the drum to lay the cable on the drum in a uniformly layered manner. This test plan establishes the acceptance criteria, test procedure and test conditions It also describes the test apparatus necessary to verify the adequacy of the level wind system design. The test is defined as qualification testing (LMHC 1999b) and as such will be performed at conditions beyond the parameters that the Grapple Hoist Assembly is allowed to operate by the Safety Equipment List (SEL)(LMHC 1998).

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

Qualifications, Discrimination, or Assimilation? An Extended Framework for Analysing Immigrant Wage Gaps

DEFF Research Database (Denmark)

Nielsen, Helena Skyt; Rosholm, Michael; Smith, Nina

2001-01-01

separate wage equations for natives and a number of immigrant groups using panel data sample selection models. Based on the estimations, we find that the immigrant wage gap is caused by a lack of qualifications and incomplete assimilation, and that a large fraction of that gap would disappear if only......In this paper, we analyze immigrant wage gaps and propose an extension of the traditional wage decomposition technique, which is a synthesis from two strains of literature on ethnic/immigrant wage differences, namely the 'assimilation literature' and the 'discrimination literature'. We estimate...

Qualifications, Discrimination, or Assimilation? An Extended Framework for Analysing Immigrant Wage Gaps

DEFF Research Database (Denmark)

Nielsen, Helena Skyt; Rosholm, Michael; Smith, Nina

separate wage equations for natives and a number of immigrant groups using panel data sample selection models. Based on the estimations, we find that the immigrant wage gap is caused by a lack of qualifications and incomplete assimilation, and that a large fraction of that gap would disappear if only......In this paper, we analyze immigrant wage gaps and propose an extension of the traditional wage decomposition technique, which is a synthesis from two strains of literature on ethnic/immigrant wage differences, namely the 'assimilation literature' and the 'discrimination literature'. We estimate...

Who Can Be President of the United States?: Candidate Hillary Clinton and the Problem of Statutory Qualifications

Directory of Open Access Journals (Sweden)

Tillman Seth Barrett

2016-04-01

Full Text Available Qualifications for public office restrict democratic choice, but such restrictions have a long pedigree in many jurisdictions. For example, the U.S. Constitution sets out qualifications for elected federal officials: i.e., Representative, Senator, President, and Vice President. Qualifications for those positions include provisions relating to age, citizenship, and residence. It has been long debated whether these textual qualifications are exclusive (i.e., floors and ceilings or whether they are merely floors, which can be supplemented by additional qualifications imposed by Congress or by the States.

Qualification of cables to IEEE standards 323-1974 and 383-1974

International Nuclear Information System (INIS)

Hosticka, C.; Kingsbury, E.R.; Bruhin, A.C.

1980-01-01

Wire and Cable manufacturers generally qualify products for class IE application by envelope type testing to user specifications and environmental conditions recommended by IEEE Standards 323-1974 and 383-1974. The General Electric Wire and Cable Business Department recently completed two such qualification programs. Cable constructions tested were 600V control cables and 600 V, 2kV, and 15kV power cables insulated with flame resistant mineral filled crosslinked polyethylene. The 15kV samples included taped field splices. In the second test program, the steam pressure-temperature profile included a simulated main steam line break. Test specimens were wrapped on grounded mandrels and were electrically loaded throughout the simulated LOCA tests. After completion of environmental testing, samples were subjected to the IEEE 383 simulated post-LOCA test. 6 refs

Qualification of cables to IEEE standards 323-1974 and 383-1974

International Nuclear Information System (INIS)

Hosticka, C.; Kingsbury, E.R.; Bruhin, A.C.

1980-01-01

Wire and Cable manufacturers generally qualify products for class IE application by envelope type testing to user specifications and environmental conditions recommended by IEEE Standards 323-1974 and 383-1974. The General Electric Wire and Cable Business Department recently completed two such qualification programs. Cable constructions tested were 600V control cables and 600 V, 2KV, and 15KV power cables insulated with flame resistant mineral filled crosslinked polyethylene. The 15KV samples included taped field splices. In the second test program, the steam pressure-temperature profile included a simulated main steam line break. Test specimens were wrapped on grounded mandrels and were electrically loaded throughout the simulated LOCA tests. After completion of environmental testing, samples were subjected to the IEEE 383 simulated post-LOCA test. 6 refs

Data Qualification Report For: Thermodynamic Data File, DATA0.YMP.R0 For Geochemical Code, EQ3/6 

Energy Technology Data Exchange (ETDEWEB)

P.L. Cloke

2001-10-16

The objective of this work is to evaluate the adequacy of chemical thermodynamic data provided by Lawrence Livermore National Laboratory (LLNL) as DataO.ymp.ROA in response to an input request submitted under AP-3.14Q. This request specified that chemical thermodynamic data available in the file, Data0.com.R2, be updated, improved, and augmented for use in geochemical modeling used in Process Model Reports (PMRs) for Engineered Barrier Systems, Waste Form, Waste Package, Unsaturated Zone, and Near Field Environment, as well as for Performance Assessment. The data are qualified in the temperature range 0 to 100 C. Several Data Tracking Numbers (DTNs) associated with Analysis/Model Reports (AMR) addressing various aspects of the post-closure chemical behavior of the waste package and the Engineered Barrier System that rely on EQ316 outputs to which these data are used as input, are Principal Factor affecting. This qualification activity was accomplished in accordance with the AP-SIII.2Q using the Technical Assessment method. A development plan, TDP-EBS-MD-000044, was prepared in accordance with AP-2.13Q and approved by the Responsible Manager. In addition, a Process Control Evaluation was performed in accordance with AP-SV.1Q. The qualification method, selected in accordance with AP-SIII.2Q, was Technical Assessment. The rationale for this approach is that the data in File Data0.com.R2 are considered Handbook data and therefore do not themselves require qualification. Only changes to Data0.com.R2 required qualification. A new file has been produced which contains the database Data0.ymp.R0, which is recommended for qualification as a result of this action. Data0.ymp.R0 will supersede Data0.com.R2 for all Yucca Mountain Project (YMP) activities.

URGENT AND LAG PSYCHOPHYSIOLOGICAL EFFECTS NEUROFEEDBACK IN SPORTSMEN OF HIGH QUALIFICATION

Directory of Open Access Journals (Sweden)

O. V. Kaigorodtseva

2013-01-01

Full Text Available The article provides a comparative analysis of the psychophysiological state of sportsmen of high qualification within one year after the course neurofeedback. These data demonstrated that high qualification sportsmen physiological effects of training persist throughout the year and depend on the ability to arbitrarily increase the power of the alpha rhythm of the brain.

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

Current advances and strategies towards fully automated sample preparation for regulated LC-MS/MS bioanalysis.

Science.gov (United States)

Zheng, Naiyu; Jiang, Hao; Zeng, Jianing

2014-09-01

Robotic liquid handlers (RLHs) have been widely used in automated sample preparation for liquid chromatography-tandem mass spectrometry (LC-MS/MS) bioanalysis. Automated sample preparation for regulated bioanalysis offers significantly higher assay efficiency, better data quality and potential bioanalytical cost-savings. For RLHs that are used for regulated bioanalysis, there are additional requirements, including 21 CFR Part 11 compliance, software validation, system qualification, calibration verification and proper maintenance. This article reviews recent advances in automated sample preparation for regulated bioanalysis in the last 5 years. Specifically, it covers the following aspects: regulated bioanalysis requirements, recent advances in automation hardware and software development, sample extraction workflow simplification, strategies towards fully automated sample extraction, and best practices in automated sample preparation for regulated bioanalysis.

Design compliance matrix waste sample container filling system for nested, fixed-depth sampling system

International Nuclear Information System (INIS)

BOGER, R.M.

1999-01-01

This design compliance matrix document provides specific design related functional characteristics, constraints, and requirements for the container filling system that is part of the nested, fixed-depth sampling system. This document addresses performance, external interfaces, ALARA, Authorization Basis, environmental and design code requirements for the container filling system. The container filling system will interface with the waste stream from the fluidic pumping channels of the nested, fixed-depth sampling system and will fill containers with waste that meet the Resource Conservation and Recovery Act (RCRA) criteria for waste that contains volatile and semi-volatile organic materials. The specifications for the nested, fixed-depth sampling system are described in a Level 2 Specification document (HNF-3483, Rev. 1). The basis for this design compliance matrix document is the Tank Waste Remediation System (TWRS) desk instructions for design Compliance matrix documents (PI-CP-008-00, Rev. 0)

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.

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.

Results Of Analytical Sample Crosschecks For Next Generation Solvent Extraction Samples Isopar L Concentration And pH

International Nuclear Information System (INIS)

Peters, T.; Fink, S.

2011-01-01

As part of the implementation process for the Next Generation Cesium Extraction Solvent (NGCS), SRNL and F/H Lab performed a series of analytical cross-checks to ensure that the components in the NGCS solvent system do not constitute an undue analytical challenge. For measurement of entrained Isopar(reg s ign) L in aqueous solutions, both labs performed similarly with results more reliable at higher concentrations (near 50 mg/L). Low bias occurred in both labs, as seen previously for comparable blind studies for the baseline solvent system. SRNL recommends consideration to use of Teflon(trademark) caps on all sample containers used for this purpose. For pH measurements, the labs showed reasonable agreement but considerable positive bias for dilute boric acid solutions. SRNL recommends consideration of using an alternate analytical method for qualification of boric acid concentrations.

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

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)

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.

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...

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

"EU-on-Demand": Developing National Qualifications Frameworks in a Multi-Level Context

Science.gov (United States)

Elken, Mari

2016-01-01

The development of comprehensive national qualifications frameworks (NQFs) across Europe has been sparked by the introduction of the European Qualifications Framework (EQF) in 2008. Taking an institutional perspective, this article examines the development of NQFs in three countries, in light of developments that have taken place at the European…

Planetary Sample Caching System Design Options

Science.gov (United States)

Collins, Curtis; Younse, Paulo; Backes, Paul

2009-01-01

Potential Mars Sample Return missions would aspire to collect small core and regolith samples using a rover with a sample acquisition tool and sample caching system. Samples would need to be stored in individual sealed tubes in a canister that could be transfered to a Mars ascent vehicle and returned to Earth. A sample handling, encapsulation and containerization system (SHEC) has been developed as part of an integrated system for acquiring and storing core samples for application to future potential MSR and other potential sample return missions. Requirements and design options for the SHEC system were studied and a recommended design concept developed. Two families of solutions were explored: 1)transfer of a raw sample from the tool to the SHEC subsystem and 2)transfer of a tube containing the sample to the SHEC subsystem. The recommended design utilizes sample tool bit change out as the mechanism for transferring tubes to and samples in tubes from the tool. The SHEC subsystem design, called the Bit Changeout Caching(BiCC) design, is intended for operations on a MER class rover.

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…

NRC Information No. 89-23: Environmental qualification of Litton-Veam CIR series electrical connectors

International Nuclear Information System (INIS)

Rossi, C.E.

1992-01-01

Litton-Veam CIR series multi-pin electrical connectors are used in core exit thermocouple (CET) and reactor vessel level monitoring (RVLM) systems supplied to numerous plants by Combustion Engineering, Inc., and are used in other applications in at least three additional plants. A proprietary qualification test report has been used to document environmental qualification of the connectors for loss of coolant accident (LOCA) conditions in the CE-supplied systems. During LOCA testing, the connector face seal gasket was completely degraded and elastomeric inserts interacted with simulated containment spray solution which leaked into the connector. Insulation resistances near 1,000 ohms were measured. CE has performed analyses to show that resultant errors are acceptable in CE-supplied CET and RVLM system thermocouple circuits. However, the moisture ingress and resultant low insulation resistances are not acceptable for heater circuits in the RVLM. For that application, CE developed two remedies; one is a clamp, and the other is a new connector design. CE has advised that one of these remedies has been used for all of the RVLM heater circuits. Unmodified CIR connectors are believed to be still in use in other applications

Core sampling system spare parts assessment

International Nuclear Information System (INIS)

Walter, E.J.

1995-01-01

Soon, there will be 4 independent core sampling systems obtaining samples from the underground tanks. It is desirable that these systems be available for sampling during the next 2 years. This assessment was prepared to evaluate the adequacy of the spare parts identified for the core sampling system and to provide recommendations that may remediate overages or inadequacies of spare parts

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.

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…

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...

Quality Assurance and Qualifications Frameworks: Exchanging Good Practice. ENQA Workshop Report 21

Science.gov (United States)

Blomqvist, Carita; Donohoe, Tony; Kelo, Maria; Linde, Karin Jarplid; Llavori, Rafael; Maguire, Bryan; Metz, David; Sanchez, Teresa

2012-01-01

The theme of qualifications frameworks and their relation to quality assurance is gaining urgency in the European scene as more and more countries are completing their national qualifications frameworks and quality assurance agencies need to take important decisions on how to implement them. Some of the key features of the qualifications…

10 CFR 50.120 - Training and qualification of nuclear power plant personnel.

Science.gov (United States)

2010-01-01

... 10 Energy 1 2010-01-01 2010-01-01 false Training and qualification of nuclear power plant... Training and qualification of nuclear power plant personnel. (a) Applicability. The requirements of this... each holder of a combined license issued under part 52 of this chapter for a nuclear power plant of the...

First experiment on LMJ facility: pointing and synchronisation qualification, sequences qualification

Science.gov (United States)

Henry, Olivier; Bretheau, Dominique; Luttmann, Michel; Graillot, Herve; Ferri, Michel; Seguineau, Frederic; Bar, Emmanuel; Patissou, Loic; Canal, Phillipe; Sautarel, Françoise; Tranquille Marques, Yves; Raffestin, Didier

2016-10-01

The LMJ (Laser mega Joule) facility at the CESTA site (Aquitaine, France) is a tool designed to deliver up to 1.2 MJ at 351 nm for plasma experiments. The experiment system will include 11 diagnostics: UV and X energy balances, imagers (Streak and stripe camera, CCD), spectrometers, and a Visar/pyrometer. The facility must be able to deliver, within the hour following the shot, all the results of the plasma diagnostics, alignment images and laser diagnostic measurements. These results have to be guaranteed in terms of conformity to the request and quality of measurement. The end of 2014 was devoted to the qualification of system pointing on target and synchronization within and between beams. The shots made with one chain (divided in 2 quads - 8 laser beams) have achieved 50 µm of misalignment accuracy (chain and quad channel) and a synchronization accuracy in the order of 50 ps. The performances achieved for plasma diagnostic (in the order of less 100 µm of alignment and timing accuracy less than 150 ps) comply with expectations. At the same time the first automatic sequences were tested. They allowed a shot on target every 6h:30 and in some case twice a day by reducing preparation actions, leading to a sequence of 4h:00. These shooting sequences are managed by an operating team of 7 people helped by 3 people for security aspects.

Differences in the performance of health officers at the workplace according to their qualifications.

Science.gov (United States)

Kim, Yeong-Kwang; Yoon, Jin-Ha; Lee, Wanhyung; Kim, Jihyun; Lim, Sung-Shil; Won, Jong-Uk

2018-01-01

Health officers are an integral part of the occupational health service, and there have been studies to identify and improve the role of health officers in the workplace in order to improve the level of health care in the workplace. This study aimed to determine the contribution of health officers to the role of a health officer as prescribed by law and the percentage of health management work performed during work according to their qualifications. Questionnaires were distributed to a total of 4584 workplaces where health officers were hired, and a total of 806 copies (17.58%) were returned. Of these, 336 questionnaires were finally analyzed, after excluding questionnaires missing the main variables. Using the data, the difference of role contributions and the percentage of health care work performed during the whole day according to the qualification of the health officer was analyzed. Nurses were highly rated in the field of medical care, and industrial hygienists and air environmental engineers were highly rated in terms of chemicals and risk factor management. The percentage of health care work performed during the whole day differed according to the size of the workplace and industrial classification, but it was generally the lowest among air environmental engineers. Health officers play a very different role in the workplace depending on their qualification, and they need support for areas of other qualification. In order to effectively manage the health of the staff at a workplace, it is necessary to consider the development of a support system for small- and medium-sized enterprises and adjust the conditions of employment of the health officer according to the law.

DATA QUALIFICATION REPORT: DATA QUALIFICATION REPORT FOR 1991 1:1200 TOPOGRAPHIC MAPS FOR USE ON THE YUCCA MOUNTAIN PROJECT

International Nuclear Information System (INIS)

Knop, M.F.; Grant, T.A.; Bonisolli, R.W.

2005-01-01

This Data Qualification Report (DQR) is prepared in accordance with the provisions of AP-SIII.2Q, Rev. 0, ICN 3, Qualification of Unqualified Data and the Documentation of Rationale for Accepted Data and Data Qualification Plan for 1991 Topographic Maps 1:1200 Scale for use on the Yucca Mountain Project, DQP-WHS-CI-000001, Rev. 00 (BSC 2002a). This DQR presents an evaluation of a set of 90 topographic sheets at 1:1200 scale (and an associated electronic file) that covers an approximate 18 square mile area surrounding the proposed Yucca Mountain Project repository surface facilities location in Midway Valley, Nevada. These maps, that require qualification, are now being used to determine the physical characteristics of watershed sub-areas, interconnecting channels, and drainage channel cross-sections for hydrologic engineering studies of the north portal pad and vicinity. The result of this effort is to qualify one data tracking number (DTN) containing the electronic version of the mapping data. This DTN is: M09906COV98462.000. Coverage: TOP02FTS. The underlying quality assurance (QA) issue associated with these topographic maps is that the maps were originally designated as not for use in the design of items important to safety, waste isolation, and/or of programmatic importance. The maps were therefore generated outside the U.S. Department of Energy Office of Civilian Radioactive Waste Management (OCRWM) QA program. Based on a comparison with corroborating information, this report concludes that the topographic maps are qualified. The comparison found that the mapping was reasonably accurate when compared with other mapping and survey data within the coverage area of the maps. Relative map accuracy was found to be very good and suitable for the hydrologic engineering studies being considered. Absolute accuracy is good but could not be demonstrated to comply with national map accuracy standards. Point locations that require high absolute accuracy should be

78 FR 25488 - Qualification Tests for Safety-Related Actuators in Nuclear Power Plants

Science.gov (United States)

2013-05-01

... Nuclear Power Plants AGENCY: Nuclear Regulatory Commission. ACTION: Draft regulatory guide; request for... regulatory guide (DG), DG-1235, ``Qualification Tests for Safety-Related Actuators in Nuclear Power Plants... entitled ``Qualification Tests for Safety-Related Actuators in Nuclear Power Plants'' is temporarily...

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

QUALIFICATIONS FRAMEWORKS LEADING TO REFORMS IN EAST EUROPEAN EDUCATION

Directory of Open Access Journals (Sweden)

Arjen Vos

2014-01-01

Full Text Available The paper examines the evolution of qualifications frameworks across Europe. Five years ago, it was not clear if the discussions on national qualification frameworks (NQF in Eastern Europe would lead to the new standards and qualifications development, or initiate the reforms in education and training. Now, there is evidence of more countries using the NQFs to promote a dialogue between the public and private sectors on the expected outcomes of educational process. In some countries, the private sector has even taken the lead in the NQF discussions, being increasingly involved in their implementation. This is a fundamentally new paradigm in education policies and a cornerstone of the demand driven education and training. Each country is following its own patterns while moving to the comparable results. However, this is just the initial stage of NQF implementation. The author regards learning by doing and the local expertise expansion as the key challenges of the coming years. Although the reforms take time, they increasingly tend to become a shared public and private responsibility.

Preliminary Hanford Waste Vitrification Plan Waste Form Qualification Plan

International Nuclear Information System (INIS)

Nelson, J.L.

1987-09-01

This Waste Form Qualification Plan describes the waste form qualification activities that will be followed during the design and operation of the Hanford Waste Vitrification Plant to ensure that the vitrified Hanford defense high-level wastes will meet the acceptance requirements of the candidate geologic repositories for nuclear waste. This plan is based on the defense waste processing facility requirements. The content of this plan is based on the assumption that the Hanford Waste Vitrification Plant high-level waste form will be disposed of in one of the geologic repository projects. Proposed legislation currently under consideration by Congress may change or delay the repository site selection process. The impacts of this change will be assessed as details of the new legislation become available. The Plan describes activities, schedules, and programmatic interfaces. The Waste Form Qualification Plan is updated regularly to incorporate Hanford Waste Vitrification Plant-specific waste acceptance requirements and to serve as a controlled baseline plan from which changes in related programs can be incorporated. 10 refs., 5 figs., 5 tabs

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.

Qualification of γ-heating calculation in nuclear reactors

International Nuclear Information System (INIS)

Ravaux, Simon

2013-01-01

During the last few years, the γ-heating issue has gained in stature, mainly for the safety of the 3. generation reactors in which a stainless steel reflector is inserted. The purpose of this work is the qualification of the needed tools for calculation of the γ-heating in the nuclear reactors. In a nuclear reactor, all the photons are directly or indirectly produced by the neutron-matter interactions. Thus, the first phase of this work is a critical analysis of the photon production data in the standard nuclear data library. New evaluations have been proposed to the next version of the JEFF library after that some omissions have been found. They have partly been accepted for JEFF-3.2. Two particle-transport codes are currently developed in the CEA: the deterministic code APOLLO2 and the Monte Carlo code TRIPOLI4. The second part of this work is the qualification of both these codes by interpreting an integral experiment called PERLE. The experimental set-up is made by a LWR pin assembly surrounded by a stainless steel reflector in which the γ-heating is measured by Thermo-luminescent Detector (TLD). A calculation scheme has been proposed for both APOLLO2 and TRIPOLI4 in order to calculate the TLD's responses. Comparisons between calculations and measurements have shown that TRIPOLI4 gives a satisfactory estimation of the γ-heating in the reflector. These discrepancies are within the experimental 1 σ uncertainty. Before the qualification, APOLLO2 has been previously validated against TRIPOLI4 reference calculation. This validation gives an estimation of the bias due to the deterministic approximations of the transport equation resolution. The qualification has shown that the discrepancies between APOLLO2 predictions and TLD's measurements are in the same range as experimental uncertainties. (author) [fr

Index of Submarine Medical Officer’s Qualification Theses 1944-1974

Science.gov (United States)

1976-04-01

USING HYPOTHERMIA AND HYPERBARIC CXYGENATI 1972-3011 0 A CASE REPO+ HYPOBARIC HYPOXIA ABOARD A SUBMERGED SUBMARINE 1972-0014 THE EFFECTS OF ACUTE HYPOXIA...G009 LEVEL. VENTILATORY DYNAMICS UNDER HYPERBARIC STATES.= SUBMARINE MEDICAL QUALIFICATION THESES U. So NAVAL SJBMARINE MEDICAL CENTER SUBMARINE BASE...CONNECTICUT. 23 OCT 62 StJRL ____________ 1962-0019 WOO3D W.- - ____ VENTILATORY DYNAMICS UNDER HYPERBARIC STATES.= SUBMARINE MEDICAL QUALIFICATION THESES

14 CFR 121.411 - Qualifications: Check airmen (airplane) and check airmen (simulator).

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 3 2010-01-01 2010-01-01 false Qualifications: Check airmen (airplane) and... § 121.411 Qualifications: Check airmen (airplane) and check airmen (simulator). (a) For the purposes of this section and § 121.413: (1) A check airman (airplane) is a person who is qualified, and permitted...

Method for qualification of cementation processes and its application to a vibration mixer

International Nuclear Information System (INIS)

Vicente, R.; Rzyski, B.M.; Suarez, A.A.

1987-01-01

In this paper the definition of homogeneneity is discussed and methods to measure the 'degree of heterogeneity' of waste forms are proposed. These measurements are important as aids for mixing process qualification, and as tools in quality assurance procedures and in the development of waste management standards. Homogeneity is a basic quality requirement for waste forms to be accepted in final sites. It do not depend on the matrix immmobilization, rather it is one mean for qualification of the immobilization process. The proposed methods were applied to a vibration assisted mixing process and has proved to an useful mean to judge process improvements. There are many conceivable methods to evaluate homogeneity of waste forms. Some were selected as screening tests aiming at quickly reaching a promising set of process variables. Others were selected to evaluate the degree of excellence of the process in respect to product quality. These envisaged methods were: visual inspection, the use of cement dye as tracer, scanning of radioactive tracers, and measurements of variations of density, water absorption, porosity and mechanical strength across the waste form sample. The process variables were: waste-cement and water-cement ratios, mixer geometry, mixing time and vibration intensity. Some of the apparatus details were change during the experimental work in order to improve product quality. Experimental methods and results statistically analysed and compared with data obtained from samples prepared with a planetary paddle mixer, which were adopted as the homogeneity standard. (Author) [pt

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…

Qualification of an evaluated butterfly-packaged DFB laser designed for space applications

Science.gov (United States)

Tornow, S.; Stier, C.; Buettner, T.; Laurent, T.; Kneier, M.; Bru, J.; Lien, Y.

2017-11-01

An extended qualification program has proven the quality of a previously evaluated semiconductor laser diode, which is intended to be used in a subsystem for the GAIA mission. We report on results of several reliability tests performed in subgroups. The requirements of the procurement specification with respect to reliability and desired manufacturing processes were confirmed. This is an example for successful collaboration between component supplier, system integrator and payload responsible party.

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...

Seismic and environmental qualification of class IE equipment manufactured in Spain

International Nuclear Information System (INIS)

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

1978-01-01

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

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

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...

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

Qualification of NDE personnel in the nuclear industry

International Nuclear Information System (INIS)

Epps, T.N.

1984-01-01