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

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

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)

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.

IEEE Std 535-1986: IEEE standard for qualification of Class 1E lead storage batteries for nuclear power generating stations

International Nuclear Information System (INIS)

Anon.

1992-01-01

This document describes qualification methods for Class 1E lead storage batteries and racks to be used in nuclear power generating stations outside of primary containment. Qualification required in ANSI/IEEE Std 308-1980 can be demonstrated by using the procedures provided in this standard in accordance with ANSI/IEEE Std 323-1983. Battery sizing, maintenance, capacity testing, installation, charging equipment, and consideration of other type batteries are beyond the scope of this standard

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

IEEE Std 535-1979: IEEE standard for qualification of Class 1E lead storage batteries for nuclear power generating stations

International Nuclear Information System (INIS)

Anon.

1992-01-01

This document describes qualification methods for Class 1E lead storage batteries and racks to be used in nuclear power generating stations outside of primary containment. Qualification required in ANSI/IEEE Std 279-1971 and IEE Std 308-1978, can be demonstrated by using the procedures provided in this standard in accordance with IEEE Std 323-1974. Battery sizing, maintenance, capacity testing, installation, charging equipment and consideration of other type batteries are beyond the scope of this standard

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.

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)

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.

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

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

Science.gov (United States)

2015-05-20

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

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

CERN Document Server

American Society for Testing and Materials. Philadelphia

2004-01-01

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

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

Survey of NDT techniques, services, qualifications and certification of NDT personnel-preliminary results

International Nuclear Information System (INIS)

Aleta, C.R.; Kinilitan, V.E.; Lailo, R.M.

1987-01-01

This paper presented the results of a survey conducted to determine the profile of the NDT industry including its problems. A questionnaire designed in three parts 1) present practices on qualification and certification, 2) NDT equipment and 3) services and problems in NDT. Of the 36 firms contacted only 20 responded. Results indicated the following: a) most firms are engaged in four (4) main techniques, RT, UT, MT and PT. Only 2 indicated capability of ET. b) level III personnel are relatively few in number, c) most firms allow the ASNT recommendation as a basis for their qualifications and certification and are in favor of standardization of the qualification and certification process and supportive of a national center for training of NDT personnel and d) most firms perceived the lack of adequate repair/maintenance skills/facilities, followed by high cost of equipment and the lack of national standard for qualification and certification. (ELC)

An overview of reactor physics standards: Past, present and future

International Nuclear Information System (INIS)

Cokinos, D.M.

1992-07-01

This report discusses for determining key static reactor physics parameters which have been developed by groups of experts (working groups) under the aegis of ANS-19, the ANS Reactor Physics Standards Committee. Following a series of sequential reviews, augmented by feedback from potential users, a proposed standard is brought into final form by the working group before it is adopted as a formal standard by the American National Standards Institute (ANSI); Reactor Physics standards are intended to provide guidance in the performance and qualification of complex sequences of reactor calculations and/or measurements and are regularly reviewed for possible updates and/or revisions. The reactor physics standards developed to date are listed and standards now being developed by the respective working groups are also provided

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

International Nuclear Information System (INIS)

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

2011-01-01

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

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

Establishment of nuclear equipment qualification system

International Nuclear Information System (INIS)

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

2003-04-01

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

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

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

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

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

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

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

Implementation plans for the Korean certified tumor registrar qualification system.

Science.gov (United States)

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

2014-01-01

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

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

A British standard for inspection qualification - a step on the road to European harmonization

International Nuclear Information System (INIS)

Waites, C.; Leyland, K.S.; Whittle, M.J.

1993-01-01

The safety case for the Sizewell 'B' reactor requires the ultrasonic inspection of certain components to be validated independently of those directly responsible for reactor construction and operation. This paper describes how this has been done. To illustrate the way in which validation needs to be tailored to particular requirements, an example is given involving the application of a time-of-flight detection (TOFD) technique to in-service inspection of a weld from an offshore installation. The experience gained from the application above and from other work has enabled an approach to validation to be set out in a British Standard Draft for Development. The intent is to provide a methodology within which individual validations can be developed in a consistent and coherent way. A European Methodology for Inspection Qualification also builds on this and other experience and aims to promote a common approach within Europe. The intent is to define a qualification approach to NDT which provides the necessary confidence in the test in the most cost-effective way possible. (author)

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

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

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

International Nuclear Information System (INIS)

2001-01-01

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

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

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

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

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.

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

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

International Nuclear Information System (INIS)

Anon.

1992-01-01

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

Standards for radiation protection instrumentation: design of safety standards and testing procedures

International Nuclear Information System (INIS)

Meissner, Frank

2008-01-01

This paper describes by means of examples the role of safety standards for radiation protection and the testing and qualification procedures. The development and qualification of radiation protection instrumentation is a significant part of the work of TUV NORD SysTec, an independent expert organisation in Germany. The German Nuclear Safety Standards Commission (KTA) establishes regulations in the field of nuclear safety. The examples presented may be of importance for governments and nuclear safety authorities, for nuclear operators and for manufacturers worldwide. They demonstrate the advantage of standards in the design of radiation protection instrumentation for new power plants, in the upgrade of existing instrumentation to nuclear safety standards or in the application of safety standards to newly developed equipment. Furthermore, they show how authorities may proceed when safety standards for radiation protection instrumentation are not yet established or require actualization. (author)

Seismic qualification tests of fans of the NPP of Laguna Verde U-1 and U-2

International Nuclear Information System (INIS)

Jarvio C, G.; Garcia H, E. E.; Arguelles F, R.; Vela H, A.; Naranjo U, J. L.

2013-10-01

This work presents the results of the seismic qualification tests applied to the fans that will be installed in the control panels of the three divisions of the diesel generators of the nuclear power plant (NPP) of Laguna Verde, Unit-1 and Unit-2. This seismic qualification process of the fans was carried out using two specimens that were tested in the seismic table (vibrating) of the Engineering Institute of Universidad Nacional Autonoma de Mexico (UNAM), in accordance with the requirements of the standard IEEE 344-1975, to satisfy the established requirements of seismic qualification in the technical specifications and normative documents required by the nuclear standards, in order to demonstrate its application in the diesel generators Divisions I, II and III of the NPP. The seismic qualification tests were developed on specimens that were retired of the NPP of Laguna Verde recently with a service life of 7.75 years. (Author)

Occupational scope and qualification of environment experts in public administration. Final report. Berufsfeld- und Qualifikationsanalyse fuer Umweltfachleute in der Oeffentlichen Verwaltung. Abschlussbericht

Energy Technology Data Exchange (ETDEWEB)

Brater, M; Hemmer, C; Maurus, A; Munz, C; Schluchter,

1991-12-01

The publication presents the three parts of the original report in one volume. The parts refewing to occupational qualifications consistently differentiate between occupation all specific qualification standards and those of a non-specific nature. Environmental protection is defined to be based on pollution control as a matter of engineering, pollution abatement as a matter of planning and regulatory activities, and the integrated version of the two strategies. Experts in public administration specialising in environmental protection are to be trained as experts in the following sub-areas environmental planning (innovation and strategy planning); design planning (engineering aspects); environmental law (impact statements, expert opinions, special knowledge of environmental media); enforcement of the law, licensing procedure, monitoring and supervision (efficiency evaluation); public relations (information, consultancy, education). The report presents job descriptions, qualification standards, occupational scopes and prospects for every type of qualification and education. (HSCH).

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

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

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

Standard practice for qualification of journeyman painters for application of coatings to steel surfaces of safety-related areas in nuclear facilities

International Nuclear Information System (INIS)

Anon.

1984-01-01

This practice provides a standard qualifying method for journeyman painters to verify their proficiency and ability to attain the required quality for application of specified coatings to steel surfaces in safety-related areas in a nuclear facility. Variations or simplifications of the practice set forth herein may be appropriate for special coating work such as maintenance or qualifications of equipment suppliers shop personnel. It is not the intent of this practice to mandate a singular basis for all qualifications. Evaluation of the journeyman painter being qualified in accordance with this practice, shall be by qualified agents as specified in 4.1. Reports shall be prepared as specified in Section 5, and certification as specified in Section 6. It is the intent of this practice to judge only the ability of the journeyman painter to apply specified coatings with the proper tools and equipment. This standard may involve hazardous materials, operations, and equipment

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)

Excellence in fleet combat replacement squadrons: predicting carrier qualification success

OpenAIRE

Smith, Martin P.

1988-01-01

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

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)

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

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

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...

Overview of nuclear power plant equipment qualification issues and practices

International Nuclear Information System (INIS)

Torr, K.G.

1989-01-01

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

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

International Nuclear Information System (INIS)

Anon.

1992-01-01

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

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.

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

Qualification, training, licensing and retraining of operating shift personnel in nuclear power plants. Presentation of different procedures in the countries of the European Community, Spain, Sweden, Switzerland and the USA

International Nuclear Information System (INIS)

Pfeffer, W.; Kraut, A.

1985-01-01

This study aims at evaluating and compiling the procedures to reach the necessary qualification applied in the countries of the European Community, Sweden, Spain, Switzerland and the United States of America. Additionally to the presentation of practice the report is to show similarities - as far as they were identified - and special topics or aspects worth mentioning. In the report the following topics are dealt with: tasks of the shift personnel, nomenclature for different groups of personnel; shift staffing of the control room; criteria for personnel selection when new shift staff; personnel qualification necessary for recruitment; training of shift personnel; retraining for preservation of the qualification standard; training facilities, especially simulators; licensing or authorization of shift personnel; training and education organization. The study is based on the evaluation of EC documents as well as well as general publications and reports. To check the results and to integrate some lacking information the report was discussed in a meeting of an ad hoc subgroup of the CEC working group dealing with the safety of light-water reactors, joined by specialists from Spain, Sweden and Switzerland. 121 refs

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

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.

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

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

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)

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

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)

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.

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)

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)

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

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

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.

Standard practice for qualification of journeyman painters for application of coatings to concrete surfaces of safety-related areas in nuclear facilities

International Nuclear Information System (INIS)

Anon.

1984-01-01

This practice provides a standard qualifying method for journeyman painters to verify their proficiency and ability to attain the required quality for application of specified coatings to concrete surfaces in safety-related areas in a nuclear facility. Variations or simplifications of the practice set forth herein may be appropriate for special coating work such as maintenance. It is not the intent of this practice to mandate a singular basis for all qualifications. Evaluation of the journeyman painter being qualified in accordance with this practice, shall be by qualified agents as specified in 4.1. Reports shall be prepared as specified in Section 5, and qualification as specified in Section 6. It is the intent of this practice to judge only the ability of the journeyman painter to apply specified coatings with the proper tools and equipment

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

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...

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

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.

Environmental Qualification Program for NPP Krsko

International Nuclear Information System (INIS)

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

1998-01-01

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

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

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

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...

DOE handbook: Guide to good practices for the selection, training, and qualification of shift supervisors

International Nuclear Information System (INIS)

1999-04-01

This Department of Energy (DOE) handbook is approved for use by all DOE Components and their contractors. The Handbook incorporates editorial changes to DOE-STD-1061-93, ''Guide to Good Practices for the Selection, Training, and Qualification of shift Supervisors,'' and supersedes DOE-STD-1061-93. Technical content of this Handbook has not changed from the original technical standard. Changes are primarily editorial improvements, redesignation of the standard to a Handbook, and format changes to conform with current Technical Standards Program procedures. This guide, used in conjunction with a facility-specific job analysis, provides a framework for the selection, training, qualification, and professional development of reactor facility and non-reactor nuclear facility shift supervisors. Training and qualification programs based on this guide should provide assurance that shift supervisors perform their jobs safely and competently

DOE handbook: Guide to good practices for the selection, training, and qualification of shift supervisors

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-04-01

This Department of Energy (DOE) handbook is approved for use by all DOE Components and their contractors. The Handbook incorporates editorial changes to DOE-STD-1061-93, ``Guide to Good Practices for the Selection, Training, and Qualification of shift Supervisors,`` and supersedes DOE-STD-1061-93. Technical content of this Handbook has not changed from the original technical standard. Changes are primarily editorial improvements, redesignation of the standard to a Handbook, and format changes to conform with current Technical Standards Program procedures. This guide, used in conjunction with a facility-specific job analysis, provides a framework for the selection, training, qualification, and professional development of reactor facility and non-reactor nuclear facility shift supervisors. Training and qualification programs based on this guide should provide assurance that shift supervisors perform their jobs safely and competently.

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)

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).

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.''

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...

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.)

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

Energy Technology Data Exchange (ETDEWEB)

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

2014-07-01

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

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

International Nuclear Information System (INIS)

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

2014-01-01

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

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…

IEEE Std 650-1990: IEEE standard for qualification of Class 1E static battery chargers and inverters for nuclear power generating stations

International Nuclear Information System (INIS)

Anon.

1992-01-01

Methods for qualifying static battery chargers and inverters for Class 1E installations in a mild environment outside containment in nuclear power generating stations are described. The qualification methods set forth employ a combination of type testing and analysis, the latter including a justification of methods, theories, and assumptions used. These procedures meet the requirements of IEEE Std 323-1983, IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations

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

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

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…

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.)

FPGA and Software Design for the Qualification and Automated tests for the production of CERN Digital Acquisition Boards

CERN Document Server

Laroussi, H; Lefevre, T; Degeest, A; Garcia, S; Tichon, J

The VFC-HPC is an FPGA-based multipurpose board designed to be the new standard back-end for the Beam Instrumentation (BI) Group. This contribution is aimed to give a presentation of the test and qualification system designed to be used to verify the compliance of the VFC-HPC to the specifications. We will begin by presenting the CERN, the company, its main purpose and its brief history. Afterward, we will present the VFC-HPC, the purpose of this board and its mains characteristics. We will then focus on the work done to allow the test and qualification of the VFC-HPC. This project was focused on the test and qualification of the connectivity of the board, consisting of the FMC Connector and the SFPs. This work involved making several market surveys to choose the proper test components to be used (as FMC Mezzanines), setting up a test bench, implementing optical communications through SFPs, writing Verilog firmwares, writing software test routines in Python and measuring Bit Error Rates (BER) and eye diagrams...

Standard compliance - NDE performance demonstration/inspection in the CANDU industry

International Nuclear Information System (INIS)

Choi, E.

2011-01-01

CANDU nuclear power plants are operated in 3 provinces in Canada for electric power generation. A table in the paper will show the built and operating plants in Ontario, Quebec, New Brunswick and overseas. The regulator for nuclear power in Canada is the Canadian Nuclear Safety Commission (CNSC). The CNSC holds the plant licensees accountable for compliance to CSA N285.4 for periodic inspections. The Standard basically specifies the 'what, when, where, how, how much and how frequently' NDE is to be done on pressure retaining systems and components in CANDU nuclear power plants. In inspection methods, the Standard specifies they must be non-destructive. The NDE methods were grouped into visual, dimensional, surface, volumetric and integrative. The Standard also specifies that the licensees are responsible for the performance demonstration (PD) of the adequacy of the procedures and the proficiency of the personnel. This paper describes the Standard's requirement in NDE qualification and presents a joint project participated by Canadian and overseas CANDU owners. The sub-project for NDE included providing evidence and technical justification on the adequacy of the procedures and the proficiency of the personnel. The paper describes the qualification methodology followed by the participants. This will be followed by how the participants produced Inspection Specification, tools and procedures, personnel training and qualification programs, test and qualification samples, independent peer reviews and Technical Justification. (author)

Developing competence based qualification system in the nuclear energy sector

International Nuclear Information System (INIS)

Ceclan, Mihail

2016-01-01

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

Developing competence based qualification system in the nuclear energy sector

Energy Technology Data Exchange (ETDEWEB)

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

2016-04-15

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

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...

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.

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.)

The use of case tools in OPG safety analysis code qualification

International Nuclear Information System (INIS)

Pascoe, J.; Cheung, A.; Westbye, C.

2001-01-01

Ontario Power Generation (OPG) is currently qualifying its critical safety analysis software. The software quality assurance (SQA) framework is described. Given the legacy nature of much of the safety analysis software the reverse engineering methodology has been adopted. The safety analysis suite of codes was developed over a period of many years to differing standards of quality and had sparse or incomplete documentation. Key elements of the reverse engineering process require recovery of design information from existing coding. This recovery, if performed manually, could represent an enormous effort. Driven by a need to maximize productivity and enhance the repeatability and objectivity of software qualification activities the decision was made to acquire or develop and implement Computer Aided Software Engineering (CASE) tools. This paper presents relevant background information on CASE tools and discusses how the OPG SQA requirements were used to assess the suitability of available CASE tools. Key findings from the application of CASE tools to the qualification of the OPG safety analysis software are discussed. (author)

REGULATION OF NATIONAL QUALIFICATIONS SYSTEMS

Directory of Open Access Journals (Sweden)

Anna A. Muravyeva

2014-01-01

Full Text Available The paper looks into the diverse aspects of qualifications system regulation, designed for balancing the supply and demand in the labor and educational service markets. Both the objects and mechanisms of such regulation are described. Special attention is given to institutions, involved in regulation of qualifications, and their jurisdiction. Another emphasis is on the industry-related regulation of qualifications which proved to be effective both on the national and European level. Such structures were first established on the national levels to regulate the qualifications and ensure their comparability and compatibility, given the economic globalization and growing labor and academic mobility. The author points out the role of the ministries of education and labor in maintaining a steady qualifications system, and outlines the positive experience of Great Britain using the industry councils for continuing development of qualifications system.

Qualification testing facility for packages to be used for transport and storage of radioactive materials

International Nuclear Information System (INIS)

Vieru, Gheorghe

2009-01-01

The radioactive materials (RAM) packaging have to comply to all modes and transport condition, routine or in accident conditions possibly to occur during transportation operations. It is well known that the safety in the transport of RAM is dependent on packaging appropriate for the contents being shipped rather than on operational and/or administrative actions required for the package. The quality of these packages - type A, B or C has to be proved by performing qualification tests in accordance with the ROMANIAN nuclear regulation conditions provided by CNCAN Order no. 357/22.12.2005- 'Norms for a Safe Transport of Radioactive Material', the IAEA Vienna Recommendation stipulated in the Safety standard TS-R-1- Regulation for the Safe Transport of Radioactive Material, 2005 Edition, and other applicable international recommendations. The paper will describe the components of the designed testing facilities, and the qualification testing to be performed for all type A, B and C packages subjected to the testing. In addition, a part of the qualification tests for a package (designed and manufactured in INR Pitesti) used for transport and storage of spent fuel LEU elements of a TRIGA nuclear reactor will be described and analyzed. Quality assurance and quality controls measures taken in order to meet technical specification provided by the design are also presented and commented. The paper concludes that the new Romanian Testing Facilities for RAM packages will comply with the national safe standards as well as with the IAEA applicable recommendation provided by the TS-R-1 safety standard. (author)

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.

11 CFR 7.27 - Hearing examiner designation and qualifications.

Science.gov (United States)

2010-01-01

... complaint. (2) The examiner shall be an attorney at the Assistant General Counsel level or higher. ... 11 Federal Elections 1 2010-01-01 2010-01-01 false Hearing examiner designation and qualifications. 7.27 Section 7.27 Federal Elections FEDERAL ELECTION COMMISSION STANDARDS OF CONDUCT Post Employment...

Standard practice for qualification and acceptance of boron based metallic neutron absorbers for nuclear criticality control for dry cask storage systems and transportation packaging

CERN Document Server

American Society for Testing and Materials. Philadelphia

2007-01-01

1.1 This practice provides procedures for qualification and acceptance of neutron absorber materials used to provide criticality control by absorbing thermal neutrons in systems designed for nuclear fuel storage, transportation, or both. 1.2 This practice is limited to neutron absorber materials consisting of metal alloys, metal matrix composites (MMCs), and cermets, clad or unclad, containing the neutron absorber boron-10 (10B). 1.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

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)

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

International Nuclear Information System (INIS)

Bell, R.N.; Akos, T.

1985-01-01

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

Chapter 9. Personnel qualification and training

International Nuclear Information System (INIS)

2001-01-01

the direct supervision of the trainer within 4 to 10 weeks after the successful completion of both written and oral of examination. Last year the committee held thirteen sessions for oral theoretical examination. The number of licenses issued in 2000 and the total number of valid licenses is given in table. The standard of professional skills of the staff at nuclear installations is a very important factor for assuring and maintaining a high level of nuclear safety of nuclear installations. Conclusions from inspections and tests as well as results from operation and start up of nuclear units confirm that in this area 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 UJD staff for 2000. These training, composed of specialised qualification study, functional study, as well as study aimed at maintaining qualification. Training courses organised by the Government Office of Slovakia and the IAEA were also of a significant benefit and UJD staff participated on foreign training courses, seminars and conferences, focusing on maintaining and improvement of professional skills. In January 2000 the agreement on co-operation with the Faculty of Natural Science of Comenius University in Bratislava and UJD on INIS system performance (INIS Slovak National Center) was signed

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)

Seismic qualification tests of fans of the NPP of Laguna Verde U-1 and U-2; Pruebas de calificacion sismica de ventiladores de la Central Laguna Verde U1 and U2

Energy Technology Data Exchange (ETDEWEB)

Jarvio C, G.; Garcia H, E. E.; Arguelles F, R.; Vela H, A. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Naranjo U, J. L., E-mail: gilberto.jarvio@inin.gob.mx [Comision Federal de Electricidad, Gerencia de Centrales Nucleoelectricas, Subgerencia de Ingenieria, Carretera Veracruz-Medellin Km 7.5, Dos Bocas, Veracruz (Mexico)

2013-10-15

This work presents the results of the seismic qualification tests applied to the fans that will be installed in the control panels of the three divisions of the diesel generators of the nuclear power plant (NPP) of Laguna Verde, Unit-1 and Unit-2. This seismic qualification process of the fans was carried out using two specimens that were tested in the seismic table (vibrating) of the Engineering Institute of Universidad Nacional Autonoma de Mexico (UNAM), in accordance with the requirements of the standard IEEE 344-1975, to satisfy the established requirements of seismic qualification in the technical specifications and normative documents required by the nuclear standards, in order to demonstrate its application in the diesel generators Divisions I, II and III of the NPP. The seismic qualification tests were developed on specimens that were retired of the NPP of Laguna Verde recently with a service life of 7.75 years. (Author)

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.

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)

Integrated Information System for Higher Education Qualifications

Directory of Open Access Journals (Sweden)

Catalin Ionut SILVESTRU

2012-10-01

Full Text Available In the present article we aim to study thoroughly and detail aspects related to architectures specific for e-learning and management of human resources training interconnected to management of qualifications. In addition, we take into consideration combining e-learning architectures with software in an e-learning system interconnected with the National Registry of Qualifications of Higher Education, in view of developing and information system that correlates educational supply from higher education from Romania with labor market demands through qualifications. The scientific endeavor consists of original architectural solutions to integrate data, systems, processes, services from various sources and to use them in the proposed system. The practical result of the scientific endeavor is represented by design of architectures required for developing an e-learning system interconnected with the National Registry of Qualifications from Romania, which involve in first stage the qualifications provided by higher education. The proposed innovative solution consists in the fact that the proposed information system combines the advantages of content management system (CMS with learning content management system (LCMS and with reusable learning objects (RLO. Thus, the architecture proposed in the research ensures the integration of a content management system with a portal for information, guidance and support in making a professional project. The integration enables correlation of competences with content areas and specific items from various teaching subjects, thus evaluating the usefulness for this registry from learning/educational perspective. Using the proposed information system in enables correlation among qualifications, content of educational program and continuous self-evaluation opportunities, which facilitate monitoring of progress and adjustment of learning content.

A new standard for core training in radiation safety

International Nuclear Information System (INIS)

Trinoskey, P.A.

1997-02-01

A new American National Standard for radiation worker training was recently developed. The standard emphasizes performance-based training and establishing a training program rather than simply prescribing objectives. The standard also addresses basic criteria, including instructor qualifications. The standard is based on input from a wide array of regulatory agencies, universities, national laboratories, and nuclear power entities. This paper presents an overview of the new standard and the philosophy behind it. The target audience includes radiation workers, management and supervisory personnel, contractors, students, emergency personnel, and visitors

Comparison of the Standards applied to Instrumentation and Control Systems for Nuclear Power Stations in Korea and Russia

International Nuclear Information System (INIS)

Park, Joo Hyun; Hwang, In Koo; Lee, Dong Young

2005-04-01

This report describes a comparison result of technical standards applied to instrumentation and control systems for nuclear power plants between in Korea and in Russia. Russia also has a state-run organization authorized to conduct approval, cancellation, and audit in use of nuclear facility or equipment. The Russian standards for nuclear instrumentation and control equipment are analogous with the Korean ones in the aspect of basic concepts and principles. However, there are some differences in document structure, design requirements, qualification test items, depth of contents between two standard systems. The biggest deviation exists in the standard documents for seismic qualification and electromagnetic interference qualification. Korean seismic qualification standard utilizing US approach, defines testing and qualification methods specifically and clearly. Russian standards however provide only conceptual definitions and requirements in the seismic related aspects. Therefore, it is conceived that any equipment or system qualified seismically in accordance with Korean standards should additionally provide technical evidence that it is satisfactory with Russian standards as well. In electromagnetic interference qualification, because Russian standard requires more testing items than the current Korean standard, the additional qualification tests are necessary to meet the Russian requirements. However, these additional test items are based on IEC(International Electrotechnical Commission), therefore it is not a problem to perform those tests in a Korean testing facility

Comparison of the Standards applied to Instrumentation and Control Systems for Nuclear Power Stations in Korea and Russia

Energy Technology Data Exchange (ETDEWEB)

Park, Joo Hyun; Hwang, In Koo; Lee, Dong Young

2005-04-15

This report describes a comparison result of technical standards applied to instrumentation and control systems for nuclear power plants between in Korea and in Russia. Russia also has a state-run organization authorized to conduct approval, cancellation, and audit in use of nuclear facility or equipment. The Russian standards for nuclear instrumentation and control equipment are analogous with the Korean ones in the aspect of basic concepts and principles. However, there are some differences in document structure, design requirements, qualification test items, depth of contents between two standard systems. The biggest deviation exists in the standard documents for seismic qualification and electromagnetic interference qualification. Korean seismic qualification standard utilizing US approach, defines testing and qualification methods specifically and clearly. Russian standards however provide only conceptual definitions and requirements in the seismic related aspects. Therefore, it is conceived that any equipment or system qualified seismically in accordance with Korean standards should additionally provide technical evidence that it is satisfactory with Russian standards as well. In electromagnetic interference qualification, because Russian standard requires more testing items than the current Korean standard, the additional qualification tests are necessary to meet the Russian requirements. However, these additional test items are based on IEC(International Electrotechnical Commission), therefore it is not a problem to perform those tests in a Korean testing facility.

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...

Harmonization of IEEE323 and IEC60780 standards For Environmental Qualificaiton of Electric Equipment

International Nuclear Information System (INIS)

Kim, Jong Seog

2009-01-01

IEEE323 standard has been widely used for the qualification of electric equipment in Asian pacific area while IEC6070 has been mostly used in European area. Since each plant use different standard for environmental qualification, manufacturer has to perform the qualification test twice in accordance with each standard. Problem also can be happened in the plant site when they are going to purchase equipment qualified by different qualification standard which are not used in his plant. The need of harmonization of each standard has been raised several years and it is known that some studies are in progress by IEEE committee. KEPRI has a plan of comparing EQ relative standards of IEEE, IEC and RCC in 2009. In this paper, brief comparing result between IEEE323 and IEC60780 and the proper harmonization method is introduced

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

Special aspects of hemo-dynamic and reaction of erythrocytes in blood to standard physical load of different qualification female volleyball players

Directory of Open Access Journals (Sweden)

S. L. Popel’

2017-10-01

Full Text Available Purpose: to study the aspects of organism’s cardio-hemo-dynamic and blood erythrocytes reaction of female volleyball players to standard physical load. Material: with functional methods we studied cardio-hemo-dynamic and with the help of scanning electronic microscopy - erythrocytes’ structure in 18 female volleyball players of different qualification (age - 22.0±0.60 years. Results: it was found that maximal physical load causes substantial changes in cardio-hemo-dynamic, which depend on female volleyball players’ qualification. These changes have intrinsic to them type of blood circulation system reacting, which is manifested in the following: appropriate changes of some indicators; natural changes of periphery blood erythrocytes. In the article possible mechanisms of realization of female volleyball players’ organism’s typological features, depending on blood circulation type and erythrocytes’ conformation, are discussed. Conclusions: In relaxed state all female volleyball players have non-uniform cardio-hemo-dynamic of blood circulation. With hyper-dynamic blood circulation type, higher indicators of strike and minute blood volume were observed. With hypo-kinetic blood circulation type the opposite picture was observed: indicators of strike and minute blood volume, heart index, load on cardio-vascular system in different periods of day were low.

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

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)

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

Engineering tool for the qualification of optical coatings

Science.gov (United States)

Davi, M.; Perrin, D.; Lequime, M.; Doyle, D.

2017-11-01

For the needs of the European Space Agency, SESO is developing in cooperation with the Institut Fresnel an Engineering Tool for the Qualification of Optical Coatings. The goal is to develop a standard methodology for testing the behaviour and stability of optical coatings during the air to vacuum transition. The Engineering Tool is indeed designed to achieve in vacuum reflectance and transmittance measurements between 600 and 1700 nm. It is also designed to evaluate during the vacuum cycle partially the nature of the outgassing elements, using mass spectrometry. We will present in our paper the concept of this equipment and the associated test method. The preliminary characterizations will be done in June 2006 on reflective coatings, one anti reflective coating and dichroic filters.

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

workshop was to share lessons learned and provide a technology exchange to support development of a technically defensible waste qualification program. The objective of this report is to provide a review, from SRNL's perspective, of the WTP waste qualification program as presented during the workshop. In addition to SRNL's perspective on the general approach to the waste qualification program, more detailed insight into the specific unit operations presented by WTP during the workshop is provided. This report also provides a general overview of the SRS qualification program which serves as a basis for a comparison between the two programs. Recommendations regarding specific steps are made based on the review and SRNL's lessons learned from qualification of SRS low-activity waste (LAW) and high-level waste (HLW) to support maturation of the waste qualification program leading to WTP implementation.

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...

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

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

International Nuclear Information System (INIS)

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

2006-01-01

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

VHDL basics applied design by SIPAC qualification system

International Nuclear Information System (INIS)

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

2005-12-01

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

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

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

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

Accreditation of qualification testing organizations: the industry viewpoint

International Nuclear Information System (INIS)

Roby, A.

1983-01-01

This paper presents the industry viewpoint on the program for the Accreditation of Qualification Testing Organizations, which has been proposed for rulemaking by the Nuclear Regulatory Commission. The IEEE has agreed to establish the program content, and would administer its requirements in accordance with an agreement between the NRC and IEEE of September 30th, 1981. Presented in this paper is the industry perspective, developed and prepared through the AIF, identifying the serious concerns which the accreditation program has raised. Discussed are the disadvantages of the program and those present benefits which would be lost if the program was adopted. The value of greater emphasis on current regulation to improve the qualification process is presented and the paper details areas where the NRC proposals do not provide adequate justification for the accreditation program

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

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

International Nuclear Information System (INIS)

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

2004-01-01

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

Nuclear safety review for qualification of class 1E motor inside containment for nuclear power stations

International Nuclear Information System (INIS)

Li Shixin; Wu Qi; Zhang Yunbo; Wu Caixia

2013-01-01

In nuclear power plants with pressurized water reactors, the review for class 1E motor inside containment qualification process and documents is an important aspect of nuclear safety equipment review, and the reviewers should make evaluations for the qualification test results in terms of the compliance with standard and regulation, and the consistency with inside containment environment. Firstly, this paper introduces the qualification test of class 1E motor inside containment for nuclear power generating stations, such as aging test and design-basis-event test. Second, there is a discussion about typical problems of review. At last, comparison of IEEE334 with RCC-E is conducted and explored. (authors)

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.)

Computer code qualification program for the Advanced CANDU Reactor

International Nuclear Information System (INIS)

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

2003-01-01

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

Qualification of the AUTOBUS Mod. 2 Code

International Nuclear Information System (INIS)

Ciarniello, U.; Peroni, P.

1988-01-01

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

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)

A conceptual analysis of standard setting in large-scale assessments

NARCIS (Netherlands)

van der Linden, Willem J.

1994-01-01

Elements of arbitrariness in the standard setting process are explored, and an alternative to the use of cut scores is presented. The first part of the paper analyzes the use of cut scores in large-scale assessments, discussing three different functions: (1) cut scores define the qualifications used

Post-installed concrete anchors in nuclear power plants: Performance and qualification

International Nuclear Information System (INIS)

Mahrenholtz, Philipp; Eligehausen, Rolf

2015-01-01

Graphical abstract: - Highlights: • Review of qualification and design regulations for anchors in nuclear power plants. • First complete set of nuclear anchor load–displacement data and its evaluation ever. • Demonstration of robust test behavior of a qualified post-installed anchor product. - Abstract: In nuclear power plants (NPPs), post-installed anchors are widely used for structural and non-structural connections to concrete. In many countries, anchor products employed for safety relevant applications have to be approved by the authorities. For the high safety standards in force for NPPs, special requirements have to be met to allow for extreme design situations. This paper presents an experimental test program conducted to evaluate the performance of anchors according to the German Guideline for Anchorages in Nuclear Power Plants and Nuclear Technology Installations (DIBt KKW Leitfaden, 2010). After a brief introduction to anchor behavior and the regulative context, the results of tension and shear tests carried out on undercut anchors are discussed. Robust load capacities and relatively small displacements determined for demanding load and crack cycling tests demonstrated the suitability of anchors qualified according to a state-of-the-art qualification guideline

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

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)

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.

High-level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID), Volume 2

International Nuclear Information System (INIS)

1994-04-01

The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Document (S/RID) is contained in multiple volumes. This document (Volume 2) presents the standards and requirements for the following sections: Quality Assurance, Training and Qualification, Emergency Planning and Preparedness, and Construction

High-level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID), Volume 2

Energy Technology Data Exchange (ETDEWEB)

1994-04-01

The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Document (S/RID) is contained in multiple volumes. This document (Volume 2) presents the standards and requirements for the following sections: Quality Assurance, Training and Qualification, Emergency Planning and Preparedness, and Construction.

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...

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.

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.

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

A Step Towards Electric Propulsion Testing Standards: Pressure Measurements and Effective Pumping Speeds

Science.gov (United States)

Dankanich, John W.; Swiatek, Michael W.; Yim, John T.

2012-01-01

The electric propulsion community has been implored to establish and implement a set of universally applicable test standards during the research, development, and qualification of electric propulsion systems. Existing practices are fallible and result in testing variations which leads to suspicious results, large margins in application, or aversion to mission infusion. Performance measurements and life testing under appropriate conditions can be costly and lengthy. Measurement practices must be consistent, accurate, and repeatable. Additionally, the measurements must be universally transportable across facilities throughout the development, qualification, spacecraft integration and on-orbit performance. A preliminary step to progress towards universally applicable testing standards is outlined for facility pressure measurements and effective pumping speed calculations. The standard has been applied to multiple facilities at the NASA Glenn Research Center. Test results and analyses of universality of measurements are presented herein.

Water bath and air bath calorimeter qualification for measuring 3013 containers of plutonium oxide at the Hanford Plutonium Finishing Plant (PFP)

International Nuclear Information System (INIS)

WELSH, T.L.

2003-01-01

The purpose of this paper is to present qualification data generated from water and air-bath calorimeters measuring radioactive decay heat from plutonium oxide in DOE STD-3013-2000 (3013) containers at the Hanford Plutonium Finishing Plant (PFP). Published data concerning air and water bath calorimeters and especially 3013-qualified calorimeters is minimal at best. This paper will address the data from the measurement/qualification test plan, the heat standards used, and the calorimeter precision and accuracy results. The 3013 package is physically larger than earlier plutonium oxide storage containers, thereby necessitating a larger measurement chamber. To accommodate the measurements of the 3013 containers at PFP, Los Alamos National Laboratory (LANL) supplied a water bath dual-chambered unit and the Savannah River Technology Center (SRTC) provided two air-bath calorimeters. Both types of Calorimeters were installed in the analytical laboratory at PFP. The larger 3013 containers presented a new set of potential measurement problems: longer counting times, heat conductivity through a much larger container mass and wall thickness, and larger amounts of copper shot to assist sample thermal conductivity. These potential problems were addressed and included in the measurement/qualification test plan

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).

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...

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.

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

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

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)

76 FR 20351 - Federal Acquisition Regulation; Information Collection; Architect-Engineer Qualifications (SF 330)

Science.gov (United States)

2011-04-12

...; Information Collection; Architect-Engineer Qualifications (SF 330) AGENCIES: Department of Defense (DOD... approve an extension of a currently approved information collection requirement for the Architect-Engineer... Standard Form 330, Part I is used by all Executive agencies to obtain information from architect-engineer...

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.

IEEE Std 649-1980: IEEE standard for qualifying Class 1E motor control centers for nuclear power generating stations

International Nuclear Information System (INIS)

Anon.

1992-01-01

This standard describes the basic principles, requirements, and methods for qualifying Class 1E motor control centers for outside containment applications in nuclear power generating stations. Qualification of motor control centers located inside containment in a nuclear power generating station is beyond the scope of this standard. The purpose of this standard is (1) to define specific qualification requirements for Class 1E motor control centers in accordance with the more general qualification requirements of IEEE Std 323-1974, IEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations; (2) to provide guidance in establishing a qualification program for demonstrating the design adequacy of Class 1E motor control centers in nuclear power generating station applications

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.

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

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)

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.

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

International Nuclear Information System (INIS)

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

1997-01-01

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

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.

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.

Overview of the IAEA's activity on ISI qualification

International Nuclear Information System (INIS)

Trampus, P.

2000-01-01

The IAEA Subprogram on Nuclear Power Planning, Implementation and Performance is presented. It's objective is to assist Member States in: planning nuclear power programmes in an integrated manner considering all necessary factors; systematically improving overall performance and competitiveness of NPPs trough entire service life with due regard to safety; applying technological/engineering best practices including QA/QM in all areas of nuclear power utilisation. International working group on life management of NPPs (IWG-LMNPP) has been established in 1975 with 26 Member States and 2 international organizations in order to provide the Director General with advice and opinions and the Member States with information, recommendations and support in life management issues.The technical co-operation program RER/4/020 'Advanced NDT of Primary Circuit Components' is presented.The pilot study is aimed to provide the participating Member States with practical advice how to apply the IAEA's qualification methodology. The target application is Technical Justification for UT of WWER-1000 RPV shell weld (unit 5 of 'Kozloduy NPP). The concept is to simulate the qualification process through assistance to establish qualification for a real NPP component, using real ISI, in a real regulatory environment. Interim results for Bulgaria are reported and further tasks are outlined

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

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.

Registration factors that limit international mobility of people holding physiotherapy qualifications: A systematic review.

Science.gov (United States)

Foo, Jonathan S; Storr, Michael; Maloney, Stephen

2016-06-01

There is no enforced international standardisation of the physiotherapy profession. Thus, registration is used in many countries to maintain standards of care and to protect the public. However, registration may also limit international workforce mobility. What is known about the professional registration factors that may limit the international mobility of people holding physiotherapy qualifications? Systematic review using an electronic database search and hand searching of the World Confederation for Physical Therapy and International Network of Physiotherapy Regulatory Authorities websites. Analysis was conducted using thematic analysis. 10 articles and eight websites were included from the search strategy. Data is representative of high-income English speaking countries. Four themes emerged regarding limitations to professional mobility: practice context, qualification recognition, verification of fitness to practice, and incidental limitations arising from the registration process. Professional mobility is limited by differences in physiotherapy education programmes, resulting in varying standards of competency. Thus, it is often necessary to verify clinical competencies through assessments, as well as determining professional attributes and ability to apply competencies in a different practice context, as part of the registration process. There has been little evaluation of registration practices, and at present, there is a need to re-evaluate current registration processes to ensure they are efficient and effective, thereby enhancing workforce mobility. Copyright © 2016 Elsevier Ireland Ltd. All rights reserved.

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 ...

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

International Nuclear Information System (INIS)

Serrano, M.A.B.

1986-01-01

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

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. ...

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...

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

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. ...

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

International Nuclear Information System (INIS)

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

1984-08-01

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

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

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 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.)

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. ...

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)

Qualification of NDT techniques for in-service inspections in nuclear power plants in accordance with ENIQ - examples and lessons - learned

International Nuclear Information System (INIS)

Just, T.; Csapo, G.

2006-01-01

ENIQ (European Network for Inspection and Qualification) has developed regulations on how to qualify non-destructive testing (NDT) methods and techniques in a standardized and structured manner. Two major innovative qualifications were carried out and reviewed with regard to implementation, according to the recommended German practice of ENIQ. The conclusions were drawn after performing the ENIQ qualification procedure for in-service inspections (ISI) of real components in nuclear power plants (NPP). The first example covers the qualification of NDT methods for the detection and characterization of surface, subsurface and underclad cracks in the area of the austenitic cladded RPV surface. Open and blind tests were conducted applying UT and ET (from the ID) and UT (from the OD) on realistic flaws (artificially induced IGSCC, hot cracks and fatigue cracks) in the cladding of a full scale RPV mock-up from MPA Stuttgart. The second example covers the qualification of mechanised RT in combination with tomography (developed by the BAM) for the sizing of cracks in pipe welds. For both qualification procedures TUEV NORD SysTec experts were part of the qualification body. The proposed NDT procedures have been qualified within defined limits of application. Recommendations were made to optimise the procedures and the techniques itself further. (orig.)

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)

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

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)

Qualification of contractor/consultant instructors

International Nuclear Information System (INIS)

Hanson, H.D.

1985-01-01

Following a brief discussion of the role of consultant instructors in Public Service Electric and Gas Company's training organization, the qualification process is presented. Consultant instructors are provided with information regarding supervision of the trainees and the instructional process and procedures required. Each individual must have his or her instructional capability, supervisory skills and technical competence verified and documented prior to conducting training independently. Concluding comments describe the overall satisfactory experience with this program

Hanford Waste Vitrification Plant Project Waste Form Qualification Program Plan

International Nuclear Information System (INIS)

Randklev, E.H.

1993-06-01

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

Chapter No.8. Personnel qualification and training

International Nuclear Information System (INIS)

2002-01-01

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 NPP's. A part of the examination in case of promotion to a higher position is the practical part, which is conducted under the direct supervision of the trainer within 4 to 10 weeks after the successful completion of both written and oral of examinations. Last year the committee held ten sessions for the oral theoretical examination. The number of licenses issued in 2001 and the total number of valid licenses is given. Conclusions from inspections and tests as well as results from operation and start up of nuclear units confirm that in this area a high standard of operational safety is being achieved on a permanent basis. Increasing the qualification of UJD staff Increasing the qualification of UJD staff was done in a form of training and courses scheduled in the plan of training for UJD staff for 2001. This training composed of specialised qualification study, functional study, as well as study aimed at maintaining qualification (continual and periodical exercise). Training courses organised by the Government Office of Slovakia and the IAEA were also of a significant benefit and UJD staff participated on foreign training courses, seminars and conferences, focusing on maintaining and improvement of professional skills

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

Analysis of the qualification test standards for small radioactive material shipping packages

International Nuclear Information System (INIS)

McClure, J.D.

1978-01-01

The study compares the severity of the existing regulatory standards which are used to license radioactive material (RAM) shipping packages with the severity of transportation accidents. The basic findings of the study indicate that the present regulatory standards provide significantly higher levels of protection for surface transportation modes (truck, rail) than for RAM packages shipped by aircraft. It was also determined that crush can occur in all of the transport modes and is not presently included in existing regulations for accident conditions. Test proposals are included for the surface transport mode (truck, rail) and the air transport mode

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

International Nuclear Information System (INIS)

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

1977-04-01

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

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

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.

A novel strategy with standardized reference extract qualification and single compound quantitative evaluation for quality control of Panax notoginseng used as a functional food.

Science.gov (United States)

Li, S P; Qiao, C F; Chen, Y W; Zhao, J; Cui, X M; Zhang, Q W; Liu, X M; Hu, D J

2013-10-25

Root of Panax notoginseng (Burk.) F.H. Chen (Sanqi in Chinese) is one of traditional Chinese medicines (TCMs) based functional food. Saponins are the major bioactive components. The shortage of reference compounds or chemical standards is one of the main bottlenecks for quality control of TCMs. A novel strategy, i.e. standardized reference extract based qualification and single calibrated components directly quantitative estimation of multiple analytes, was proposed to easily and effectively control the quality of natural functional foods such as Sanqi. The feasibility and credibility of this methodology were also assessed with a developed fast HPLC method. Five saponins, including ginsenoside Rg1, Re, Rb1, Rd and notoginsenoside R1 were rapidly separated using a conventional HPLC in 20 min. The quantification method was also compared with individual calibration curve method. The strategy is feasible and credible, which is easily and effectively adapted for improving the quality control of natural functional foods such as Sanqi. Copyright © 2013 Elsevier B.V. All rights reserved.

Seismic qualification of civil engineering structures - Temelin NPP

International Nuclear Information System (INIS)

Schererova, K.; Holub, I.; Stepan, J.; Maly, J.

2004-01-01

Basic information is presented about the input data and methodology used for evaluation of Temelin NPP civil structures. The existing conditions as listed in POSAR report for the two reactor units are considered. The original design of the power plant assumed a lower level of locality seismic hazard, as followed from seismological surveys that where then available. Later the seismic assessment was updated while fully respecting IAEA recommendations and using a minimum value of acceleration in the horizontal direction PGAHOR = 0.1 g at free field level for SL-2. In relation to the new seismic project, new qualification of the structures, components and systems classed as seismic resistance category 1 was carried out. Since the Czech Republic has no specific technical standards for seismic resistance evaluation of nuclear power plants, a detailed methodology was elaborated, comprising principles of seismic resistance evaluation based on IAEA guides and on common practice in countries with advanced nuclear power engineering. (P.A.)

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

International Nuclear Information System (INIS)

Szukiewicz, A.J.

1981-07-01

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

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.)

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...

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

International Nuclear Information System (INIS)

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

1995-01-01

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

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

Wireless installation standard

International Nuclear Information System (INIS)

Lim, Hwang Bin

2007-12-01

This is divided six parts which are radio regulation law on securing of radio resource, use of radio resource, protection of radio resource, radio regulation enforcement ordinance with securing, distribution and assignment of radio regulation, radio regulation enforcement regulation on utility of radio resource and technical qualification examination, a wireless installation regulation of technique standard and safety facility standard, radio regulation such as certification regulation of information communicative machines and regulation of radio station on compliance of signal security, radio equipment in radio station, standard frequency station and emergency communication.

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.

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

International Nuclear Information System (INIS)

Mitton, T.

2004-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2015-10-15

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

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.

Hybrid qualifications. Increasing the value of vocational education and training in the comtext of Lifelong Learning

DEFF Research Database (Denmark)

Jørgensen, Christian Helms; Lindvig, Katrine

The aim of this second report is to present the results of an empirical study of the perceptions and views of the key stakeholders (teachers, learners, employers, policy-makers) in relation to hybrid qualifications (vocational and general qualifications). A special attention is given to the new h...

Qualification of high density aluminide fuels for the BR2 reactor

International Nuclear Information System (INIS)

Beeckmans de West-Meerbeeck, Andre; Gubel, Pol; Ponsard, Bernard; Pin, Thomas; Falgoux, Jean Louis

2005-01-01

The BR2 operation still relies on the use of 90..93% enriched HEU aluminide fuel. The availability of a limited batch of 73% enriched HEU from reprocessed BR2 uranium in Dounreay justified 10 years ago the qualification and use of this material. After some preliminary test irradiations, various batches of fuel elements were fabricated by the UKAEA-Dounreay and successfully irradiated. Due to their lower 235 U content (0.050 g 235 U/cm 2 ), these elements were always irradiated together with standard 90...93% HEU fuel elements. A mixed-core strategy was developed at this occasion for an optimal utilization, and was reported during the 4th RRFM conference (March 19-21, 2000, Colmar, France). The availability of a new batch of fresh 73% HEU material was the occasion, a few years ago, to initiate the development, fabrication and qualification of a new high density fuel element. An order was placed with CERCA to assess the optimal fabrication methods and tooling required to meet as far as possible the existing BR2 standard specifications and 235 U content (0.060 g 235 U/cm 2 ). This development phase has been already reported during the 7th RRFM conference (March 9-12, 2003, Aix-en-Provence, France). Afterwards, six lead test fuel elements were ordered for qualification by irradiation. The neutronic properties of the fuel elements were adjusted and optimized. After a short summary of the main results of the development program, this paper describes the nuclear characteristics of the high density fuel elements and comments on the nuclear follow-up of the lead test fuel elements during their irradiation for five cycles in the BR2 reactor and the return of experience for CERCA. (author)

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

IAEA standard syllabus of a course to acquire competence on ionizing radiation sources activities

International Nuclear Information System (INIS)

Antonova, M.

2004-01-01

The specialized training for Ionizing Radiation Sources (IRS) activities is conducted according to educational syllabuses developed for every job position in compliance with art. 12, (3) of new Regulation of the conditions and procedure for acquiring professional qualification and for the procedure for issuing licenses for specialized training and certificates for qualification for use of nuclear energy. A brief review of the modular structure of the standard syllabus of the Postgraduate Educational Course in Radiation Protection and the Safe Use of Radiation Sources is presented in this paper. The content and level of training for categories of persons engaged in different practices are also listed

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...

THE ROLE OF EDUCATIONAL COMPLEXES IN THE IMPLEMENTATION OF THE PARTNERSHIP MODEL FORMATION OF THE NATIONAL QUALIFICATIONS FRAMEWORK

Directory of Open Access Journals (Sweden)

Kristina V. Gileva

2015-01-01

Full Text Available The aim of the study is to define potential of modern educational complexes in the field of formation of national system of qualifications on the basis of interpretation of procedures changes in regulation of social and labour relations. Methods. The methods involve analysis, generalisation, ordering and a technique of modelling of processes.Results. The authors describe key positions of the theory of the continuous education that provides rapprochement of requirements of employers with quality of vocational training and the content of educational process in the branch educational institutions. The possible contribution of educational complexes to creation of national system of qualifications and professional standards is considered. In this connection various forms of partnership of the given complexes with public authorities, public structures, and also employers are described.Scientific novelty. The concept of business competence characterising ability of system of vocational training is offered to satisfy the requirement of a labour market by means of active integration of educational, innovative and labour processes.Practical significance. The presented model of interaction of educational complexes and subjects of a labour market can be realised by working out of professional standards, creation of the expert centers and the innovative platforms intended to realisation of advisory activity on the basis of high schools; and also organizational-methodical support of processes of professional certification system formation. According to authors, this model will help to co-ordinate the content of professional and Federal State Educational Standards (FSES. 

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

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

International Nuclear Information System (INIS)

Anon.

1993-01-01

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

U-Mo fuel qualification program in HANARO

International Nuclear Information System (INIS)

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

2000-01-01

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

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)

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

International Nuclear Information System (INIS)

2005-01-01

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

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

International Nuclear Information System (INIS)

2002-01-01

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

Procedure for the qualification of a manufacturer of ingot iron pieces for application in nuclear power plant components

International Nuclear Information System (INIS)

Rahn, K.M.M.; Jusevicius, E.; Michael, H.

1981-01-01

The process for the qualification of 'Sao Caetano do Sul (Acos Villares S/A)' Plant as manufacturers of ingot iron pieces for application in components of Angra 2 and Angra 3 Nuclear Power Plants, is presented. The qualification was executed by IBQN - Instituto Brasileiro de Qualidade Nuclear - the organ officially in charge of the execution of qualification of suppliers of materials for the nuclear industry. (E.G.) [pt

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

ISO radiation sterilization standards

International Nuclear Information System (INIS)

Lambert, Byron J.; Hansen, Joyce M.

1998-01-01

This presentation provides an overview of the current status of the ISO radiation sterilization standards. The ISO standards are voluntary standards which detail both the validation and routine control of the sterilization process. ISO 11137 was approved in 1994 and published in 1995. When reviewing the standard you will note that less than 20% of the standard is devoted to requirements and the remainder is guidance on how to comply with the requirements. Future standards developments in radiation sterilization are being focused on providing additional guidance. The guidance that is currently provided in informative annexes of ISO 11137 includes: device/packaging materials, dose setting methods, and dosimeters and dose measurement, currently, there are four Technical Reports being developed to provide additional guidance: 1. AAMI Draft TIR, 'Radiation Sterilization Material Qualification' 2. ISO TR 13409-1996, 'Sterilization of health care products - Radiation sterilization - Substantiation of 25 kGy as a sterilization dose for small or infrequent production batches' 3. ISO Draft TR, 'Sterilization of health care products - Radiation sterilization Selection of a sterilization dose for a single production batch' 4. ISO Draft TR, 'Sterilization of health care products - Radiation sterilization-Product Families, Plans for Sampling and Frequency of Dose Audits'

Standard Test Method for Sandwich Corrosion Test

CERN Document Server

American Society for Testing and Materials. Philadelphia

2009-01-01

1.1 This test method defines the procedure for evaluating the corrosivity of aircraft maintenance chemicals, when present between faying surfaces (sandwich) of aluminum alloys commonly used for aircraft structures. This test method is intended to be used in the qualification and approval of compounds employed in aircraft maintenance operations. 1.2 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information. 1.3 This standard may involve hazardous materials, operations, and equipment. This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use. Specific hazard statements appear in Section 9.

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

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.

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

76 FR 82306 - Draft Guidance for Industry on Use of Histology in Biomarker Qualification Studies; Availability

Science.gov (United States)

2011-12-30

...] Draft Guidance for Industry on Use of Histology in Biomarker Qualification Studies; Availability AGENCY... announcing the availability of a draft guidance for industry entitled ``Use of Histology in Biomarker... studies for which histology is a reference standard. This guidance discusses the processes that should be...

Evolution of seismic shock test qualification of equipment

International Nuclear Information System (INIS)

Berriaud, C.

1979-01-01

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

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

Studies to demonstrate the adequacy of testing results of the qualification tests for the actuator of main steam safety relive valves (MSSRV) in an advanced boiling water reactor (ABWR)

International Nuclear Information System (INIS)

Gou, P.F.; Patel, R.; Curran, G.; Henrie, D.; Solorzano, E.

2005-01-01

This paper presents several studies performed to demonstrate that the testing results from the qualification tests for the actuator of the Main Steam Safety Relief Valves (MSSRV; also called SRV in this paper) in GE's Advanced Boiling Water Reactor (ABWR) are in compliance with the qualification guidelines stipulated in the applicable IEEE standards. The safety-related function of the MSSRV is to relieve pressure in order to protect the reactor pressure vessel from over-pressurization condition during normal operation and design basis events. In order to perform this function, the SRV must actuate at a given set pressure while maintaining the pressure and structural integrity of the SRV. The valves are provided with an electro-pneumatic actuator assembly that opens the valve upon receipt of an automatic or manually initiated electric signal to allow depressurization of the reactor pressure vessel (RPV). To assure the SRV can perform its intended safety related functions properly, qualification tests are needed in addition to analysis, to demonstrate that the SRV can withstand the specified environmental, dynamic and seismic design basis conditions without impairing its safety related function throughout their installed life under the design conditions including postulated design basis events such as OBE loads and Faulted (SSE) events. The guidelines used for the test methods, procedures and acceptance criteria for the qualification tests are established in IEEE std 344-1987 and IEEE std 382-1985. In the qualification tests, the specimen consists of the actuator, control valve assembly, limit switches, and limit switch support structure. During the functional, dynamic and seismic tests, the test specimen was mounted on a SRV. Qualification of safety related equipment to meet the guidelines of the IEEE standards is typically a two-step process: 1) environmental aging and 2) design basis events qualification. The purpose of the first step is to put the equipment in an

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...

DNA Qualification Workflow for Next Generation Sequencing of Histopathological Samples

Science.gov (United States)

Simbolo, Michele; Gottardi, Marisa; Corbo, Vincenzo; Fassan, Matteo; Mafficini, Andrea; Malpeli, Giorgio; Lawlor, Rita T.; Scarpa, Aldo

2013-01-01

Histopathological samples are a treasure-trove of DNA for clinical research. However, the quality of DNA can vary depending on the source or extraction method applied. Thus a standardized and cost-effective workflow for the qualification of DNA preparations is essential to guarantee interlaboratory reproducible results. The qualification process consists of the quantification of double strand DNA (dsDNA) and the assessment of its suitability for downstream applications, such as high-throughput next-generation sequencing. We tested the two most frequently used instrumentations to define their role in this process: NanoDrop, based on UV spectroscopy, and Qubit 2.0, which uses fluorochromes specifically binding dsDNA. Quantitative PCR (qPCR) was used as the reference technique as it simultaneously assesses DNA concentration and suitability for PCR amplification. We used 17 genomic DNAs from 6 fresh-frozen (FF) tissues, 6 formalin-fixed paraffin-embedded (FFPE) tissues, 3 cell lines, and 2 commercial preparations. Intra- and inter-operator variability was negligible, and intra-methodology variability was minimal, while consistent inter-methodology divergences were observed. In fact, NanoDrop measured DNA concentrations higher than Qubit and its consistency with dsDNA quantification by qPCR was limited to high molecular weight DNA from FF samples and cell lines, where total DNA and dsDNA quantity virtually coincide. In partially degraded DNA from FFPE samples, only Qubit proved highly reproducible and consistent with qPCR measurements. Multiplex PCR amplifying 191 regions of 46 cancer-related genes was designated the downstream application, using 40 ng dsDNA from FFPE samples calculated by Qubit. All but one sample produced amplicon libraries suitable for next-generation sequencing. NanoDrop UV-spectrum verified contamination of the unsuccessful sample. In conclusion, as qPCR has high costs and is labor intensive, an alternative effective standard workflow for

DNA qualification workflow for next generation sequencing of histopathological samples.

Directory of Open Access Journals (Sweden)

Michele Simbolo

Full Text Available Histopathological samples are a treasure-trove of DNA for clinical research. However, the quality of DNA can vary depending on the source or extraction method applied. Thus a standardized and cost-effective workflow for the qualification of DNA preparations is essential to guarantee interlaboratory reproducible results. The qualification process consists of the quantification of double strand DNA (dsDNA and the assessment of its suitability for downstream applications, such as high-throughput next-generation sequencing. We tested the two most frequently used instrumentations to define their role in this process: NanoDrop, based on UV spectroscopy, and Qubit 2.0, which uses fluorochromes specifically binding dsDNA. Quantitative PCR (qPCR was used as the reference technique as it simultaneously assesses DNA concentration and suitability for PCR amplification. We used 17 genomic DNAs from 6 fresh-frozen (FF tissues, 6 formalin-fixed paraffin-embedded (FFPE tissues, 3 cell lines, and 2 commercial preparations. Intra- and inter-operator variability was negligible, and intra-methodology variability was minimal, while consistent inter-methodology divergences were observed. In fact, NanoDrop measured DNA concentrations higher than Qubit and its consistency with dsDNA quantification by qPCR was limited to high molecular weight DNA from FF samples and cell lines, where total DNA and dsDNA quantity virtually coincide. In partially degraded DNA from FFPE samples, only Qubit proved highly reproducible and consistent with qPCR measurements. Multiplex PCR amplifying 191 regions of 46 cancer-related genes was designated the downstream application, using 40 ng dsDNA from FFPE samples calculated by Qubit. All but one sample produced amplicon libraries suitable for next-generation sequencing. NanoDrop UV-spectrum verified contamination of the unsuccessful sample. In conclusion, as qPCR has high costs and is labor intensive, an alternative effective standard

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

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.)

Space qualification of high capacity grooved heat pipes

Energy Technology Data Exchange (ETDEWEB)

Dubois, M; Mullender, B; Druart, J [SABCA, Societe Anomyme Belgel de Construction Aeronautique (Belgium); Supper, W; Beddows, A [ESTEC-The (Netherlands)

1997-12-31

Based on the thermal requirements of the future telecommunication satellites, the development of a High Capacity Grooved Heat Pipe (HPG), was contracted by ESA to SABCA leading to an aluminium extruded heat pipe (outer diameter of 25 mm) based on a multi re-entrant grooves design. After an intensive acceptance test campaign whose results showed a good confidence in the design and the fulfillment of the required specifications of heat transport and on tilt capability (experimental maximum heat transport capability of 1500 Watt metres for a vapour temperature of 20 deg C), similar heat pipes have been developed with various outer diameters (11 mm, 15 mm and 20 mm) and with various shapes (circular outer shapes, integrated saddles). Several of these heat pipes were tested during two parabolic flight campaigns, by varying the heat loads during the micro-gravity periods. This HGP heat pipe family is now being submitted to a space qualification program according to ESA standards (ESA PSS-49), both in straight and bent configuration. Within this qualification, the heat pipes are submitted to an extended test campaign including environmental (random/sinus vibration, constant acceleration) and thermal tests (thermal performance, thermal cycle, thermal soak, ageing). (authors) 9 refs.

Space qualification of high capacity grooved heat pipes

Energy Technology Data Exchange (ETDEWEB)

Dubois, M.; Mullender, B.; Druart, J. [SABCA, Societe Anomyme Belgel de Construction Aeronautique (Belgium); Supper, W.; Beddows, A. [ESTEC-The (Netherlands)

1996-12-31

Based on the thermal requirements of the future telecommunication satellites, the development of a High Capacity Grooved Heat Pipe (HPG), was contracted by ESA to SABCA leading to an aluminium extruded heat pipe (outer diameter of 25 mm) based on a multi re-entrant grooves design. After an intensive acceptance test campaign whose results showed a good confidence in the design and the fulfillment of the required specifications of heat transport and on tilt capability (experimental maximum heat transport capability of 1500 Watt metres for a vapour temperature of 20 deg C), similar heat pipes have been developed with various outer diameters (11 mm, 15 mm and 20 mm) and with various shapes (circular outer shapes, integrated saddles). Several of these heat pipes were tested during two parabolic flight campaigns, by varying the heat loads during the micro-gravity periods. This HGP heat pipe family is now being submitted to a space qualification program according to ESA standards (ESA PSS-49), both in straight and bent configuration. Within this qualification, the heat pipes are submitted to an extended test campaign including environmental (random/sinus vibration, constant acceleration) and thermal tests (thermal performance, thermal cycle, thermal soak, ageing). (authors) 9 refs.

Seismic qualification using digital signal processing/modal testing and finite element techniques

International Nuclear Information System (INIS)

Steedman, J.B.; Edelstein, A.

1983-01-01

A systematic procedure in which digital signal processing, modal testing and finite element techniques can be used to seismically qualify Class IE equipment for use in nuclear generating stations is presented. A new method was also developed in which measured transmissibility functions and Fourier transformation techniques were combined to compute instrument response spectra. As an illustrative example of the qualification method, the paper follows the qualification of a safety related Class IE Heating, Ventilating, and Air Conditioning (HVAC) Control Panel subjected to both seismic and hydrodynamic loading conditions

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

Analysis and qualification of steam generator relief valves (BRU-A)

International Nuclear Information System (INIS)

Lathuile, C.; Serre, J. L.

1997-01-01

This paper presents a general overview of improvements foreseen in the frame of Safety Measures S01 and S10 in order to prevent and mitigate consequences of a large primary to secondary leakage. Among these improvements, a more detailed description of methodology and results relative to Steam Generator Relief Valves (BRU-A) qualification tests is presented. (author)

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

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...

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

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.

Qualification of quality assurance program audit personnel for nuclear power plants

International Nuclear Information System (INIS)

Anon.

1979-01-01

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

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...

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

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.

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

Dosimetry. Standard practice for dosimetry in gamma irradiation facilities for food and non-food processing

International Nuclear Information System (INIS)

2008-01-01

This Ghana Standard outlines the installation qualification program for an irradiator and the dosimetry procedures to be followed during operational qualification, performance qualification and routine processing in facilities that process food and non-food with gamma rays. This is to ensure that the product has been treated with predetermined range of absorbed dose. It is not intended for use in X-ray and electron beam facilities and therefore dosimetry systems in such facilities are not covered

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

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...

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.

Some considerations on adapting academic qualifications to the Romanian labor market

Directory of Open Access Journals (Sweden)

Denes Calin

2017-01-01

Full Text Available The paper presents the results of some research carried out by the authors during the activities of the “Academic Entrepreneurial Laboratory – Progress through Innovation and Practice – (Univers Practic” and seeks to evince certain key aspects pertaining to the adaptation of university qualifications to the needs of the Romanian workforce. First, the general context of higher education and the current state of affairs, as reflected by the analysis of relevant works in the field are presented. This is followed by a presentation of the main results of a questionnaire-based study that evinces the opinions of students, graduates, and company managers with regard to the necessity of adapting academic qualifications to the Romanian labor market. Lastly, the conclusions of the paper are delineated and several recommendations concerning the relationship of universities with the business environment and other stakeholders are elaborated, with the aim of improving the interactions of the university with the entire society.

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...

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

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 ...

THE PROFESSIONAL QUALIFICATION SOLIDARY EXTENSION PROJECT AT ELECTRONICS: TECHNICAL AUXILIAR

Directory of Open Access Journals (Sweden)

Glaucio Lopes Ramos

2009-10-01

Full Text Available This paper has the objective to present the extension course “professional qualification solidary extension project at electronics: technical auxiliar” in the Electrical Engineering course in the University Center of Belo Horizonte, as a professional qualification activity that make possible to young, adults and elderly people from poor communities the social inclusion and an opportunity to improve their access to the labor market. The course is part of extension program of Uni-BH, UniTrabalho e Renda, that is offered since 2006. The responsible for the course are professors and students of the Electrical Engineering course, and an electricity project is also offered. This paper presents the results of an evaluation that is made for the students at the beginning and at the end of the course and showed that the concepts had been assimilated by the students and the expectation of them related to the insertion at labor market is also improved.

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.

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...

Development and Execution of a Large-scale DDT Tube Test for IHE Material Qualification

Energy Technology Data Exchange (ETDEWEB)

Parker, Gary Robert [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Broilo, Robert M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Lopez-Pulliam, Ian Daniel [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Vaughan, Larry Dean [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2016-10-24

Insensitive High Explosive (IHE) Materials are defined in Chapter IX of the DOE Explosive Safety Standard (DOE-STD-1212-2012) as being materials that are massdetonable explosives that are so insensitive that the probability of accidental initiation or transition from burning to detonation is negligible1. There are currently a number of tests included in the standard that are required to qualify a material as IHE, however, none of the tests directly evaluate for the transition from burning to detonation (aka deflagration-to-detonation transition, DDT). Currently, there is a DOE complex-wide effort to revisit the IHE definition in DOE-STD-1212-2012 and change the qualification requirements. The proposal lays out a new approach, requiring fewer, but more appropriate tests, for IHE Material qualification. One of these new tests is the Deflagration-to-Detonation Test. According to the redefinition proposal, the purpose of the new deflagration-todetonation test is “to demonstrate that an IHE material will not undergo deflagration-to-detonation under stockpile relevant conditions of scale, confinement, and material condition. Inherent in this test design is the assumption that ignition does occur, with onset of deflagration. The test design will incorporate large margins and replicates to account for the stochastic nature of DDT events.” In short, the philosophy behind this approach is that if a material fails to undergo DDT in a significant over-test, then it is extremely unlikely to do so in realistic conditions. This effort will be valuable for the B61 LEP to satisfy their need qualify the new production lots of PBX 9502. The work described in this report is intended as a preliminary investigation to support the proposed design of an overly conservative, easily fielded DDT test for updated IHE Material Qualification standard. Specifically, we evaluated the aspects of confinement, geometry, material morphology and temperature. We also developed and tested a

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)

Adopting ISO 9712:2005 and ISO/IEC 17024:2003 as Philippine national standard for NDT for global competitiveness

International Nuclear Information System (INIS)

Banaga, Renato T.; Mateo, Alejandro J.

2005-01-01

This paper describes and promotes the adoption of ISO 9712: 2005 edition and the ISO/IEC 17024: 2003 edition by the Philippines to be globally competitive. ISO 9712 is a standard for qualifications and certification of nondestructive testing (NDT) personnel while ISO/IEC 17024 is conformity assessment-general requirements for bodies operating certification of persons. ISO 9712 defies that the effectiveness of an application of nondestructive testing depends on the capabilities and qualifications of personnel performing the NDT test. The Philippines through the national certifying body (NCB) implements the certification of proficiency of NDT personnel in accordance with the Philippine National Standards (PNS-146: 1998) This standard (formerly PNS-146: 1987) was originally based from the draft ISO/TC-135/SC7N35.3 and was later revised to conform to the latest ISO FDIS 9712: 1997 and rename PNS-146: 1998. Now with the issuance of the latest ISO 9712:2005 edition and to keep abreast with the current trends of NDT technology, present time and conditions dictates for us to revise our NDT personnel certification to the latest edition of ISO 9712. The International Atomic Energy Agency (IAEA) supports the establishment of a common NDT standard. The IAEA is promoting af financially supporting the establishment in developing countries of only one NDT standard. The IAEA through the Regional Cooperative Agreement (RCA) has initiated the harmonization of the NDT qualification and certification of personnel in the RCA member states. In October 2001, the IAEA sponsored the Dhaka meeting where the International Committee for Nondestructive Testing (ICNDT), Asia-Pacific Committee (APCNDT) and RCA member states representatives drafted a Mutual Recognition Agreement (MRA) for the Asia-Pacific NDT (APCNDT) personnel certification schemes acording to ISO 9712. Last August 2005, IAEA/RCA sponsored the Colombo meeting for the harmonization of regional NDT applying ISO 9712 and ISO

16 CFR 1025.66 - Qualifications and standards of conduct.

Science.gov (United States)

2010-01-01

... standards of conduct. (a) Good faith transactions. The Commission expects all persons appearing in... conducted in good faith. (b) Exclusion of parties, participants, or their representatives. To maintain... reasonable standards of orderly and ethical conduct, failure to act in good faith, or violation of the...

Shaking table qualification tests of mechanical and electrical components

International Nuclear Information System (INIS)

Jurukovski, D.

1993-01-01

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

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...

Transportability of tertiary qualifications and CPD: A continuing challenge for the global health workforce

Directory of Open Access Journals (Sweden)

Saltman Deborah C

2012-07-01

Full Text Available Abstract Background In workforces that are traditionally mobile and have long lead times for new supply, such as health, effective global indicators of tertiary education are increasingly essential. Difficulties with transportability of qualifications and cross-accreditation are now recognised as key barriers to meeting the rapidly shifting international demands for health care providers. The plethora of mixed education and service arrangements poses challenges for employers and regulators, let alone patients; in determining equivalence of training and competency between individuals, institutions and geographical locations. Discussion This paper outlines the shortfall of the current indicators in assisting the process of global certification and competency recognition in the health care workforce. Using Organisation for Economic Cooperation and Development (OECD data we highlight how International standardisation in the tertiary education sector is problematic for the global health workforce. Through a series of case studies, we then describe a model which enables institutions to compare themselves internally and with others internationally using bespoke or prioritised parameters rather than standards. Summary The mobility of the global health workforce means that transportability of qualifications is an increasing area of concern. Valid qualifications based on workplace learning and assessment requires at least some variables to be benchmarked in order to judge performance.

A brief review of nuclear electronics standards . . . Past, present and future

International Nuclear Information System (INIS)

Larsen, R.S.

2000-01-01

Modular Nuclear Instrument Standards have played a key role in U. S. Department of Energy National Laboratories and similar scientific laboratories worldwide for more than three decades. The scientific and engineering efficiency and economic benefits have been well documented. Standards are constantly evolving with the introduction of new technologies and the present is a time of rapid change. This report is based on an invited talk presented at the Joint Meeting of the U.S. Nuclear Instrument Module (NIM) and European Standards for Norms in Electronics (ESONE) Standards Committees, Lyon, France, October 20, 2000. It provides a brief overview of past developments and attempts to identify areas of possible opportunities for renewed standardization efforts to meet future challenges

Environmental data qualification system

International Nuclear Information System (INIS)

Hester, O.V.; Groh, M.R.

1989-01-01

The Integrated Environmental Data Management System (IEDMS) is a PC-based system that can support environmental investigations from their design stage and throughout the duration of the study. The system integrates data originating from the Sampling and Analysis Plan, field data and analytical findings. The IEDMS automated features include sampling guidance forms, barcoded sample labels and tags, field and analytical forms reproduction, sample tracking, analytical data qualification, completeness reports, and results and QC data reporting. The IEDMS has extensive automated capabilities that support a systematic and comprehensive process for performing quality assessment of EPA-CLP chemical analyses data. One product of this process is a unique and extremely useful tabular presentation of the data. One table contains the complete set of results and QC data included on the CLP data forms while presenting the information consistent with the chronology in which the analysis was performed. 3 refs., 1 fig

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

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

Contribution of the ultrasonic simulation to the testing methods qualification process; Contribution de la modelisation ultrasonore au processus de qualification des methodes de controle

Energy Technology Data Exchange (ETDEWEB)

Le Ber, L.; Calmon, P. [CEA/Saclay, STA, 91 - Gif-sur-Yvette (France); Abittan, E. [Electricite de France (EDF-GDL), 93 - Saint-Denis (France)

2001-07-01

The CEA and EDF have started a study concerning the simulation interest in the qualification of nuclear components control by ultrasonic methods. In this framework, the simulation tools of the CEA, as CIVA, have been tested on real control. The method and the results obtained on some examples are presented. (A.L.B.)

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...

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

International Nuclear Information System (INIS)

Chang, T.Y.

1987-02-01

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

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

International Nuclear Information System (INIS)

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

2004-01-01

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

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

Progress on qualification testing methodology study of electric cables

International Nuclear Information System (INIS)

Yoshida, K.; Seguchi, T.; Okada, S.; Ito, M.; Kusama, Y.; Yagi, T.; Yoshikawa, M.

1983-01-01

Many instrumental, control and power cables are installed in nuclear power plants, and these cables contain a large amount of organic polymers as insulating and jacketing materials. They are exposed to radiation at high dose rate, steam at high temperature and chemical (or water) spray simultaneously when a LOCA occurs. Under such conditions, the polymers tend to lose their original properties. For reactor safety, the cables should be functional even if they are subjected to a loss-of-coolant accident (LOCA) at the end of their intended service life. In Japan, cable manufacturers qualify their cables according to the proposed test standard issued from IEEJ in 1982, but the standard still has many unsolved problems or uncertainties which have been dealt with tentatively through the manufacturer-user's agreement. The objectives of this research are to study the methodologies for qualification testing of electric wires and cables, and to provide the improved technical bases for modification of the standard. Research activities are divided into the Accident (LOCA) Testing Methodology and the Accelerated Aging Methodology

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...

Text-Mining and Gamification for the Qualification of Service Technicians in the Maintenance Industry of Offshore Wind Energy

Directory of Open Access Journals (Sweden)

Thies Beinke

2017-04-01

Full Text Available The competition of maintenance services in the offshore wind industry is continually increasing. The quality of the services acts as the distinguishing feature in the industry. Furthermore, there are public standards, which lead to the permanent necessity to offer further education and training programs for employees. To meet the requirements for further training in the specific field of application within the offshore wind industry, a gamified e-learning application has been developed and is introduced in this paper. It consists of a complete solution, which contains the automated analysis of service protocols to identify qualification needs, the involvement of service technicians in the generation of learning materials, the preparation, transmission as well as the further development of those materials in accordance with the principles of e-learning. Finally, the solution contains a gamified mobile application for qualification, which is designed to meet the individual learning needs of the service technicians. This concept paper follows a problem-centred approach. Based on the current state of technology and research, the problem and motivation are identified and the urgency is verified. Furthermore, a detailed specification of the solution and a first implementation approach is presented.

Prognostics-based qualification of high-power white LEDs using Lévy process approach

Science.gov (United States)

Yung, Kam-Chuen; Sun, Bo; Jiang, Xiaopeng

2017-01-01

Due to their versatility in a variety of applications and the growing market demand, high-power white light-emitting diodes (LEDs) have attracted considerable attention. Reliability qualification testing is an essential part of the product development process to ensure the reliability of a new LED product before its release. However, the widely used IES-TM-21 method does not provide comprehensive reliability information. For more accurate and effective qualification, this paper presents a novel method based on prognostics techniques. Prognostics is an engineering technology predicting the future reliability or determining the remaining useful lifetime (RUL) of a product by assessing the extent of deviation or degradation from its expected normal operating conditions. A Lévy subordinator of a mixed Gamma and compound Poisson process is used to describe the actual degradation process of LEDs characterized by random sporadic small jumps of degradation degree, and the reliability function is derived for qualification with different distribution forms of jump sizes. The IES LM-80 test results reported by different LED vendors are used to develop and validate the qualification methodology. This study will be helpful for LED manufacturers to reduce the total test time and cost required to qualify the reliability of an LED product.

Biomarker Qualification: Toward a Multiple Stakeholder Framework for Biomarker Development, Regulatory Acceptance, and Utilization.

Science.gov (United States)

Amur, S; LaVange, L; Zineh, I; Buckman-Garner, S; Woodcock, J

2015-07-01

The discovery, development, and use of biomarkers for a variety of drug development purposes are areas of tremendous interest and need. Biomarkers can become accepted for use through submission of biomarker data during the drug approval process. Another emerging pathway for acceptance of biomarkers is via the biomarker qualification program developed by the Center for Drug Evaluation and Research (CDER, US Food and Drug Administration). Evidentiary standards are needed to develop and evaluate various types of biomarkers for their intended use and multiple stakeholders, including academia, industry, government, and consortia must work together to help develop this evidence. The article describes various types of biomarkers that can be useful in drug development and evidentiary considerations that are important for qualification. A path forward for coordinating efforts to identify and explore needed biomarkers is proposed for consideration. © 2015 American Society for Clinical Pharmacology and Therapeutics.

Developments in mechanical ultrasonic inspection and qualification of NDE

International Nuclear Information System (INIS)

Kauppinen, P.; Pitkaenen, J.; Kuusinen, P.

2001-01-01

Reliability of non-destructive testing results has a direct influence on structural integrity assessment and safety of the inspected structures e.g. NPP primary circuit pressure boundaries. Advanced technology together with highly skilled and experienced personnel is required. One of the current trends is automation. Mechanised equipment can replace tedious manual work in positioning and moving of the transducers. Large areas can be scanned, analysed and numerically documented for direct comparison of eventual later repeated inspections. Another major trend is qualification, which aims to ensure that the inspection results are correct and fit the purpose. The suitability and proper operation of equipment, methods and personnel i.e. the whole chain shall be proven. This presentation summarises the advances in automation and qualification of non-destructive inspection during the second project year, Monitoring of material degradation was included in the studied topics and will also be shortly described. (author)

CMS Pixel Upgrade for the Phase I: Module Production and Qualification

CERN Document Server

AUTHOR|(CDS)2078028

2016-01-01

The present CMS pixel detector has been designed to be fully efficient up to a LHC luminosity of $10^{34}~\\mathrm{cm}^{-2}~\\mathrm{s}^{-1}$. However, the luminosity will increase by a factor of two in the coming years. Therefore it is planned to build and install a new detector in the extended year-end technical stop (YETS) in 2016-17. Barrel pixel modules are in production since Spring/Summer 2015 in five different centers. Module production requires bump bonding, wire bonding and gluing processes to finally assemble a full module. To have a uniform performance of all modules standard qualification procedures have been developed. All modules will be subjected to 10 termal cycles between +$17^{\\circ}$C and -$25^{\\circ }$C and then electrically tested. In addition, module performance will be verified under high rate X-rays, and internal calibrate signals used for electrical tests will be calibrated in units of electrons using well defined X-ray fluorescence lines from different target materials. The qualifica...

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...

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

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

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…

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...

40 CFR 60.2890 - How are these new source performance standards structured?

Science.gov (United States)

2010-07-01

... standards structured? 60.2890 Section 60.2890 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY... standards contain nine major components, as follows: (a) Preconstruction siting analysis. (b) Waste management plan. (c) Operator training and qualification. (d) Emission limitations and operating limits. (e...

Experimental comparison of the different methods for seismic qualification of electrical cabinets

International Nuclear Information System (INIS)

Buland, P.; Gauthier, G.; Simon, D.

1993-01-01

This paper presents the results of an experimental seismic study performed on a cabinet equipped with 96 acceleration sensitive relays located in four racks. The aim of this study is to verify the validity of the seismic qualification method proposed in the IEC 980 standard. The cabinet was primarily tested on a shaking table and the relay chatter was monitored. The interactions between the racks and the cabinet frame induce shocks which were correlated with some of the contact openings. The racks were afterwards tested individually with the accelerations recorded during the cabinet test. A comparison of relay chatter was performed for both test phases. An important reduction of relay chatter was noticed during the racks test. This is due to the fact that it is not possible to fully represent on shaking table the complex vibration environment (shocks) sustained by a rack in a cabinet

SU-B-213-00: Education Council Symposium: Accreditation and Certification: Establishing Educational Standards and Evaluating Candidates Based on these Standards

International Nuclear Information System (INIS)

2015-01-01

The North American medical physics community validates the education received by medical physicists and the clinical qualifications for medical physicists through accreditation of educational programs and certification of medical physicists. Medical physics educational programs (graduate education and residency education) are accredited by the Commission on Accreditation of Medical Physics Education Programs (CAMPEP), whereas medical physicists are certified by several organizations, the most familiar of which is the American Board of Radiology (ABR). In order for an educational program to become accredited or a medical physicist to become certified, the applicant must meet certain specified standards set by the appropriate organization. In this Symposium, representatives from both CAMPEP and the ABR will describe the process by which standards are established as well as the process by which qualifications of candidates for accreditation or certification are shown to be compliant with these standards. The Symposium will conclude with a panel discussion. Learning Objectives: Recognize the difference between accreditation of an educational program and certification of an individual Identify the two organizations primarily responsible for these tasks Describe the development of educational standards Describe the process by which examination questions are developed GS is Executive Secretary of CAMPEP

Leading professions bank on new standards in the sector of power-, gas- and water supply engineering; Einschlaegige Leitberufe setzen neue Standards in der Strom-, Gas- und Wasserversorgungstechnik

Energy Technology Data Exchange (ETDEWEB)

Fassnacht, Axel [Univ. Hannover (Germany)

2009-09-15

With the emergence of new professions and training subjects in power and water supply engineering, new standards have been set for vocational qualifications. Experts of public utilities and industrial associations have cooperated in setting a new frame of standards for the new professions. (orig.)

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.

A systematic approach to the training in the nuclear power industry: The need for standard

International Nuclear Information System (INIS)

Wilkinson, J.D.

1995-01-01

The five elements of a open-quotes Systematic Approach to Trainingclose quotes (SAT) are analysis, design, development, implementation and evaluation. These elements are also present in the effective application of basic process control. The fundamental negative feedback process control loop is therefore an excellent model for a successful, systematic approach to training in the nuclear power industry. Just as standards are required in today's manufacturing and service industries, eg ISO 9000, so too are control standards needed in the training industry and in particular in the training of nuclear power plant staff. The International Atomic Energy Agency (IAEA) produced its TECDOC 525 on open-quotes Training to Establish and Maintain the Qualification and Competence of Nuclear Power Plant Operations Personnelclose quotes in 1989 and the American Nuclear Society published its open-quotes Selection, Qualification, and Training of Personnel for Nuclear Power Plants, an American National Standardclose quotes in 1993. It is important that community colleges, training vendors and organizations such as the Instrument Society of America (ISA), who may be supplying basic or prerequisite training to the nuclear power industry, become aware of these and other standards relating to training in the nuclear power industry

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)

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.)

Design, Qualification and Lessons Learned of the Shutter Calibration Mechanism for EnMAP Mission

Science.gov (United States)

Schmidt, Tilo; Muller, Silvio; Bergander, Arvid; Zajac, Kai; Seifart, Klaus

2015-09-01

The Shutter Calibration Mechanism (SCM) Assembly is one of three mechanisms which are developed by HTS for the EnMAP instrument in subcontract to OHB System AG Munich. EnMAP is the Environmental Mapping and Analysis Program of the German Space Agency DLR.The binary rotary encoder of the SCM using hall-effect sensors was already presented during ESMATS 2011. This paper summarizes the main functions and design features of the Hardware and focuses on qualification testing which has finished successfully in 2014. Of particular interest is the functional testing of the main drive including the precise hall-effect position sensing system and the test of the fail safe mechanism. In addition to standard test campaign required for QM also a shock emission measurement of the fail safe mechanism activation was conducted.Test conduction and results will be presented with focus on deviations from the expected behaviour, mitigation measures and on lessons learned.

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

International Nuclear Information System (INIS)

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

2015-01-01

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

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...

Qualification of code-Saturne for thermal-hydraulics single phase nuclear applications

International Nuclear Information System (INIS)

Archambeau, F.; Bechaud, C.; Gest, B.; Martin, A.; Sakiz, M.

2003-01-01

Code-Saturne is a general finite volume CFD (computational fluid dynamics) code developed by Electricite de France (EDF) under quality assurance for 2- and 3-dimensional simulations, laminar and turbulent flows, conjugate heat transfer (coupling with thermal code SYRTHES), including combustion modelling and a Lagrangian module. A very large range of meshes can be used. The solver relies on a finite volume method on arbitrary meshes (hybrid, with hanging nodes, any type of element). All variables are located at the cell centres. The solver is time marching, with a predictor-corrector scheme for Navier-Stokes equations. Standard Reynolds Average Navier-Stokes modelling (RANS) is included (k-epsilon, RSM). Code-Saturne is used by EDF in various industrial fields such as process engineering, aeraulics, combustion and nuclear applications. The present paper describes the qualification phase carried out during 2001 for single-phase nuclear applications. Indeed, once an industrial product has been released and validated, it is of major importance, especially in this particular field related to safety matters, to demonstrate the ability of the code to help engineers produce satisfactory conclusions to industrial problems. In coherence with analyses and best practice guidelines such as those published by the ERCOFTAC Special Interest Group, it seemed important to base the qualification phase on well defined and documented experimental facilities, sufficiently complex to be representative of industrial studies. Much attention has been devoted to evaluating sensitivity to numerical parameters such as grid refinement, time step... Moreover, the qualification studies have been carried out in real-life conditions, that is in limited time, with industrial limitations on the number of grid cells, and by the teams usually producing such studies, so as to integrate a real industrial process in the qualification phase. Two test cases chosen to assess certain types of flows in PWR

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…

SU-B-213-02: Development of CAMPEP Standards

International Nuclear Information System (INIS)

Beckham, W.

2015-01-01

The North American medical physics community validates the education received by medical physicists and the clinical qualifications for medical physicists through accreditation of educational programs and certification of medical physicists. Medical physics educational programs (graduate education and residency education) are accredited by the Commission on Accreditation of Medical Physics Education Programs (CAMPEP), whereas medical physicists are certified by several organizations, the most familiar of which is the American Board of Radiology (ABR). In order for an educational program to become accredited or a medical physicist to become certified, the applicant must meet certain specified standards set by the appropriate organization. In this Symposium, representatives from both CAMPEP and the ABR will describe the process by which standards are established as well as the process by which qualifications of candidates for accreditation or certification are shown to be compliant with these standards. The Symposium will conclude with a panel discussion. Learning Objectives: Recognize the difference between accreditation of an educational program and certification of an individual Identify the two organizations primarily responsible for these tasks Describe the development of educational standards Describe the process by which examination questions are developed GS is Executive Secretary of CAMPEP

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

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)

Inspection Qualification Centre in NPP 'Kozloduy'

International Nuclear Information System (INIS)

Mikhovski, M.

2000-01-01

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

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 tests for a type B (U) package

International Nuclear Information System (INIS)

Vieru, G.

2004-01-01

The primary objective for the safety of radioactive materials transport is to protect human health and the environment taking into consideration its potential risks and radiological consequences. Romania as a Member State of the International Atomic Energy Agency has implemented national regulations for the safe transport of radioactive materials (RAM) in accordance with the Agency's recommendations as well as other international specialized organizations. The paper will describe the qualification tests performed for a type B (U) package, intended to be used for the transport of the radioactive sources Am-241 and Cs-137. For this kind of package the tests were performed the first time in Romania and include: the water spray test, the 1.2 m free drop test, the stacking test, the penetration test, the 9m free drop test, the thermal test and the submersion under a head of water of at least 15 m. The test facilities used for performing qualification tests for the type B (U) package as well as experience and conclusions will be also presented

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

International Nuclear Information System (INIS)

Kraut, A.; Pfeffer, W.

1987-01-01

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

Calculation qualification of gadolinium burnable poisons in water reactors

International Nuclear Information System (INIS)

Chaucheprat, P.

1988-01-01

The work presented in this thesis constitutes the qualification on the one end of Appolo-Neptune scheme for the gadolinium burnable poison in a pressurized water reactor, and on the other end of basis nuclear data on natural gadolinium. This study has permitted to reduce by a factor 3 the actual incertitude on the gadolinium poison comparatively at precisions cited in international benchmarks calculations [fr

42 CFR 493.1423 - Standard; Testing personnel qualifications.

Science.gov (United States)

2010-10-01

..., or bachelor's degree in a chemical, physical, biological or clinical laboratory science, or medical... stability and storage; (F) The skills required to implement the quality control policies and procedures of... HUMAN SERVICES (CONTINUED) STANDARDS AND CERTIFICATION LABORATORY REQUIREMENTS Personnel for Nonwaived...

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

Science.gov (United States)

Clark, A; Hook, J; Stein, K

1997-01-01

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

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

Application of a Bayesian model for the quantification of the European methodology for qualification of non-destructive testing

International Nuclear Information System (INIS)

Gandossi, Luca; Simola, Kaisa; Shepherd, Barrie

2010-01-01

The European methodology for qualification of non-destructive testing is a well-established approach adopted by nuclear utilities in many European countries. According to this methodology, qualification is based on a combination of technical justification and practical trials. The methodology is qualitative in nature, and it does not give explicit guidance on how the evidence from the technical justification and results from trials should be weighted. A Bayesian model for the quantification process was presented in a previous paper, proposing a way to combine the 'soft' evidence contained in a technical justification with the 'hard' evidence obtained from practical trials. This paper describes the results of a pilot study in which such a Bayesian model was applied to two realistic Qualification Dossiers by experienced NDT qualification specialists. At the end of the study, recommendations were made and a set of guidelines was developed for the application of the Bayesian model.

Standard guide for computed radiography

CERN Document Server

American Society for Testing and Materials. Philadelphia

2010-01-01

1.1 This guide provides general tutorial information regarding the fundamental and physical principles of computed radiography (CR), definitions and terminology required to understand the basic CR process. An introduction to some of the limitations that are typically encountered during the establishment of techniques and basic image processing methods are also provided. This guide does not provide specific techniques or acceptance criteria for specific end-user inspection applications. Information presented within this guide may be useful in conjunction with those standards of 1.2. 1.2 CR techniques for general inspection applications may be found in Practice E2033. Technical qualification attributes for CR systems may be found in Practice E2445. Criteria for classification of CR system technical performance levels may be found in Practice E2446. Reference Images Standards E2422, E2660, and E2669 contain digital reference acceptance illustrations. 1.3 The values stated in SI units are to be regarded as the st...

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...

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

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...

A Path to Alignment: Connecting K-12 and Higher Education via the Common Core and the Degree Qualifications Profile

Science.gov (United States)

Conley, David T.; Gaston, Paul L.

2013-01-01

The Common Core State Standards (CCSS), which aim to assure competency in English/language arts and mathematics through the K-12 curriculum, define necessary but not sufficient preparedness for success in college. The Degree Qualifications Profile (DQP), which describes what a college degree should signify, regardless of major, offers useful but…

Training for the qualification and competence of nuclear power plant personnel. Working material

International Nuclear Information System (INIS)

1993-01-01

This document contains summaries of the presentations prepared for the IAEA Review Meeting ''Training for the Qualification and Competence of Nuclear Power Plant Personnel''. The individual contributors have been indexed separately for the database. Refs, figs and tabs

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 ...

Code qualification of structural materials for AFCI advanced recycling reactors.

Energy Technology Data Exchange (ETDEWEB)

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

2012-05-31

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

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.

Contribution of the ultrasonic simulation to the testing methods qualification process

International Nuclear Information System (INIS)

Le Ber, L.; Calmon, P.; Abittan, E.

2001-01-01

The CEA and EDF have started a study concerning the simulation interest in the qualification of nuclear components control by ultrasonic methods. In this framework, the simulation tools of the CEA, as CIVA, have been tested on real control. The method and the results obtained on some examples are presented. (A.L.B.)

The DWPF: Results of full scale qualification runs leading to radioactive operations

International Nuclear Information System (INIS)

Marra, S.L.; Elder, H.H.; Occhipinti, J.H.; Snyder, D.E.

1996-01-01

The Defense Waste Processing Facility (DWPF) at the Savannah River Site in Aiken, SC will immobilize high-level radioactive liquid waste, currently stored in underground carbon steel tanks, in borosilicate glass. The radioactive waste is transferred to the DWPF in two forms: precipitate slurry and sludge slurry. The radioactive waste is pretreated and then combined with a borosilicate glass frit in the DWPF. This homogeneous slurry is fed to a Joule-heated melter which operates at approximately 1150 degrees C. The glass is poured into stainless steel canisters for eventual disposal in a geologic repository. The DWPF product (i.e. the canistered waste form) must comply with the Waste Acceptance Product Specifications (WAPS) in order to be acceptable for disposal. The DWPF has completed Waste Qualification Runs which demonstrate the facility's ability to comply with the waste acceptance specifications. During the Waste Qualification Runs seventy-one canisters of simulated waste glass were produced in preparation for Radioactive Operations. These canisters of simulated waste glass were produced during five production campaigns which also exercised the facility prior to beginning Radioactive Operations. The results of the Waste Qualification Runs are presented

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

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...

AP-102/104 Retrieval control system qualification test procedure

International Nuclear Information System (INIS)

RIECK, C.A.

1999-01-01

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

Kwalifikacje i kompetencje trenerów personalnych a oczekiwania rynku pracy = Personal trainers professional qualifications - demands of the labour market

Directory of Open Access Journals (Sweden)

Aleksandra Leśniewska

2016-09-01

Abstract Fitness has been a growth industry over the past years and seems not to be saturated on the polish ground. Fitness clubs offer a wide range of services to their clients from group classes to individual trainings such as personal training. However, personal trainers in Poland have conducive and effortless way to access to their profession, they still struggle with the lack of professional standards and incoherent educationa; system. The main purpose of this article was to define what are the demands of the labour market in terms of required qualifications and competences for personal trainers who are taking part in recruitment process.   Keywords: personal trainer, fitness services, qualifications and competencies, labour market

SU-B-213-05: Development of ABR Certification Standards

International Nuclear Information System (INIS)

Seibert, J.

2015-01-01

The North American medical physics community validates the education received by medical physicists and the clinical qualifications for medical physicists through accreditation of educational programs and certification of medical physicists. Medical physics educational programs (graduate education and residency education) are accredited by the Commission on Accreditation of Medical Physics Education Programs (CAMPEP), whereas medical physicists are certified by several organizations, the most familiar of which is the American Board of Radiology (ABR). In order for an educational program to become accredited or a medical physicist to become certified, the applicant must meet certain specified standards set by the appropriate organization. In this Symposium, representatives from both CAMPEP and the ABR will describe the process by which standards are established as well as the process by which qualifications of candidates for accreditation or certification are shown to be compliant with these standards. The Symposium will conclude with a panel discussion. Learning Objectives: Recognize the difference between accreditation of an educational program and certification of an individual Identify the two organizations primarily responsible for these tasks Describe the development of educational standards Describe the process by which examination questions are developed GS is Executive Secretary of CAMPEP

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

International Nuclear Information System (INIS)

Anon.

1975-01-01

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

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...

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

International Nuclear Information System (INIS)

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

2012-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2012-05-16

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

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…

Guidebook for establishing a sustainable and accredited system for qualification and certification of personnel for non-destructive testing

International Nuclear Information System (INIS)

2009-01-01

Non-destructive testing (NDT) methods are used for detection, location and sizing of surface and internal defects (in welds, castings, forging, composite materials, concrete and many more). Various NDT methods are also used in preventive maintenance (nuclear power plants, aircraft, bridges, etc.). NDT methods are essential to the inspection of raw materials and half-finished products. They are applied to finished products and to in-service inspection, as well as for the design and development of new products and for plant life assessment studies. Thus NDT technology contributes significantly to the protection of life, public health and the environment through assurance of the quality and integrity of critical equipment and facilities. It is especially important in the developing Member States where the consequences of failure may be particularly severe, resulting in social, financial and environmental impacts. The IAEA has supported developing Member States for capacity building in utilization of NDT technology by providing experts, equipment, training opportunities and scientific visits. It was recognized early that NDT operator qualification and certification deserved special attention as the Member States began to apply NDT technology to local industrial problems. A series of meetings, workshops and publications have been dedicated to this issue. These efforts have led to a stage of maturity and self-sufficiency in many countries, especially in the field of training and certification of personnel, and in the provision of services to industries. ISO 9712, the international standard for qualification and certification of NDT personnel, has been adopted as the cornerstone for carrying out the training and certification activities. In 2005, a revised version of the standard, ISO 9712:2005, was published. There are some significant differences in this standard from previous editions, particularly in reference to an accreditation standard, ISO/IEC 17024:2003 (2003

76 FR 70414 - National Fire Protection Association (NFPA) Proposes To Revise Codes and Standards

Science.gov (United States)

2011-11-14

... Commercial Cooking Operations. NFPA 99--2012 Health Care Facilities Code 6/22/2012 NFPA 99B--2010 Standard... Explosion Investigations..... 1/4/2012 NFPA 1005--2007 Standard for Professional Qualifications for 1/4/2012 Marine Fire Fighting for Land-Based Fire Fighters. NFPA 1021--2009 Standard for Fire Officer Professional...

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

International Nuclear Information System (INIS)

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

1996-01-01

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

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

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.

Space qualification of an experimental two-phase flow thermal management system

International Nuclear Information System (INIS)

Koonmen, J.P.; Carswell, L.C.; Kvansnak, M.A.

1991-01-01

The Weapons Laboratory will launch a space experiment in March 1991 to investigate the effects of extended microgravity on two-phase (liquid/vapor) flow. The qualification process for the experimental flight system hardware differs significantly from the process used for complex, high cost, long life space systems. Some development, qualification, and acceptance tests normally included in the test program of an operational space system were omitted because of the low program cost and low consequence of experiment failure. Key environment and functional qualification tests were performed, however, in an effort to reduce the risk of failure inherent in any space mission. The environmental qualification program included short duration vacuum chamber tests, reduced gravity missions onboard a National Aeronautics and Space Administration (NASA) test aircraft, and a complete series of shock and vibration tests. The functional qualification program centered on thermal-hydraulic system performance tests and a complete check-out of the unique telemetry system used to retrieve the experimental data from the payload. The test program also contains a number of acceptance and prelaunch validation tests to be performed as final verification of payloads readiness for spaceflight

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

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

International Nuclear Information System (INIS)

Chang, T.Y.

1985-08-01

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

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

Qualification and Life Testing of Li-Ion Ves16 Batteries

Directory of Open Access Journals (Sweden)

Remy Stéphane

2017-01-01

Up to the present time, Saft batteries have been mainly utilizing for space applications high capacity cells, like the 45 Ah VES180 and the 35 Ah VES140 cells, targeting predominantly space missions in Geostationary Earth Orbit (GEO. However following the qualification and commercialization of the Saft 4.5 Ah VES16 cell in October 2011 [1] & [2], Saft has been developing and qualifying in the frame of this ESA GSTP 5.2 contract, VES 16 batteries for space missions, targeting both GEO and Low Earth Orbit (LEO satellite missions. The electrochemistry of the VES16 cells used for the battery modules under the ESA qualification program is not novel. For VES16 cells, the Saft knowhow from large capacity space cells used for space applications, since SMART 1 mission in 2003, has been tailored for a cell with smaller capacity in order to facilitate the modular philosophy that has been deployed in this battery range.

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

Qualification of PHT piping of Indian 500 MW PHWR for LBB, using R-6 method

International Nuclear Information System (INIS)

Rastogi, Rohit; Bhasin, V.; Kushwaha, H.S.

1997-01-01

This document discusses the qualification of straight pipe portion of the primary heat transport (PHT) piping of Indian 500 MWe pressurised heavy water reactor (PHWR) for leak before break (LBB). The evaluation is done using R-6 [1] method. The results presented here are: the safety margins which exist on straight pipe components of main PHT piping of 500 MWe, under leakage size crack (LSC) and design basis accident loads; the sensitivity of safety margins with respect to different analysis parameters and the qualification of PHT piping for LBB based on criterion given by NUREG-1061 [2] and TECDOC-774 [3]. (author)

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...

IEEE Std 649-1991: IEEE standard for qualifying Class 1E motor control centers for nuclear power generating stations

International Nuclear Information System (INIS)

Anon.

1993-01-01

The basic principles, requirements, and methods for qualifying Class 1E motor control centers for both harsh and mild environment applications in nuclear power generating stations are described. In addition to defining specific qualification requirements for Class 1E motor control centers and their components in accordance with the more general qualification requirements of IEEE Std 323-1983, this standard is intended to provide guidance in establishing a qualification program for demonstrating the adequacy of Class 1E motor control centers in nuclear power generating station applications

Effects of Student Characteristics, Principal Qualifications, and Organizational Constraints for Assessing Student Achievement: A School Public Relations and Human Resources Concern

Science.gov (United States)

Young, I. Phillip; Vang, Maiyoua; Young, Karen Holsey

2008-01-01

Standards-based student achievement scores are used to assess the effectiveness of public education and to have important implications regarding school public relations and human resource practices. Often overlooked is that these scores may be moderated by the characteristics of students, the qualifications of principals, and the restraints…

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'

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,…

A new standard for multidisciplinary health and safety technicians

International Nuclear Information System (INIS)

Trinoskey, P.A.; Fry, L.A.; Egbert, W.F.

2000-01-01

Over the last two decades, a significant trend in health and safety has been toward greater specialization. However, compartmentalization of health and safety disciplines often leads to an inequity in resources, especially when appropriations overemphasize one risk to the detriment of others. For example, overemphasis on radiological safety can create an imbalance in overall worker protection. A multidisciplinary technical can help restore the balance and provide for a healthier and safer work environment. The key advantages of a multidisciplinary health and safety technician include: Broad coverage of the work area by one technician, More diverse use of the technician pool, Better coverage for off-shift or nonstandard hours, Balance of risks because all hazards are considered, Integrated emergency response, Ownership, Less time of identify the correct person with the requisite skills. We have developed a new standard that establishes the training and related qualifications for a multidisciplinary health and safety technician. The areas of training and qualification that are addressed include elements of industrial hygiene, industrial safety, fire protection, electrical safety, construction safety, and radiation safety. The initial core training program ensures that individuals are trained to the performance of requirements of the job. Initial training is in five areas: Fundamentals, Hazard recognition, Hazard assessment, Hazards controls, Hazards minimization. Core training is followed by formal qualification on specific tasks, including ventilation surveys, air monitoring, noise assessments, radiological monitoring, area inspections, work-area setups, and work coverage. The new standard addresses not only training topics and requirements, but also guidance to ensure that performance objectives are met. The standard applies to technicians, supervisors, technologists, and six specialty areas, including academic institutions and decontamination and decommissioning

A new standard for multidisciplinary health and safety technicians

Energy Technology Data Exchange (ETDEWEB)

Trinoskey, P.A.; Fry, L.A. [Lawrence Livermore National Laboratory, Univ. of California, CA (United States); Egbert, W.F. [Lawrence Livermore National Laboratory, Allied Signal Technical Corporation (United States)

2000-05-01

Over the last two decades, a significant trend in health and safety has been toward greater specialization. However, compartmentalization of health and safety disciplines often leads to an inequity in resources, especially when appropriations overemphasize one risk to the detriment of others. For example, overemphasis on radiological safety can create an imbalance in overall worker protection. A multidisciplinary technical can help restore the balance and provide for a healthier and safer work environment. The key advantages of a multidisciplinary health and safety technician include: Broad coverage of the work area by one technician, More diverse use of the technician pool, Better coverage for off-shift or nonstandard hours, Balance of risks because all hazards are considered, Integrated emergency response, Ownership, Less time of identify the correct person with the requisite skills. We have developed a new standard that establishes the training and related qualifications for a multidisciplinary health and safety technician. The areas of training and qualification that are addressed include elements of industrial hygiene, industrial safety, fire protection, electrical safety, construction safety, and radiation safety. The initial core training program ensures that individuals are trained to the performance of requirements of the job. Initial training is in five areas: Fundamentals, Hazard recognition, Hazard assessment, Hazards controls, Hazards minimization. Core training is followed by formal qualification on specific tasks, including ventilation surveys, air monitoring, noise assessments, radiological monitoring, area inspections, work-area setups, and work coverage. The new standard addresses not only training topics and requirements, but also guidance to ensure that performance objectives are met. The standard applies to technicians, supervisors, technologists, and six specialty areas, including academic institutions and decontamination and decommissioning

1994 report on Tasks 4.3.1 and 4.3.2: Survey of anticipated requirements and qualification requirements for OSS

International Nuclear Information System (INIS)

Silvani, V.

1995-01-01

This is a preliminary report summarizing some topics related to the survey on functional and qualification requirements of Operator Support Systems (OSS's) in NPP's. This document has been prepared on the basis of the information presented in the previous meetings of this CRP working group. Additional information are expected when the answers to the working group questionnaire will be available. Functionalities examined are those referring to system functions and user's needs; technology trends are also considered. For practical purposes this document is divided in the followings: Summary of major OSS requirements and related problems as derived from the existing literature; appendix 1 reporting a summary of major functions performed by the OSS's presently in operation or under development in laboratories; appendix 2 reporting the list of standards for critical software. 18 refs, tabs

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...

Optimized qualification protocol on particle cleanliness for EUV mask infrastructure

Science.gov (United States)

van der Donck, J. C. J.; Stortelder, J. K.; Derksen, G. B.

2011-11-01

With the market introduction of the NXE:3100, Extreme Ultra Violet Lithography (EUVL) enters a new stage. Now infrastructure in the wafer fabs must be prepared for new processes and new materials. Especially the infrastructure for masks poses a challenge. Because of the absence of a pellicle reticle front sides are exceptionally vulnerable to particles. It was also shown that particles on the backside of a reticle may cause tool down time. These effects set extreme requirements to the cleanliness level of the fab infrastructure for EUV masks. The cost of EUV masks justifies the use of equipment that is qualified on particle cleanliness. Until now equipment qualification on particle cleanliness have not been carried out with statistically based qualification procedures. Since we are dealing with extreme clean equipment the number of observed particles is expected to be very low. These particle levels can only be measured by repetitively cycling a mask substrate in the equipment. Recent work in the EUV AD-tool presents data on added particles during load/unload cycles, reported as number of Particles per Reticle Pass (PRP). In the interpretation of the data, variation by deposition statistics is not taken into account. In measurements with low numbers of added particles the standard deviation in PRP number can be large. An additional issue is that particles which are added in the routing outside the equipment may have a large impact on the testing result. The number mismatch between a single handling step outside the tool and the multiple cycling in the equipment makes accuracy of measurements rather complex. The low number of expected particles, the large variation in results and the combined effect of added particles inside and outside the equipment justifies putting good effort in making a test plan. Without a proper statistical background, tests may not be suitable for proving that equipment qualifies for the limiting cleanliness levels. Other risks are that a

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

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)

Qualification testing facility for type A, B and C packages to be used for transport and storage of radioactive materials

International Nuclear Information System (INIS)

Vieru, G.; Nistor, V.; Vasile, A.; Cojocaru, V.

2009-01-01

In accordance with the Economic Commission for Europe-Committee on inland transport (ADR- European Agreement-concerning the international carriage of dangerous goods by road, 2007 Edition) the Safety and Security of the dangerous goods class No. 7 - Radioactive Materials during transport in all different modes - by road, by rail, by sea, by inland rivers or by air - have to be ensured at a very high level. The radioactive materials (RAM) packaging have to comply to all transport conditions, routine or in accident conditions, possibly to occur during transportation operations. It is well known that the safety in the transport of RAM is dependent on packaging appropriate for the contents being shipped rather than on operational and/or administrative actions required for the package. The quality of these packages - type A, B or C has to be proved by performing qualification tests in accordance with the Romanian nuclear regulation conditions provided by CNCAN Order no. 357/22.12.2005- N orms for a Safe Transport of Radioactive Material , the IAEA Vienna Recommendation (1, 2) stipulated in the Safety standard TS-R-1- Regulation for the Safe Transport of Radioactive Material, 2005 Edition, and other applicable international recommendations. The paper will describe the components of the designed testing facilities, and the qualification testing to be performed for all type A, B and C packages subjected to the testing Quality assurance and quality controls measures taken in order to meet technical specification provided by the design are also presented and commented. The paper concludes that the new Romanian Testing Facilities for RAM packages will comply with the national safe standards as well as with the IAEA applicable recommendation provided by the TS-R-1 safety standard. (authors)

Defense Standardization Program Journal. January-March 2012

Science.gov (United States)

2012-03-01

example, the team added standardized qualification and performance verification procedures, such as edge-reten- tion verification, cathodic disbondment...edge retention. In addition, they incorporated cathodic disbondment tests used to verify the performance of pipeline coatings into the specification...pure electrodeposited aluminum—were identified as being suitable plating finishing options for replacing cadmium. DLA Land and Maritime added these

Transparency of Vocational Qualifications: The Leonardo da Vinci Approach. CEDEFOP Panorama Series.

Science.gov (United States)

Bjornavold, Jens; Pettersson, Sten

This report gives an overview of the situation of transparency of vocational qualifications by presenting measures introduced at the European Community level and by drawing attention to projects within the Leonardo da Vinci Program dealing with the issue. A 16-page executive summary appears first. Chapter 1 provides general background and aims.…

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)

Environmental qualification program for Krsko NPP

International Nuclear Information System (INIS)

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

1998-01-01

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

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

International Nuclear Information System (INIS)

Ng, Ching Hang; Chen, Pei-Ying

2009-01-01

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

IEEE C37.105-1987: IEEE standard for qualifying Class 1E protective relays and auxiliaries for nuclear power generating stations

International Nuclear Information System (INIS)

Anon.

1992-01-01

This standard describes the basic principles, requirements, and methods for qualifying Class 1E protective relays and auxiliaries such as test and control switches, terminal blocks, and indicating lamps for applications in nuclear power generating stations. When properly employed it can be used to demonstrate the design adequacy of such equipment under normal, abnormal, design basis event and post design basis event conditions in accordance with ANSI/IEEE Std 323-1983. When protective relays and auxiliaries are located in areas not subject to harsh environments, environmental qualification is not required. Protective relays and auxiliaries located inside primary containment in a nuclear power generating station present special conditions beyond the scope of this document. The qualification procedure presented is generic in nature. Other methods may be used at the discretion of the qualifier, provided the basic precepts of ANSI/IEEE Std 32301983 are satisfied

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

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.

77 FR 67340 - National Fire Codes: Request for Comments on NFPA's Codes and Standards

Science.gov (United States)

2012-11-09

... Water Mist Fire P Protection Systems. NFPA 921 Guide for Fire and Explosion P Investigations. NFPA 1005 Standard for Professional P Qualifications for Marine Fire Fighting for Land-Based Fire Fighters. NFPA 1192... DEPARTMENT OF COMMERCE National Institute of Standards and Technology National Fire Codes: Request...

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...

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

International Nuclear Information System (INIS)

1986-01-01

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

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.

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)

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...

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.

Present status of standards relating to radiation control and protection

International Nuclear Information System (INIS)

Minami, Kentaro

1996-01-01

Japanese and international standards related to radiation control and radiation protective management are presented focusing on the forming condition, significance, current situation, and their relationship. Japanese Industrial Standards (JIS) is quite useful in the field of atomic energy as well as other fields in terms of optimization and rationalization of the management. JIS includes JIS Z 4001 Atomic Energy Terminology which corresponds to internationl standards ISO 921 Nuclear Glossary, and JIS Z 4005 Medical Radiation Terminology, covering about 500 articles, which corresponds to IEC 788 Medical Radiology-Terminology. The first standards regarding radiation protection was established in X-ray Film Badge, which is included in the field of personal dosimeter, in 1956. Currently, 36 JIS has been established in the field of radiation management dosimeter and 3 are under arrangement. As for radiation protective supplies, 9 JIS has been established so far. Before proposal of JIS, investigation had been conducted to improve, simplify, and standardize the standards of radiation dosimetric technique, dosimeters, dosimetric procedures, and improvement. In this article, the results of material surface contamination monitoring and body surface monitoring conducted in Atomic Energy Safety Association and Radiation Dosimetry Associationare reported, and ISO and IEC are also treated. (S.Y.)

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…

The need to qualify Non Destructive Tests (NDT) has been recognized for many years in the European countries engaged in nuclear power generation

International Nuclear Information System (INIS)

Walczak, M.; Wojas, M.

2008-01-01

The European Network for Inspection Qualification, ENIQ, which groups the major part of the nuclear power plant operators in the European Union and in the Applicant Countries, has developed the European methodology for Qualification of Non Destructive Tests. As qualification of NDT is nowadays a standard method in the nuclear industry and in other industries. CEN (European Committee for Standardization) Technical Committee 138 '' Non Destructive Testing '' has established a Working Group, which is responsible for developing a Standard document detailing the CEN Methodology for the qualification of Non Destructive Tests applicable to all industries carrying out Non-Destructive Tests. This Standard document sets out basic principles and provides recommendations and general guidelines for carrying out qualification of NDT. It describes a methodology for qualification of Non-Destructive Tests, applicable to all NDT methods and considers qualification of equipment, procedure and personnel training. This paper presents a short background of the European Methodology for Qualification of Non-Destructive Tests and the Standard document CEN/TR 14748 '' Non-destructive testing - Methodology for qualification of non-destructive tests ''. (author)

The application of NISA II FEM package in seismic qualification of small class IE electric motors

International Nuclear Information System (INIS)

Fancev, T.; Saban, I.; Grgic, D.

1995-01-01

According to the IEEE standards 323/1974 and 344/1975, seismic qualification of class IE equipment is appropriate combination of test and analysis methods. Complex equipment and assemblies are usually tested through seismic testing. The analysis is recommended for simple equipment that can be easily modeled to correctly predict its response. This article deals with the application of NISA II FEM package in 3D FE modeling and mode shape calculations of small power low voltage electric motors. (author)

Review of seismic tests for qualification of components and validation of methods

International Nuclear Information System (INIS)

Buland, P.; Gantenbein, F.; Gibert, R.J.; Hoffmann, A.; Queval, J.C.

1988-01-01

Seismic tests are performed in CEA-DEMT since many years in order: to demonstrate the qualification of components, to give an experimental validation of calculation methods used for seismic design of components. The paper presents examples of these two types of tests, a description of the existing facilities and details about the new facility TAMARIS under construction. (author)

Review of seismic tests for qualification of components and validation of methods

Energy Technology Data Exchange (ETDEWEB)

Buland, P; Gantenbein, F; Gibert, R J; Hoffmann, A; Queval, J C [CEA-CEN SACLAY-DEMT, Gif sur Yvette-Cedex (France)

1988-07-01

Seismic tests are performed in CEA-DEMT since many years in order: to demonstrate the qualification of components, to give an experimental validation of calculation methods used for seismic design of components. The paper presents examples of these two types of tests, a description of the existing facilities and details about the new facility TAMARIS under construction. (author)

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

Qualification and testing of CT systems

DEFF Research Database (Denmark)

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

2018-01-01

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

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...

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

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 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

76 FR 51041 - Hemoglobin Standards and Maintaining Adequate Iron Stores in Blood Donors; Public Workshop

Science.gov (United States)

2011-08-17

...] Hemoglobin Standards and Maintaining Adequate Iron Stores in Blood Donors; Public Workshop AGENCY: Food and... Donors.'' The purpose of this public workshop is to discuss blood donor hemoglobin and hematocrit qualification standards in the United States, its impact on donor safety and blood availability, and potential...

Qualification of standard membrane-feeding assay with Plasmodium falciparum malaria and potential improvements for future assays.

Directory of Open Access Journals (Sweden)

Kazutoyo Miura

Full Text Available Vaccines that interrupt malaria transmission are of increasing interest and a robust functional assay to measure this activity would promote their development by providing a biologically relevant means of evaluating potential vaccine candidates. Therefore, we aimed to qualify the standard membrane-feeding assay (SMFA. The assay measures the transmission-blocking activity of antibodies by feeding cultured P. falciparum gametocytes to Anopheles mosquitoes in the presence of the test antibodies and measuring subsequent mosquito infection. The International Conference on Harmonisation (ICH Harmonised Tripartite Guideline Q2(R1 details characteristics considered in assay validation. Of these characteristics, we decided to qualify the SMFA for Precision, Linearity, Range and Specificity. The transmission-blocking 4B7 monoclonal antibody was tested over 6 feeding experiments at several concentrations to determine four suitable concentrations that were tested in triplicate in the qualification experiments (3 additional feeds to evaluate Precision, Linearity and Range. For Specificity, 4B7 was tested in the presence of normal mouse IgG. We determined intra- and inter-assay variability of % inhibition of mean oocyst intensity at each concentration of 4B7 (lower concentrations showed higher variability. We also showed that % inhibition was dependent on 4B7 concentration and the activity is specific to 4B7. Since obtaining empirical data is time-consuming, we generated a model using data from all 9 feeds and simulated the effects of different parameters on final readouts to improve the assay procedure and analytical methods for future studies. For example, we estimated the effect of number of mosquitoes dissected on variability of % inhibition, and simulated the relationship between % inhibition in oocyst intensity and % inhibition of prevalence of infected mosquitos at different mean oocysts in the control. SMFA is one of the few biological assays used in

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)

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.

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...

The development, qualification and availability of AECL analytical, scientific and design codes

International Nuclear Information System (INIS)

Kupferschmidt, W.C.H.; Fehrenbach, P.J.; Wolgemuth, G.A.; McDonald, B.H.; Snell, V.G.

2001-01-01

Over the past several years, AECL has embarked on a comprehensive program to develop, qualify and support its key safety and licensing codes, and to make executable versions of these codes available to the international nuclear community. To this end, we have instituted a company-wide Software Quality Assurance (SQA) Program for Analytical, Scientific and Design Computer Programs to ensure that the design, development, maintenance, modification, procurement and use of computer codes within AECL is consistent with today's quality assurance standards. In addition, we have established a comprehensive Code Validation Project (CVP) with the goal of qualifying AECL's 'front-line' safety and licensing codes by 2001 December. The outcome of this initiative will be qualified codes, which are properly verified and validated for the expected range of applications, with associated statements of accuracy and uncertainty for each application. The code qualification program, based on the CSA N286.7 standard, is intended to ensure (1) that errors are not introduced into safety analyses because of deficiencies in the software, (2) that an auditable documentation base is assembled that demonstrates to the regulator that the codes are of acceptable quality, and (3) that these codes are formally qualified for their intended applications. Because AECL and the Canadian nuclear utilities (i.e., Ontario Power Generation, Bruce Power, Hydro Quebec and New Brunswick Power) generally use the same safety and licensing codes, the nuclear industry in Canada has agreed to work cooperatively together towards the development, qualification and maintenance of a common set of analysis tools, referred to as the Industry Standard Toolset (IST). This paper provides an overview of the AECL Software Quality Assurance Program and the Code Validation Project, and their associated linkages to the Canadian nuclear community's Industry Standard Toolset initiative to cooperatively qualify and support commonly

Framework for a Comparative Accelerated Testing Standard for PV Modules: Preprint

Energy Technology Data Exchange (ETDEWEB)

Kurtz, S.; Wohlgemuth, J.; Yamamichi, M.; Sample, T.; Miller, D.; Meakin, D.; Monokroussos, C.; TamizhMani, M.; Kempe, M.; Jordan, D.; Bosco, N.; Hacke, P.; Bermudez, V.; Kondo, M.

2013-08-01

As the photovoltaic industry has grown, the interest in comparative accelerated testing has also grown. Private test labs offer testing services that apply greater stress than the standard qualification tests as tools for differentiating products and for gaining increased confidence in long-term PV investments. While the value of a single international standard for comparative accelerated testing is widely acknowledged, the development of a consensus is difficult. This paper strives to identify a technical basis for a comparative standard.

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

Cement waste form qualification report: WVDP [West Valley Demonstration Project] PUREX decontaminated supernatant

International Nuclear Information System (INIS)

McVay, C.W.; Stimmel, J.R.; Marchetti, S.

1988-08-01

This report provides a summary of work performed to develop a cement-based, low-level waste formulation suitable for the solidification of decontaminated high-level waste liquid produced as a by-product of PUREX spent fuel reprocessing. The resultant waste form is suitable for interim storage and is intended for ultimate disposal as low-level Class C waste; it also meets the stability requirements of the NRC Branch Technical Position on Waste Form Qualification, May 1983 and the requirements of 10 CFR 61. A recipe was developed utilizing only Portland Type I cement based on an inorganic salts simulant of the PUREX supernatant. The qualified recipe was tested full scale in the production facility and was observed to produce a product with entrained air, low density, and lower-than-expected compressive strength. Further laboratory scale testing with actual decontaminated supernatant revealed that set retarders were present in the supernatant, precluding setting of the product and allowing the production of ''bleed water.'' Calcium nitrate and sodium silicate were added to overcome the set retarding effect and produced a final product with improved performance when compared to the original formulation. This report describes the qualification process and qualification test results for the final product formulation. 7 refs., 38 figs., 21 tabs

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.

Determination of the approximate number of welding qualification procedures, according to the AD-HP 2/1 and NUCLEN rules

International Nuclear Information System (INIS)

Couto, J.G.V.

1986-01-01

The simple equations based on the phylosophy of AD-HP 2/1 which determine the approximate number welding qualification procedures for the manufacture either of one component, or several components requested simultaneously are presented. It is also intended to help the manufacturer in the rational preparation of scheduling the required minimum qualifications for performing the work, including giving him an idea about the involved costs which the firm will have to bear in this phase prior to manufacturing. (Author) [pt

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

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

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

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.

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

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.

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)

Do Qualification, Experience and Age Matter for Principals Leadership Styles?

OpenAIRE

Muhammad Javed Sawati; Saeed Anwar; Muhammad Iqbal Majoka

2013-01-01

The main focus of present study was to find out the prevalent leadership styles of principals in government schools of Khyber Pakhtunkhwa and to find relationship of leadership styles with qualifications, age and experience of the principals. On the basis of analyzed data, four major leadership styles of the principals were identified as Eclectic, Democratic, Autocratic, and Free-rein. However, a small proportion of the principal had no dominant leadership style. This study shows that princip...

Governmental entities accounting: domestic standards and foreign experience of preparation and presentation

Directory of Open Access Journals (Sweden)

Ambarchian V.S.

2015-12-01

Full Text Available The purpose of research refers to comparison of Ukrainian and the USA standards of preparation and presentation of governmental entities financial reports with the aim of implementation of foreign experience regarding financial data disclosure of a governmental entity activity in domestic reporting system of budgetary resources disposers. In order to achieve the aim the author applied the following general methods of cognition: induction, deduction, analogy, comparison, and historical one. Special economic methods include grouping, tabular, graphical, information and logical analysis. The research resulted in detailed analysis of the standards of the USA governmental entities financial reports presentation and comparison of their statements with domestic governmental accounting standards. As a result of performed research, the key differences in the Ukrainian and the USA rules of presentation of governmental entities financial reports are considered. The author determined the dependence of structure and a public level of the financial reports on the character of the state political and economic systems.

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

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

CST receiver tube qualification, Phase 1, Investigation - Final Report

Energy Technology Data Exchange (ETDEWEB)

Mack, I.; Rossy, J.-P.

2010-05-15

In this report the different application possibilities for concentrated solar thermal (CST) systems are studied. Further, the possible measuring methods for characterising and qualifying the receivers with their embedded absorber tubes are investigated. The investigations show that CST systems can be used as an environmentally friendly alternative to fossil fuels in many applications. The best known one is the generation of electrical power, but concentrated solar energy can also be used for desalination, industrial process heat, and for cooling of buildings. Industrial process heat is a large potential area with temperature in the range of 120 {sup o}C to over 400 {sup o}C. Heat below 400 {sup o}C can be provided by various parabolic trough and Fresnel systems, which are optimised for the temperature required. In order to further increase the usage of CST systems, it is of great importance to provide standards for the qualification and characterisation of the different components of the CST systems. Huge efforts are currently made to define a standard for evacuated receiver tubes. For the characterisation of the black absorber tubes the development is still at the beginning, although the need here is also given. (authors)

Qualification of an Agilent Technologies 7890A gas chromatograph used in the biotechnology industry

International Nuclear Information System (INIS)

Alvarez Gonzalez, Alberto; Tambara Hernandez, Yanet; Alvarez Gil, Felix

2014-01-01

The drug manufacture is governed by strict international standards that guarantee reproducibility and consistency of results. The qualification of the instruments used in the productive processes, as well as in the characterization of products and their quality control are prerequisites to the validation of any analytical technique using them. One of the instrumental techniques used in the biotechnical industry is Gas Chromatography. A standard of pure caffeine was used for analysis in addition to a HP-5 30 m x 0,32 mm d.i. and 0,33 μm thick film column was used in a Gas Chromatograph coupled with a Flame Ionization Detector. For the testing of the different modules involved in the analysis (injector, column, oven and detector), an experimental design was made to estimate several parameters

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...

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..

"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…

Development and introduction of a modular training and qualification concept for maintenance personnel

International Nuclear Information System (INIS)

Kumpf, Thomas; Mueller, Nina; Hofbauer, Detlef

2009-01-01

The presentation entitled ''Development and Introduction of a Modular Training and Qualification Concept for Maintenance Personnel'' presents the background, concept and training modules of a reactor services training concept that was jointly elaborated by a working group consisting of the ''Maintenance manager workshop'' working panel of the VGB, the Kraftwerksschule (KWS) PowerTech Training Center, and AREVA NP GmbH in Erlangen and Offenbach. This concept is part of AREVA's comprehensive training and qualification approach which comprises inter alia extensive introduction sessions for new employees, the corporation-wide highly appreciated AREVA University as well as specialized training facilities as for example the CETIC in Chalon-sur-Saone, France and the training center in Lynchburg, USA, or the worldwide largest integration center for digital I and C equipment for safety applications in nuclear power plants in Erlangen. AREVA NP's training concept for maintenance personnel addresses not only employees from AREVA NP working in nuclear maintenance but also personnel from nuclear power plants as well as independent experts, representatives from authorities and other interest groups. (orig.)