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.

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.

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

Non-destructive qualification tests for ITER cryogenic axial insulating breaks

International Nuclear Information System (INIS)

Kosek, Jacek; Lopez, Roberto; Tommasini, Davide; Rodriguez-Mateos, Felix

2014-01-01

In the ITER superconducting magnets the dielectric separation between the CICC (Cable-In-Conduit Conductors) and the helium supply pipes is made through the so-called insulating breaks (IB). These devices shall provide the required dielectric insulation at a 30 kV level under different types of stresses and constraints: thermal, mechanical, dielectric and ionizing radiations. As part of the R and D program, the ITER Organization launched contracts with industrial companies aimed at the qualification of the manufacturing techniques. After reviewing the main functional aspects, this paper describes and discusses the protocol established for non-destructive qualification tests of the prototypes

Non-destructive qualification tests for ITER cryogenic axial insulating breaks

Energy Technology Data Exchange (ETDEWEB)

Kosek, Jacek [Wroclaw University of Technology, Wybrzeze Wyspianskiego 27, 50-370 Wroclaw, Poland and CERN, Geneva 23,CH-1211 (Switzerland); Lopez, Roberto; Tommasini, Davide [CERN, Geneva 23,CH-1211 (Switzerland); Rodriguez-Mateos, Felix [CERN, Geneva 23,CH-1211, Switzerland and ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul lez Durance (France)

2014-01-29

In the ITER superconducting magnets the dielectric separation between the CICC (Cable-In-Conduit Conductors) and the helium supply pipes is made through the so-called insulating breaks (IB). These devices shall provide the required dielectric insulation at a 30 kV level under different types of stresses and constraints: thermal, mechanical, dielectric and ionizing radiations. As part of the R and D program, the ITER Organization launched contracts with industrial companies aimed at the qualification of the manufacturing techniques. After reviewing the main functional aspects, this paper describes and discusses the protocol established for non-destructive qualification tests of the prototypes.

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

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)

Evaluation of the qualification of SPERT [Special Power Excursion Reactor Test] fuel for use in non-power reactors

International Nuclear Information System (INIS)

1987-08-01

This report summarizes the US Nuclear Regulatory Commission staff's evaluation of the qualification of the stainless-steel-clad uranium/oxide (UO 2 ) fuel pins for use in non-power reactors. The fuel pins were originally procured in the 1960's as part of the Special Power Excursion Reactor Test (SPERT) program. Argonne National Laboratory (ANL) examined 600 SPERT fuel pins to verify that the pins were produced according to specification and to assess their present condition. The pins were visually inspected under 6X magnification and by X-radiographic, destructive, and metallographic examinations. Spectrographic and chemical analyses were performed on the UO 2 fuel. The results of the qualification examinations indicated that the SPERT fuel pins meet the requirements of Phillips Specification No. F-1-SPT and have suffered no physical damage since fabrication. Therefore, the qualification results give reasonable assurance that the SPERT fuel rods are suitable for use in non-power reactors provided that the effects of thin-wall defects in the region of the upper end cap and low-density fuel pellets are evaluated for the intended operating conditions. 1 ref., 4 figs., 11 tabs

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

International Nuclear Information System (INIS)

Anon.

1992-01-01

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

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

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

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

The utilization of VUJE specialists non-destructive testing qualification at international cooperation with company TECNATOM

International Nuclear Information System (INIS)

Kuna, M.

2006-01-01

The utilization of VUJE specialists non-destructive testing qualification at cooperation with company TECNATOM. The obtain of QDA qualification for ET examination for possibility of qualified evaluation in the foreign NPP (USA, Brazil). The acquired practical experiences by evaluation of ET data from NPP Angra Brazil and Waltz Mill USA. The obtain of SNT-TC-1A and EPRI qualification for the UT evaluation of penetration tube welds measurements. The practical experience during the measurement on NPP Shearon Harris (Author)

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

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)

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.)

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)

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

Qualification of nuclear power plant inspection, examination, and testing personnel. Revision 1, September 1980

International Nuclear Information System (INIS)

Anon.

1981-01-01

Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants, to 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities, requires that the quality assurance program provide for indoctrination and training of personnel performing activities affecting quality as necessary to ensure that quality assurance personnel achieve and maintain suitable proficiency. This guide describes a method acceptable to the NRC staff for complying with the Commission's regulations with regard to qualification of inspection, examination, and testing personnel for all types of nuclear power plants

Qualification test of chemical cleaning for secondary side of steam generator in Qinshan Nuclear Power Plant

International Nuclear Information System (INIS)

Zhang Mengqin; Zhang Shufeng; Yu Jinghua; Hou Shufeng

1997-07-01

The chemical cleaning technique for removing sludge on the secondary side in Qinshan Nuclear Power Plant has been qualified. The chemical cleaning process will carry out during shutdown refuelling. The qualification test has studied the effect of chemical cleaning agent component, cleaning time on dissolution effectiveness of sludge (Fe 3 O 4 ) and to evaluate corrosion situation of main materials of SG in the cleaning process. The main component of cleaning agent is EDTA. The cleaning temperature is 20∼30 degree C. It is determined that allowable remains amount of cleaning agent (EDTA). The technique of cleaning, rinse, passivation for the chemical cleaning in Qinshan Nuclear Power Plant has been made. The qualification test shown that the technique can dissolve Fe 3 O 4 >1 g/L, the corrosion of materials is in allowable value, the allowable remains of EDTA is <0.01%. The technique character is static, ambient temperature. (9 refs., 12 tabs.)

Asia nuclear-test-ban network for nuclear non-proliferation

International Nuclear Information System (INIS)

Shinohara, Nobuo; Kokaji, Lisa; Ichimasa, Sukeyuki

2010-01-01

In Global Center of Excellence Program of The University of Tokyo, Non- Proliferation Study Committee by the members of nuclear industries, electricity utilities, nuclear energy institutes and universities has initiated on October 2008 from the viewpoints of investigating a package of measures for nuclear non-proliferation and bringing up young people who will support the near-future nuclear energy system. One of the non-proliferation issues in the Committee is the Comprehensive Nuclear-Test-Ban Treaty (CTBT). Objective of this treaty is to cease all nuclear weapon test explosions and all other nuclear explosion. This purpose should be contributed effectively to the political stability of the Asian region by continuous efforts to eliminate the nuclear weapons. In the Committee, by extracting several issues related to the CTBT, conception of 'Asia nuclear-test-ban network for nuclear non-proliferation' has been discussed with the aim of the nuclear-weapon security in Asian region, where environmental nuclear-test monitoring data is mainly treated and utilized. In this paper, the conception of the 'network' is presented in detail. (author)

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)

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

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

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)

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.

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

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

International Nuclear Information System (INIS)

Skanberg, Lars

2005-01-01

presented at the Workshop have been published in the proceedings referenced NEA/CSNI/R(2004)9. The two reports along with the NRWG-report EUR 21320 are the main source of information for this Status Report on Developments and Cooperation on Risk-Informed In-Service-Inspection and Non-Destructive Testing (NDT) Qualification in OECD-NEA member countries. The report is organized in the following way: introduction to early ISI strategies and Augmented ISI and NDT Qualification; Risk-Informed In-Service Inspection (RI-ISI): Development of RI-ISI strategies, RI-ISI Regulatory guidance, Important aspects of RI-ISI, Overview of RI-ISI methods, Comparison of methods, Overview of RI-ISI applications and pilot studies, RI-ISI experience so far, Further evaluations and developments of RI-ISI methodologies; Non-Destructive Testing (NDT) Qualification: Development of NDT qualification strategies, NDT-qualification requirements and applications, NDT-qualification experience. Conclusions and recommendations are then given

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

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

International Nuclear Information System (INIS)

Elfving, K.

1998-11-01

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

Qualification 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

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)

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

Applicability of qualification testing of electric cable to life extension

International Nuclear Information System (INIS)

Reynolds, A.B.

1988-01-01

The methods for qualification testing of electric cable for nuclear power plants followed by U.S. cable manufacturers and endorsed by the U.S. Nuclear Regulatory Commission (NRC) involve irradiation aging at high dose rates at room temperature and accident aging in steam without the pressure of air. Testing is done sequentially. The research data which led to some concerns have been reviewed, and some conclusions regarding these concerns are suggested

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

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.

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

International Nuclear Information System (INIS)

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

1992-12-01

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

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).

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 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.)

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

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

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.

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)

Qualification tests for a dosimetry system

International Nuclear Information System (INIS)

Anon.

2005-01-01

The report of qualification tests for personnel dosemeters is detailed. Qualification test for the energy response and the incidence angle is given. The procedure of test is resumed. Different coefficients of conversion used in these tests are given in tables. (N.C.)

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

International Nuclear Information System (INIS)

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

2013-01-01

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

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

Science.gov (United States)

2010-01-01

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

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

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

Qualification of NDE personnel in the nuclear industry

International Nuclear Information System (INIS)

Epps, T.N.

1984-01-01

There has been evidence of ineffective programs for certifying nondestructive examination (NDE) personnel who conduct periodic inservice examinations in nuclear power plants under ASME Section XI Code requirements. This was brought to the attention of a group from the electric utility industry, the Electric Power Research Institute (EPRI), some NDE consultants and representatives from the American Society of Mechanical Engineers (ASME) by the Nuclear Regulatory Commission (NRC) in a May, 1982 meeting in Bethesda, Maryland. One problem pointed out by the NRC was the lack of a clear definition of qualification requirements for certification of NDE personnel who conduct ASME Section XI Inservice Inspection work in nuclear power plants. The NRC requested that the nuclear industry resolve this problem by formulating definitive qualification requirements for personnel certification that could be made an industry requirement. In June, 1982 the EPRI NDE Subcommittee held a general meeting for utility representatives to discuss the results of the May, 1982 meeting to develop a plan for industry response to the issue. The consensus was that an Ad Hoc Committee of utility representatives be convened to develop a document outlining qualification requirements for vertification of NDE personnel. The Ad Hoc Committee was formally convened on September 29, 1982

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

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

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

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

International Nuclear Information System (INIS)

Wojas, M.; Walczak, M.

2006-01-01

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

Radiation hardness and qualification of semiconductor electronic devices for nuclear reactors

International Nuclear Information System (INIS)

Friant, A.; Payat, R.

1984-05-01

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

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

International Nuclear Information System (INIS)

1998-03-01

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

ENEA activities on seismic isolation of nuclear and non-nuclear structures

International Nuclear Information System (INIS)

Martelli, A.; Masoni, P.; Forni, M.; Indirli, M.; Spadoni, B.; Di Pasquale, G.; Lucarelli, V.; Sano, T.; Bonacina, G.; Castoldi, A.

1989-01-01

Work on seismic isolation of nuclear and non-nuclear structures was started by ENEA in cooperation with ISMES in 1988. The first activity consisted of a proposal for guidelines for seismically isolated nuclear plants using high-damping, steel-laminated elastomer bearings. This is being performed in the framework of an agreement with General Electric Company. Furthermore, research and development work has been defined and recently initiated to support development of the seismic isolation guidelines as well as that of qualification procedures for seismic isolation systems in general. The present R and D work includes static and dynamic experiments on single bearings, shake table tests with multi-axial simultaneous excitations on reduced-scale mockups of isolated structures supported by multiple bearings, and dynamic tests on large-scale isolated structures with on-site test techniques. It also includes the development and validation of finite-element nonlinear models of the single bearings, as well as those of simplified design tools for the analysis of the isolated structures dynamic behavior. Extension of this work is foreseen in a wider national frame

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

International Nuclear Information System (INIS)

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

1983-09-01

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

On-site tests on the nuclear power plants

International Nuclear Information System (INIS)

Morilhat, P.; Favennec, J.M.; Neau, P.; Preudhomme, E.

1996-01-01

On-site tests and experiments are performed by EDF Research and Development Division on the nuclear power plants to assess the behaviour of major components submitted to thermal and vibratory solicitations. On-going studies deal with the qualification of new nuclear power plant standard and with the feedback of plants under operation. The tests, particularly the investigation tests, correspond to large investments and entail an important data volume which must ensure the continuity over a long period of the order of magnitude of the in-service plant life (around 40 years). This paper addresses the on-site experimental activities, describes the means to be used, and gives an example: the qualification of SG of new 1450 MW nuclear power plants. (author)

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.)

IEEE Std 382-1985: IEEE standard for qualification of actuators for power operated valve assemblies with safety-related functions for nuclear power plants

International Nuclear Information System (INIS)

Anon.

1992-01-01

This standard describes the qualification of all types of power-driven valve actuators, including damper actuators, for safety-related functions in nuclear power generating stations. This standard may also be used to separately qualify actuator components. This standard establishes the minimum requirements for, and guidance regarding, the methods and procedures for qualification of power-driven valve actuators with safety-related functions Part I describes the qualification process. Part II describes the standard qualification cases and their environmental parameters for the usual locations of safety-related equipment in a nuclear generating station. Part III describes the qualification tests outlined in 6.3.3

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

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.)

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

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

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

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

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

International Nuclear Information System (INIS)

Oehmigen, Steffen; Ambos, Frank

2013-01-01

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

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

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

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

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

International Nuclear Information System (INIS)

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

1986-10-01

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

Seismic qualification testing at the National Engineering Laboratory

International Nuclear Information System (INIS)

Fairbairn, J.

1984-01-01

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

A qualification test for relay contacts as isolation devices in nuclear power plants

International Nuclear Information System (INIS)

Beck, C.E.; Behera, A.K.; Polanco, S.; Terry, B.

1995-01-01

A methodology is introduced for testing the integrity of relay contacts as isolation devices in Class IE circuits. A design activity that installed a new relay established the need for a new type of qualification test. This paper descries the process of establishing the test methodology, the development of the test plan, and the results of testing. It also describes the limitations of applying the results of any specific test to actual field installations, and offers other potential uses of the methodology

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 Standard for qualification of Class 1E lead storage batteries for nuclear power generating stations

International Nuclear Information System (INIS)

Anon.

1980-01-01

This document describes qualification methods for Class 1E lead storage batteries and racks to be used in nuclear power generating stations outside of primary containment. Qualification required in ANSI/IEEE Std 279-1979 and IEEE Std 308-1978, can be demonstrated by using the procedures provided in this Standard in accordance with IEEE Std 323-1974. Battery sizing, maintenance, capacity testing, installation, charging equipment and consideration of other types batteries are beyond the scope of this Standard

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

Energy Technology Data Exchange (ETDEWEB)

Elfving, K

1998-11-01

The goal of this study is to determine the requirements of the in-service inspection qualification in Europe, their feasibility in practice and to find out possible manufacture defects in test pieces used in practical trials. The literature study consists of qualification requirements set by European regulatory bodies and by the European nuclear power utilities. Also a brief summary of qualification requirements set by ASME Code, Section XI and comparison between ASME and European qualification requirements is included 24 refs.

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

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

Affordable Development and Qualification Strategy for Nuclear Thermal Propulsion

Science.gov (United States)

Gerrish, Harold P., Jr.; Doughty, Glen E.; Bhattacharyya, Samit K.

2013-01-01

Nuclear Thermal Propulsion (NTP) is a concept which uses a nuclear reactor to heat a propellant to high temperatures without combustion and can achieve significantly greater specific impulse than chemical engines. NTP has been considered many times for human and cargo missions beyond low earth orbit. A lot of development and technical maturation of NTP components took place during the Rover/NERVA program of the 60's and early 70's. Other NTP programs and studies followed attempting to further mature the NTP concept and identify a champion customer willing to devote the funds and support the development schedule to a demonstration mission. Budgetary constraints require the use of an affordable development and qualification strategy that takes into account all the previous work performed on NTP to construct an existing database, and include lessons learned and past guidelines followed. Current guidelines and standards NASA uses for human rating chemical rocket engines is referenced. The long lead items for NTP development involve the fuel elements of the reactor and ground testing the engine system, subsystem, and components. Other considerations which greatly impact the development plans includes the National Space Policy, National Environmental Policy Act, Presidential Directive/National Security Council Memorandum #25 (Scientific or Technological Experiments with Possible Large-Scale Adverse Environmental Effects and Launch of Nuclear Systems into Space), and Safeguards and Security. Ground testing will utilize non-nuclear test capabilities to help down select components and subsystems before testing in a nuclear environment to save time and cost. Existing test facilities with minor modifications will be considered to the maximum extent practical. New facilities will be designed to meet minimum requirements. Engine and test facility requirements are based on the driving mission requirements with added factors of safety for better assurance and reliability

The french safety approach regarding equipment qualification

International Nuclear Information System (INIS)

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

1989-10-01

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

Qualification 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)

Review of international developments and cooperation on Risk-Informed In-Service-Inspection (RI-ISI) and Non-destructive Testing (NDT) Qualification in OECD-NEA member countries- Responses to the questionnaire - CSNI/integrity and ageing working group

International Nuclear Information System (INIS)

2005-01-01

In December 2000, the Committee on Nuclear Regulatory Activities (CNRA) and the Committee on the Safety of Nuclear Installations (CSNI) agreed to prepare a state-of-the art report addressing the present situation and regulatory aspects in NEA member countries on: - Risk based / risk informed in-service inspections (ISI) developments, - Qualification of NDT system to be used for the inspections. The CSNI gave mandate to the CSNI working group on the Integrity of Components and Structures (IAGE) to prepare the report. In order to get a good basis for compiling the report with an overview on the present situation in OECD countries and regulatory aspects on the further developments of RI-ISI and NDT qualification approaches a questionnaire was prepared. This questionnaire was organised in two parts. The first part addressed used risk based / risk informed ISI approaches and regulatory aspects on the further developments. The second part addressed used NDT qualification approaches and other measures for getting reliable inspection results as well as regulatory aspects on the further developments of qualification approaches. Some parts of the questionnaire addressed topics, which have been dealt with in other European or national programs. Available relevant information from these programs has been also collected. The questionnaire was circulated in 2003 among NEA member countries organisations. Appendix 1 contains the questionnaire. Appendix 2 contains the compilation of responses to the questionnaire. A workshop was organized to complement the questionnaire (NEA/CSNI/R(2004)9 Proceedings of the CSNI Workshop on 'International developments and cooperation on Risk-Informed In-Service- Inspection (RI-ISI) and Non-destructive Testing (NDT) Qualification' held in Stockholm, Sweden on 13-14 April 2004 and hosted by SKI). In addition to regulators, licensees, manufacturers and researchers, this workshop gathered international organisations (i.e. EC, IAEA) and the main

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

Energy Technology Data Exchange (ETDEWEB)

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

2016-11-01

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

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

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.)

Seismic qualification of nuclear control board by using base isolation technique

International Nuclear Information System (INIS)

Koizumi, T.; Tsujiuchi, N.; Fujita, T.

1987-01-01

The purpose is to adopt base isolation technique as a new approach for seismic qualification of nuclear control board. Basic concept of base isolation technique is expressed. Two dimensional linear motion mechanism with pre-tensioned coil springs and some dampers are included in the isolation device. Control board is regarded as a lamped mass system with inertia moment. Fundamental movement of this device and control board is calculated as a non-linear response problems. Fundamental analysis and numerical estimation, experimental investigation has been undertaken using an actual size control board. Sufficient agreement was recognized between experimental results and numerical estimation. (orig./HP)

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

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)

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

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

Directory of Open Access Journals (Sweden)

Abd. Rashid Noor Asidah

2017-01-01

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

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)

Safety analyses for an in-pile SCWR fuel qualification test loop

Energy Technology Data Exchange (ETDEWEB)

Schulenberg, T.; Raque, M. [Karlsruhe Inst. of Tech., Karlsruhe (Germany)

2014-07-01

As a nuclear facility cooled with supercritical water has never been built nor operated in the past, the planned SCWR fuel qualification test will give the first experience with supercritical water-cooled nuclear systems in general. With a fuel inventory of almost 1 kg of UO{sub 2} with almost 20% enrichment, the supercritical pressure test section inside a low pressure, pool type research reactor needs to be cooled properly even in case of a number of postulated design basis accidents. Depressurization systems and emergency cooling systems will need to be designed with similar reliability as for a prototype reactor to ensure the integrity of barriers retaining the radioactive material. The paper reports about the safety concept and summarizes the safety analyses which have been performed in this context. (author)

Training and qualification of nuclear power plant operators (4)

International Nuclear Information System (INIS)

Ohsuga, Y.

2009-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2016-11-01

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

Qualification by analogy of the functional valving of French pressurized water nuclear power stations

International Nuclear Information System (INIS)

Grenet, M.

1991-01-01

In certain postulated accidental conditions (loss of coolant accident or secondary pipe rupture, earthquake, high energy pipe rupture) plant valving is called on the important functions to bring the reactor to and maintain it at a safe shutdown condition. ELWCTRICITE DE FRANCE has completed qualification tests of about forty valves to assure their operability. However, taking into account the costs and time required to obtain this qualification and the number of valves to be qualified, this method alone is not sufficient. For this reason, Electricite de France has developed the alternative qualification methodology by analogy for each postulated accidental situation. Feedback experience of these methods today is such that it can be they have achieved their objective; namely, to improve the safety of French pressurized water nuclear power stations, while at the same time avoiding the two dangers represented by excessive complexity resulting in unsatisfactory operation, and insufficient thoroughness not providing any real increase in safety. (author)

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

International Nuclear Information System (INIS)

LaSalle, F.R.

1991-01-01

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

Environmental qualification testing of TFE valve components

International Nuclear Information System (INIS)

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

1997-01-01

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

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

The Nuclear Non-Proliferation Treaty and the Comprehensive Nuclear-Test-Ban Treaty, the relationship

Energy Technology Data Exchange (ETDEWEB)

Graham, Thomas Jr. [7609 Glenbrook Rd., Bethesda, MD 20814 (United States)

2014-05-09

The Nuclear Non-Proliferation Treaty (NPT) is the most important international security arrangement that we have that is protecting the world community and this has been true for many years. But it did not happen by accident, it is a strategic bargain in which 184 states gave up the right forever to acquire the most powerful weapon ever created in exchange for a commitment from the five states allowed to keep nuclear weapons under the NPT (U.S., U.K., Russia, France and China), to share peaceful nuclear technology and to engage in disarmament negotiations aimed at the ultimate elimination of their nuclear stockpiles. The most important part of this is the comprehensive nuclear test ban (CTBT); the thinking by the 184 NPT non-nuclear weapon states was and is that they understand that the elimination of nuclear weapon stockpiles is a long way off, but at least the NPT nuclear weapon states could stop testing the weapons. The CTBT has been ratified by 161 states but by its terms it can only come into force if 44 nuclear potential states ratify; 36 have of the 44 have ratified it, the remaining eight include the United States and seven others, most of whom are in effect waiting for the United States. No state has tested a nuclear weapon-except for complete outlier North Korea-in 15 years. There appears to be no chance that the U.S. Senate will approve the CTBT for ratification in the foreseeable future, but the NPT may not survive without it. Perhaps it is time to consider an interim measure, for the UN Security Council to declare that any future nuclear weapon test any time, anywhere is a 'threat to peace and security', in effect a violation of international law, which in today's world it clearly would be.

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

THYC qualification on Vatican-1 low pressure tests

International Nuclear Information System (INIS)

Duval, C.; Guichard, J.

1991-06-01

PWR cores or fuel assemblies are components of a nuclear power plant involving single and two-phase flows in rod bundles. The knowledge of the detailed two-phase and three-dimensional flow patterns is necessary to evaluate the singularity (grids) and bypass effects on the Departure from Nucleate Boiling (DNB) in reactor cores during incidental transients. For that purpose, since 1989, the VATICAN experiment has been performed at EDF as a part of the qualification program of the three-dimensional computer code THYC, developed by EDF. The qualification strategy of the THYC software for PWR cores is the following: assuming the theoretical or experimental knowledge of regular and singular pressure drops and grid turbulence sources in single-phase, pressure drop multipliers and relative velocity in two-phase flow, the VATICAN experiment allows to evaluate the diffusion phenomena in two-phase flow. It provides thermalhydraulic measurements on a mock-up of a part of 900 MWe PWR fuel assembly in single and two-phase flows, with power and quality gradients. The first configuration of the mock-up, with simple spacer grids, is studied (VATICAN-1). The specific effects of mixing spacer grids will be compared to these data through a second configuration. The last void fraction measurements, using a γ-ray technique, performed on VATICAN-1 low pressure tests allowed to qualify a set of closure relations, particularly a model of little two-phase diffusion, adapted to two-phase flows at low pressure (5.0MPa). The qualification of subcooled boiling and diffusion models will continue on next VATICAN and other experimental campaigns [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

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

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

Procedure of qualification applied to motors driving auxiliaries in fossil fired and nuclear power plants

International Nuclear Information System (INIS)

Coperchini, C.; Fises, A.

1984-01-01

Twenty year operation have enabled EDF to better understand the factors improving the reliability of powerhouse auxiliary drive induction motors. Progress in the behaviour of such machines are mainly due to analysis and handling of full size test results achieved in the Saint-Denis Motor Test Laboratory. This work led to the printing of recommendations and technical specifications. Service and safety requirements of the nuclear plant new generation lead to examine again the procedures of qualification. The analysis made in this report let appear the justification to maintain the present EDF policy with some necessary adjustments, especially as far as the nuclear safety motors are concerned [fr

Dynamic testing and qualification

International Nuclear Information System (INIS)

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

1990-01-01

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

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

IAEA activities in nuclear power plant personnel training and qualification

International Nuclear Information System (INIS)

Mautner-Markhof, F.

1993-01-01

Training to achieve and maintain the qualification and competence of nuclear power personnel is essential for safe and economic nuclear power. Technical Cooperation Meeting on Training-Related Activities for Nuclear Power Plant (NPP) Personnel in the countries of Central and Eastern Europe (CEEC) and of the former Soviet Union (FSU) has as its main objective the identification, through information exchange and discussion, of possible Technical Cooperation (TC) projects to assist Member States in meeting NPP personnel training needs and priorities, including the enhancing of training capabilities

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

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)

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

International Nuclear Information System (INIS)

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

1984-08-01

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

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

International Nuclear Information System (INIS)

Anon.

1980-01-01

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

Non Nuclear Testing of Reactor Systems In The Early Flight Fission Test Facilities (EFF-TF)

International Nuclear Information System (INIS)

Van Dyke, Melissa; Martin, James

2004-01-01

The Early Flight Fission-Test Facility (EFF-TF) can assist in the design and development of systems through highly effective non-nuclear testing of nuclear systems when technical issues associated with near-term space fission systems are 'non-nuclear' in nature (e.g. system's nuclear operations are understood). For many systems, thermal simulators can be used to closely mimic fission heat deposition. Axial power profile, radial power profile, and fuel pin thermal conductivity can be matched. In addition to component and subsystem testing, operational and lifetime issues associated with the steady state and transient performance of the integrated reactor module can be investigated. Instrumentation at the EFF-TF allows accurate measurement of temperature, pressure, strain, and bulk core deformation (useful for accurately simulating nuclear behavior). Ongoing research at the EFF-TF is geared towards facilitating research, development, system integration, and system utilization via cooperative efforts with DOE laboratories, industry, universities, and other Nasa centers. This paper describes the current efforts for the latter portion of 2003 and beginning of 2004. (authors)

Qualification test of a main coolant pump for SMART pilot

International Nuclear Information System (INIS)

Park, Sang Jin; Yoon, Eui Soo; Oh, Hyong Woo

2006-01-01

SMART Pilot is a multipurpose small capacity integral type reactor. Main Coolant Pump (MCP) of SMART Pilot is a canned-motor-type axial pump to circulate the primary coolant between nuclear fuel and steam generator in the primary system. The reactor is designed to operate under condition of 310 .deg. C and 14.7 MPa. Thus MCP has to be tested under same operating condition as reactor design condition to verify its performance and safety. In present work, a test apparatus to simulate real operating situations of the reactor has been designed and constructed to test MCP. And then functional tests, performance tests, and endurance tests have been carried out upon a prototype MCP. Canned motor characteristics, homologous head/torque curves, coast-down curves, NPSH curves and life-time performance variations were obtained from the qualification test as well as hydraulic performance characteristics of MCP

Decant pump assembly and controls qualification testing - test report

Energy Technology Data Exchange (ETDEWEB)

Staehr, T.W., Westinghouse Hanford

1996-05-02

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

Training and qualification of nuclear power plant operators

International Nuclear Information System (INIS)

Ohsuga, Y.

2008-01-01

Based on training experiences of the nuclear power plant operators of pressurized water reactors (PWR) at the Nuclear Power Training Center Ltd. (NTC) in Japan, training programs were reviewed referring to US training programs. A systematic approach is deployed to them, which mainly consist of on-the-job training and the NTC training courses to meet the needs of all operators from beginners to experienced veterans according to their experiences and objectives. The NTC training is conducted using the simulators that simulate the nuclear power plant dynamics through the use of computers. The operators trained at the NTC work in the central control room of every PWR power plant. The NTC also carries out the qualification examinations for the shift managers. (T. Tanaka)

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

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

Current developments in mechanized non-destructive testing in nuclear power plants

International Nuclear Information System (INIS)

Zeilinger, R.

2008-01-01

Nuclear power plants require frequent in-service activities to be carried out conscientiously in areas potentially hazardous to human operators (because of the associated radiation exposure), such as non-destructive testing of pressurized components of the steam system. Locations to be inspected in this way include the reactor pressure vessel, core internals, steam generators, pressurizers, and pipes. The codes to be used as a basis of these inspections demand high absolute positioning and repeating accuracy. These requirements can be met by mechanized test procedures. Accordingly, many new applications of, mostly mobile, robots have been developed over the past few years. The innovative control and sensor systems for stationary and mobile robots now on the market offer a potential for economic application in a large number of new areas in inspection, maintenance and service in nuclear power plants. More progress in this area is expected for the near future. Areva NP founded the new NDT Center, NETEC (Non-destructive Examination Technical Center), as a global technical center for non-destructive materials testing. NETEC is to advance research and development of all basic NDT technologies, robotics included. For many years, intelligeNDT has offered solutions and products for a variety of inspection and testing purposes and locations in nuclear power plants and is involved in continuous further development of the experience collected in nuclear power plants on the spot. (orig.)

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

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)

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)

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...

Qualifications and training of staff of the regulatory body for nuclear power plants

International Nuclear Information System (INIS)

1979-01-01

This Safety Guide was prepared as part of the Agency's programme, referred to as the NUSS programme, for establishing Codes of Practice and Safety Guides relating to nuclear power plants. It supplements the Agency's Safety Series No.50-C-G, entitled ''Governmental Organization for the Regulation of Nuclear Power Plants: A Code of Practice'', and is mainly concerned with the qualifications and training requirements of the staff of bodies regulating nuclear power plants. It is not concerned with staff for regulating other phases of the fuel cycle, such as fuel fabrication and management. This Guide provides recommendations and guidance for establishing the qualifications required for the staff of the regulatory body. These requirements include academic training, work experience and other abilities. It also establishes the training programmes and activities necessary for personnel within the regulatory body

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

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

International Nuclear Information System (INIS)

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

1996-01-01

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

Testing of Small Graphite Samples for Nuclear Qualification

Energy Technology Data Exchange (ETDEWEB)

Julie Chapman

2010-11-01

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

The study for the high qualification of international nuclear training

International Nuclear Information System (INIS)

Noh, Byong Chull; Kim, Hyun Jin

2012-12-01

It is suggested how to reach high qualification of KAERI international nuclear training and how to play a leading role for new paradigm on the international training on the world. 1. The formulation of the core nuclear training framework- The systematic formulation of nuclear training framework based on the existing turning course design 2. Planning and operation of KAERI- Excellent Technology Series training course- The advertisement for KAERI Excellent Technology through the continuous international training and the future market development on the world for the nuclear technology 3. e-Learning training contents development- e-Learning training contents development to play a leading role for new training paradigm on the world and to overcome the limit of time/spacy

The study for the high qualification of international nuclear training

Energy Technology Data Exchange (ETDEWEB)

Noh, Byong Chull; Kim, Hyun Jin

2012-12-15

It is suggested how to reach high qualification of KAERI international nuclear training and how to play a leading role for new paradigm on the international training on the world. 1. The formulation of the core nuclear training framework- The systematic formulation of nuclear training framework based on the existing turning course design 2. Planning and operation of KAERI- Excellent Technology Series training course- The advertisement for KAERI Excellent Technology through the continuous international training and the future market development on the world for the nuclear technology 3. e-Learning training contents development- e-Learning training contents development to play a leading role for new training paradigm on the world and to overcome the limit of time/spacy.

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.

Quality assurance and non-destructive testing for nuclear power plants

International Nuclear Information System (INIS)

Manlucu, F.A.

1991-01-01

This article discussed the quality assurance requirements which have been extensively applied in plant design, fabrication, construction and operation and has played a major role in the excellent safety record of nuclear power plants. The application of non-destructive testing techniques, plays a very important role during the in-service inspection (ISI) in order to prevent dangerous accident and to assure continuous safe operation of nuclear power plants. (IMA). 12 refs

Dynamic analysis and qualification test of nuclear components

International Nuclear Information System (INIS)

Kim, B.K.; Lee, C.H.; Park, S.H.; Kim, Y.M.; Kim, B.S.; Kim, I.G.; Chung, C.W.; Kim, Y.M.

1981-01-01

This report contains the study on the dynamic characteristics of Wolsung fuel rod and on the dynamic balancing of rotating machinery to evaluate the performance of nuclear reactor components. The study on the dynamic characteristics of Wolsung fuel rod was carried out by both experimental and theoretical methods. Forced vibration testing of actual Wolsung fuel rod using sine sweep and sine dwell excitation was conducted to find the dynamic and nonlinear characteristics of the fuel rod. The data obtained by the test were used to analyze the nonlinear impact characteristics of the fuel rod which has a motion-constraint stop in the center of the rod. The parameters used in the test were the input force level of the exciter, the clearance gap between the fuel rod and the motion constraints, and the frequencies. Test results were in good agreement with the analytical results

Seismic qualification method of equipment for nuclear power plant

International Nuclear Information System (INIS)

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

1995-01-01

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

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)

High Temperature Materials Interim Data Qualification Report FY 2011

International Nuclear Information System (INIS)

Lybeck, Nancy

2011-01-01

Projects for the very high temperature reactor (VHTR) Technology Development Office provide data in support of Nuclear Regulatory Commission licensing of the VHTR. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high temperature and high fluence environments. The VHTR program has established the Next Generation Nuclear Plant (NGNP) Data Management and Analysis System (NDMAS) to ensure that VHTR data are qualified for use, stored in a readily accessible electronic form, and analyzed to extract useful results. This document focuses on the first NDMAS objective. It describes the High Temperature Materials characterization data stream, the processing of these data within NDMAS, and reports the interim fiscal year (FY) 2011 qualification status of the data. Data qualification activities within NDMAS for specific types of data are determined by the data qualification category assigned by the data generator. The High Temperature Materials data are being collected under the Nuclear Quality Assurance (NQA)-1 guidelines and will be qualified data. For NQA-1 qualified data, the qualification activities include: (1) capture testing to confirm that the data stored within NDMAS are identical to the raw data supplied, (2) accuracy testing to confirm that the data are an accurate representation of the system or object being measured, and (3) documenting that the data were collected under an NQA-1 or equivalent Quality Assurance program. Currently, data from seven test series within the High Temperature Materials data stream have been entered into the NDMAS vault, including tensile tests, creep tests, and cyclic tests. Of the 5,603,682 records currently in the vault, 4,480,444 have been capture passed, and capture testing is in process for the remaining 1,123,238.

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

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

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

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

Training guidelines in non-destructive testing techniques

International Nuclear Information System (INIS)

1991-10-01

Non-destructive testing methods (NDT), by their very nature, allow components to be fully examined for properties or flaws without interfering with their usefulness. This grouping of inspection methods has grown from a handful of primitive techniques practised by artists to a widely known discipline which is an essential part of quality control, largely as a result of the standards demanded by the nuclear and aerospace industries. Recognizing the need for an international publication of NDT training syllabi, the IAEA Consultants Meeting on ''Qualification and Certification of NDT Personnel'' (Milan, 20-21 May 1986), recommended that the Agency publish the guidelines developed by Regional Working Group of the Latin America and Caribbean project. It was first issued in English in 1987 and has now been re-edited in English and Spanish and enlarged by the addition of programmes for other techniques

Staffing, recruitment, training, qualification and certification of operating personnel of nuclear power plants

International Nuclear Information System (INIS)

1999-10-01

Safety of public, occupational workers and the protection of environment should be assured while activities for economic and social progress are pursued. These activities include the establishment and utilisation of nuclear facilities and the use of radioactive sources. This safety guide provides guidance on the aspects of staffing, recruitment, training, qualification and certification of operating personnel of nuclear power plants

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

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)

Qualifying commercial grade instruments for use in nuclear power generating stations

International Nuclear Information System (INIS)

Lamothe, R.J.; Scally, C.R.

1983-01-01

Nuclear environmental qualification of instrumentation has been successfully accomplished by many commercial grade equipment manufacturers. This paper was prepared as a guide to those manufacturers who want some insight into a qualification program. The areas addressed are the regulations and documents, the qualification program, and a case history of a chart recorder qualifications. The principal standards relating to a nuclear qualification program are IEEE Std. 323-1974 IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations, IEEE Std. 344-1975 IEEE Recommended Practices for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations and 10CFR50.49. Previously NUREG 0588 Interim Staff Position on Environmental Qualification of Safety-Related Equipment. These define the intent and purpose of the qualification. The qualification program itself consists of several distinct parts which require explanation, including the determination of qualified life, choice of test samples, selection of appropriate acceptance criteria, aging program, radiation testing, seismic testing, abnormal environment tests and others. The case history illustrates the qualification program and the thought processes involved

WTP Waste Feed Qualification: Glass Fabrication Unit Operation Testing Report

Energy Technology Data Exchange (ETDEWEB)

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

2016-07-14

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

A summary of the conclusions of generic issue 113: Dynamic qualification and testing of large bore hydraulic snubbers

International Nuclear Information System (INIS)

Ware, A.G.; Nitzel, M.E.

1993-01-01

The Nuclear Regulatory Commission (NRC) developed Generic Issue 113, Dynamic Qualification and Testing of Large Bore Hydraulic Snubbers (LBHSs), with the objective of evaluating the reliability of LBHSs in operating commercial nuclear power plants. For the purposes of this research, LBHSs were defined as those hydraulic snubbers with rated load capacities ≥50 kips. Relatively high LBHS failure rates were common during the early 1980s; however, industry actions taken during the last several years in response to increased inspection and testing requirements have resulted in lower LBHS failure rates. To address the issue of LBHS adequacy, the NRC developed Generic Issue 113 (GI-113). This paper provides a summary of the important findings of the GI-113 research program and a discussion of the recommendations that were made in NUREG/CR-5416. Fifteen potential improvements in LBHS reliability were identified, covering the areas of design, environmental (including dynamic) qualification, functional testing, visual inspection, and personnel training. Probabilistic risk assessment studies were used to perform a cost/benefit analysis for each. There were five potential improvements in functional testing and visual inspections with low cost/benefit ratios for both existing and future nuclear plants, and an additional six potential improvements that were determined to be cost beneficial only for future plants. Further investigations of the single failure of snubbers that could damage critical components or systems were recommended in NUREG/CR-5416

Challenges in education and qualification of human resources for next nuclear generation

International Nuclear Information System (INIS)

Pupak, Marcia Orrico

2009-01-01

The general goal of this paper is to present an overview of Higher Education and personnel qualification for Nuclear Field by the perspective of the International Atomic Energy Agency (IAEA), also by the Organization for Economic Co-operation and Development (OECD and by the United Nations Educational Scientific and Cultural Organization (UNESCO). On the other hand to present the challenge of the Brazilian Government in redesigning, since 2003, the role of the state in order to make it active for younger generations, while promoting growth and social justice, has guided in all actions carried out under the Policy of Human Resources Management of public personnel. The government should be able to formulate and implement public policies and decide among various options, what is the most appropriate for its Human Resources. For this, they require the strengthening of strategic intelligence and government adoption of new ways of interaction and participation. The role played by the Brazilian Nuclear Energy Commission (CNEN) in looking forward to replace and qualify its nuclear staff, as soon as up, since that the qualification of a human resource in this field demands more than one decade. Last but not least the proactive work of IPEN-CNEN/SP to encourage young generation to enter nuclear area, and the efforts of the Brazilian government to implement an integrated Nuclear Programme to form human resources, to attract and retain students in nuclear engineering and related specialized fields, and how this problem should attract the attention of the entire nuclear community, government and industry. (author)

Chapter 9. Personnel qualification and training

International Nuclear Information System (INIS)

2001-01-01

The overall training system and the development of projects for training of all categories of NPP V-1, NPP V-2 Bohunice, SE-VYZ and NPP Mochovce staff were the subject of Nuclear Regulatory Authority of the Slovak Republic (UJD) attention. During 2000, the following inspections were carried out on nuclear personnel training: (a) NPP Bohunice: an inspection focused on compliance with requirements for staff qualifications and compliance with the prescribed training of Bohunice plant staff ; (b) NPP Mochovce: an inspection focused on compliance with the requirements for staff qualifications and compliance with the prescribed training of NPP Mochovce staff; an inspection focused on verifying the simulator aided training; an inspection focused on checking the preparedness of NPP Mochovce operation and technical personnel for NPP Mochovce Unit 2 operation; (c) Technology for treatment and conditioning of radioactive waste Bohunice (BSC): an inspection focused on compliance with the requirements for staff qualifications and compliance with the prescribed training of SE-VYZ staff; VUJE Trnava: verification of technical equipment and professional skills of VUJE Trnava staff and tasks arising out of the 'Authorisation on nuclear installation staff training'. Examinations of selected personnel were scheduled according to the plan of examining committee meetings. For each examined person written tests are generated by the computer from the database of test questions at the Training Centre of VUJE Trnava for individual positions - categories of selected staff of NPP V-1 and NPP V-2 Bohunice and NPP Mochovce so that the examination questions both in written and oral part equally cover individual facilities and regimes of operation of NPP. The database is continuously updated, thereby containing new questions resulting from the recent changes carried out at NPPs. A part of the examination in case of promotion to a higher position is the practical part, which is conducted under

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

Energy Technology Data Exchange (ETDEWEB)

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

2016-06-01

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

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)

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.

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

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

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

International Nuclear Information System (INIS)

Adams, T.M.

1996-01-01

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

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

Training Guidelines in Non-destructive Testing Techniques. 2013 Edition

International Nuclear Information System (INIS)

2014-12-01

The IAEA promotes industrial applications of radiation technology, including non-destructive testing (NDT), through activities such as Technical Cooperation Projects (national and regional) and Coordinated Research Projects. Through this cooperation, Member States have initiated national programmes for the training and certification of NDT personnel. National certifying bodies have also been established based on International Organization for Standardization (ISO) standards. As part of these efforts, the IAEA has been actively involved in developing training materials. Consequently, IAEA-TECDOC-407, Training Guidelines in Non-destructive Testing Techniques, was published in 1987, then revised and expanded as IAEA-TECDOC-628 in 1991. Revisions of IAEA-TECDOC-628 were considered essential to meet the demands of end-user industries in Member States, and revised and expanded versions were issued in 2002 and 2008. These latter versions included work conducted by the International Committee for Non-Destructive Testing (ICNDT) and many national NDT societies. It is one of the publications referred to in ISO 9712:2005, Non-destructive Testing: Qualification and Certification of Personnel, which in turn is an internationally accepted standard, revised as ISO 9712:2012, Non-destructive Testing: Qualification and Certification of NDT Personnel. This publication is an updated version of IAEA-TECDOC-628. The content of which has been revised following the changes of ISO 9712 converging with EN 473 and becoming EN ISO 9712:2012, based on the experience of experts and comments from end-user industries. The details of the topics on each subject have been expanded to include the latest developments in the respective methods. The incorporated changes will assist the end-user industries to update their NDT qualification and certification schemes and course materials. This publication, like the previous versions, will continue to play an important role in international harmonization

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

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

Qualification testing of flat-plate photovoltaic modules

Science.gov (United States)

Hoffman, A. R.; Griffith, J. S.; Ross, R. G., Jr.

1982-01-01

The placement of photovoltaic modules in various applications, in climates and locations throughout the world, results in different degrees and combinations of environmental and electrical stress. Early detection of module reliability deficiencies via laboratory testing is necessary for achieving long, satisfactory field service. This overview paper describes qualification testing techniques being used in the US Department of Energy's flat-plate terrestrial photovoltaic development program in terms of their significance, rationale for specified levels and durations, and test results.

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)

Seismic qualification for water chillers of nuclear power plant

International Nuclear Information System (INIS)

Wang Chunming

2005-01-01

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

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

International Nuclear Information System (INIS)

Anon.

1981-01-01

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

Thermal Analysis for Environmental Qualification of Kori Nuclear power plant unit 3 and 4

International Nuclear Information System (INIS)

Seo, Kwi Hyun; Byun, Choong Sup; Song, Dong Soo

2006-01-01

This paper shows the temperature profiles of safety related electrical equipment exposed to MSLB inside containment. It must be demonstrated that the LOCA qualification conditions exceed or are equivalent to the maximum calculated MSLB conditions. COPATTA as Bechtel's vendor code is used for the containment pressure and temperature prediction in power uprating project for Kori 3,4 and Yonggwang 1,2 nuclear power plants(NPPs). However, CONTEMPT-LT/028 is used for calculating the containment pressure and temperatures in equipment qualification project for the same NPPs. Power uprating code that is, COPATTA benchmarking study performed in six equipment at saturation temperature and surface temperature. Specially, thermal analysis carefully investigate that view point environmental qualification and NUREG- 0588 be mentioned in regard to safety-related heat sink it boundary condition or geometry information

Thermal Analysis for Environmental Qualification of Kori Nuclear power plant unit 3 and 4

Energy Technology Data Exchange (ETDEWEB)

Seo, Kwi Hyun [ENERGEO Inc., Sungnam (Korea, Republic of); Byun, Choong Sup; Song, Dong Soo [KEPRI, Taejon (Korea, Republic of)

2006-07-01

This paper shows the temperature profiles of safety related electrical equipment exposed to MSLB inside containment. It must be demonstrated that the LOCA qualification conditions exceed or are equivalent to the maximum calculated MSLB conditions. COPATTA as Bechtel's vendor code is used for the containment pressure and temperature prediction in power uprating project for Kori 3,4 and Yonggwang 1,2 nuclear power plants(NPPs). However, CONTEMPT-LT/028 is used for calculating the containment pressure and temperatures in equipment qualification project for the same NPPs. Power uprating code that is, COPATTA benchmarking study performed in six equipment at saturation temperature and surface temperature. Specially, thermal analysis carefully investigate that view point environmental qualification and NUREG- 0588 be mentioned in regard to safety-related heat sink it boundary condition or geometry information.

Financial qualifications review of applicants for nuclear power plant construction permits

International Nuclear Information System (INIS)

Hendrickson, P.L.; Mullen, M.F.; Carr, D.B.

1988-09-01

The NRC and its predecessor the AEC have had a regulatory requirement since 1956 that utilities seeking a construction permit for a nuclear power plant be financially qualified to construct and operate the plant. Several amendments to the requirements were made over the years including an attempt in 1982 to drop financial qualification review for electric utilities. This attempt was subsequently found invalid by a federal court. Nevertheless, financial qualification reviews consume significant amounts of NRC staff time and time at Atomic Safety and Licensing Board hearings. The analysis reported in this study was conducted to determine whether there is any empirical evidence of a relationship between a utility's financial health at the time of its construction permits application and the subsequent safety performance of the operating plant. The principal financial measures used to test for this relationship were bond rating, interest coverage ratio, debt/asset ratio, debt/equity ratio, and rate of return on equity. The principal safety measure was the long-term average of the scores assigned the utility in four key areas by the NRC under the Systematic Assessment of Licensee Performance program. The results of the analysis showed no evidence of a relationship between financial health at the time of the construction permit and subsequent safety performance. 7 refs., 16 figs., 4 tabs

Underground Nuclear Testing Program, Nevada Test Site

International Nuclear Information System (INIS)

1975-09-01

The Energy Research and Development Administration (ERDA) continues to conduct an underground nuclear testing program which includes tests for nuclear weapons development and other tests for development of nuclear explosives and methods for their application for peaceful uses. ERDA also continues to provide nuclear explosive and test site support for nuclear effects tests sponsored by the Department of Defense. This Supplement extends the Environmental Statement (WASH-1526) to cover all underground nuclear tests and preparations for tests of one megaton (1 MT) or less at the Nevada Test Site (NTS) during Fiscal Year 1976. The test activities covered include numerous continuing programs, both nuclear and non-nuclear, which can best be conducted in a remote area. However, if nuclear excavation tests or tests of yields above 1 MT or tests away from NTS should be planned, these will be covered by separate environmental statements

Data qualification summary for 1985 L-Area AC Flow Tests

International Nuclear Information System (INIS)

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

1992-03-01

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

Role of non-destructive examinations in leak testing of glove boxes for industrial scale plutonium handling at nuclear fuel fabrication facility along with case study

International Nuclear Information System (INIS)

Aher, Sachin

2015-01-01

Non Destructive Examinations has the prominent role at Nuclear Fuel Fabrication Facilities. Specifically NDE has contributed at utmost stratum in Leak Testing of Glove Boxes and qualifying them as a Class-I confinement for safe Plutonium handling at industrial scale. Advanced Fuel Fabrication Facility, BARC, Tarapur is engaged in fabrication of Plutonium based MOX (PuO 2 , DDUO 2 ) fuel with different enrichments for first core of PFBR reactor. Alpha- Leak Tight Glove Boxes along with HEPA Filters and dynamic ventilation form the promising engineering system for safe and reliable handling of plutonium bearing materials considering the radiotoxicity and risk associated with handling of plutonium. Leak Testing of Glove Boxes which involves the leak detection, leak rectification and leak quantifications is major challenging task. To accomplish this challenge, various Non Destructive Testing methods have assisted in promising way to achieve the stringent leak rate criterion for commissioning of Glove Box facilities for plutonium handling. This paper highlights the Role of various NDE techniques like Soap Solution Test, Argon Sniffer Test, Pressure Drop/Rise Test etc. in Glove Box Leak Testing along with procedure and methodology for effective rectification of leakage points. A Flow Chart consisting of Glove Box leak testing procedure starting from preliminary stage up to qualification stage along with a case study and observations are discussed in this paper. (author)

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

Qualification of RETRAN for simulator applications

International Nuclear Information System (INIS)

Harrison, J.F.

1988-01-01

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

Qualification 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.

Nuclear-waste-package materials degradation modes and accelerated testing

International Nuclear Information System (INIS)

1981-09-01

This report reviews the materials degradation modes that may affect the long-term behavior of waste packages for the containment of nuclear waste. It recommends an approach to accelerated testing that can lead to the qualification of waste package materials in specific repository environments in times that are short relative to the time period over which the waste package is expected to provide containment. This report is not a testing plan but rather discusses the direction for research that might be considered in developing plans for accelerated testing of waste package materials and waste forms

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

EDS V25 containment vessel explosive qualification test report.

Energy Technology Data Exchange (ETDEWEB)

Rudolphi, John Joseph

2012-04-01

The V25 containment vessel was procured by the Project Manager, Non-Stockpile Chemical Materiel (PMNSCM) as a replacement vessel for use on the P2 Explosive Destruction Systems. It is the first EDS vessel to be fabricated under Code Case 2564 of the ASME Boiler and Pressure Vessel Code, which provides rules for the design of impulsively loaded vessels. The explosive rating for the vessel based on the Code Case is nine (9) pounds TNT-equivalent for up to 637 detonations. This limit is an increase from the 4.8 pounds TNT-equivalency rating for previous vessels. This report describes the explosive qualification tests that were performed in the vessel as part of the process for qualifying the vessel for explosive use. The tests consisted of a 11.25 pound TNT equivalent bare charge detonation followed by a 9 pound TNT equivalent detonation.

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.

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

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

Licensing requirements regarding the qualification of operating personnel in nuclear power plants

International Nuclear Information System (INIS)

Fechner, J.B.

1981-01-01

The legal requirements regarding the qualifications of operating personnel in nuclear power plants in the Federal Republic of Germany are outlined as in article 7 of the Atomic Energy Act. For the responsible operating personnel the requisite competence and reliability are legally required; for subordinate personnel the law requires only the necessary knowledge. The requisite competence and the necessary knowledge have been further specified in a set of guidelines by the authorities; work on specification of reliability requirements is under way. Essential elements of the requisite competence of responsible operating personnel are their professional qualification, their safety-related knowledge, their abilities, their practical experience, and - for the responsible shift personnel - their nuclear, plant-related training as well as a written and oral examination. Requalification is indispensible for keeping the requisite competence on a level in accordance with the current state of science and technology. Facts concerning the personal reliability of the responsible operating personnel are assessed by the competent authorities on the basis of information available at other state institutions. For the responsible shift personnel, physical and psychological fitness are important factors contributing to their reliability. The necessary knowledge subordinate operating personnel must possess with respect to plant safety and safety of the personnel is assured via instruction on safety and via special briefings at the working place. Lack of safety-related knowledge has to be compensated for by assigning an experienced permanent supervisor for each activity in question. Current work on qualification of operating personnel concentrates on training, including simulator training, of responsible shift personnel. (author)

Workshop on environmental qualification of electric equipment

International Nuclear Information System (INIS)

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

1994-05-01

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

Workshop on environmental qualification of electric equipment

Energy Technology Data Exchange (ETDEWEB)

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

1994-05-01

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

Qualification Test for Korean Mockups of ITER Blanket First Wall

International Nuclear Information System (INIS)

Kim, S. K.; Lee, D. W.; Bae, Y. D.; Hong, B. G.; Jung, H. K.; Jung, Y. I.; Park, J. Y.; Jeong, Y. H.; Choi, B. K.; Kim, B. Y.

2009-01-01

ITER First Wall (FW) includes the beryllium armor tiles joined to CuCrZr heat sink with stainless steel cooling tubes. This first wall panels are one of the critical components in the ITER machine with the surface heat flux of 0.5 MW/m 2 or above. So qualification program needs to be performed with the goal to qualify the joining technologies required for the ITER First Wall. Based on the results of tests, the acceptance of the developed joining technologies will be established. The results of this qualification test will affect the final selection of the manufacturers for the ITER First Wall

Training guidelines in non-destructive testing techniques. 1991 edition

International Nuclear Information System (INIS)

1991-10-01

Non-destructive testing methods (NDT), by their very nature, allow components to be fully examined for properties or flaws without interfering with their usefulness. This grouping of inspection methods has grown from a handful of primitive techniques practised by artists to a widely known discipline which is an essential part of quality control, largely as a result of the standards demanded by the nuclear and aerospace industries. Recognizing the need for an international publication of NDT training syllabi, the IAEA Consultants Meeting on ''Qualification and Certification of NDT Personnel'' (Milan, 20-21 May 1986), recommended that the Agency publish the guidelines developed by Regional Working Group of the Latin America and Caribbean project. It was first issued in English in 1987 and has now been re-edited in English and Spanish and enlarged by the addition of programmes for other techniques

A quality assurance program for nuclear power reactor materials tests at the Ford nuclear reactor

International Nuclear Information System (INIS)

Burn, R.R.

1989-01-01

The University of Michigan Nuclear Reactor Laboratory Quality Assurance Program has been established to assure that materials testing services provided to electric utilities produce accurate results in accordance with industry standards, sound engineering practice, and customer requirements. The program was prepared to comply with applicable requirements of 10CFR50, Appendix B, of the Code of Federal Regulations and a standard of the American National Standards Institute (ANSI), N45.2. The paper discusses the quality assurance program applicability, organization, qualification and training of personnel, material identification and control, examination and testing, measuring and test equipment, nonconforming test equipment, records, audits, and distribution

Type test of Class 1E electric cables, field splices, and connections for nuclear power generating stations - 1975

International Nuclear Information System (INIS)

Anon.

1976-01-01

This Standard provides direction for establishing type tests which may be used in qualifying Class 1E electric cables, field splices, and other connections for service in nuclear power generating stations. General guidelines for qualifications are given in IEEE Std 323-1974, Standard for Qualifying Class 1E Electric Equipment for Nuclear Power Generating Stations. Categories of cables covered are those used for power control and instrumentation services. Though intended primarily to pertain to cable for field installation, this guide may also be used for the qualification of internal wiring of manufactured devices

Dynamic testing of nuclear power plant structures: an evaluation

International Nuclear Information System (INIS)

Weaver, H.J.

1980-02-01

Lawrence Livermore Laboratory (LLL) evaluated the applications of system identification techniques to the dynamic testing of nuclear power plant structures and subsystems. These experimental techniques involve exciting a structure and measuring, digitizing, and processing the time-history motions that result. The data can be compared to parameters calculated using finite element or other models of the test systems to validate the model and to verify the seismic analysis. This report summarizes work in three main areas: (1) analytical qualification of a set of computer programs developed at LLL to extract model parameters from the time histories; (2) examination of the feasibility of safely exciting nuclear power plant structures and accurately recording the resulting time-history motions; (3) study of how the model parameters that are extracted from the data be used best to evaluate structural integrity and analyze nuclear power plants

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

International Nuclear Information System (INIS)

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

1986-01-01

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

Containment nuclear plant structures evaluation by non destructive testing: strategy and results

OpenAIRE

GARNIER, Vincent; HENAULT, Jean-Marie; HAFID, Hamid; VERDIER, Jérôme; CHAIX, Jean François; ABRAHAM, Odile; SBARTAÏ, Zoubir Medhi; BALAYSSAC, Jean Pierre; PIWAKOWSKI, Bogdan; VILLAIN, Géraldine; DEROBERT, Xavier; PAYAN, Cédric; RAKOTONARIVO, Sandrine; LAROSE, Eric; SOGBOSSI, Hognon

2016-01-01

Containment nuclear plants structures are an ultimate barrier in the event of an accident. Mechanical resistance and tightness are the two functions that they are expected to provide. To evaluate their capacity to perform them, destructive testing cannot be used to characterize the material. Non-Destructive Tests then represent a relevant solution to test concrete and the struc- ture. The article positions NDT within the context of containment structures supervision and maintenance, and prese...

Qualification tests and facilities for the ITER superconductors

International Nuclear Information System (INIS)

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

2009-01-01

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

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

International Nuclear Information System (INIS)

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

1999-11-01

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

10 CFR 26.85 - Collector qualifications and responsibilities.

Science.gov (United States)

2010-01-01

... 10 Energy 1 2010-01-01 2010-01-01 false Collector qualifications and responsibilities. 26.85 Section 26.85 Energy NUCLEAR REGULATORY COMMISSION FITNESS FOR DUTY PROGRAMS Collecting Specimens for... reports, if any; results of tests to establish employee competency for the position he or she holds...

Qualification and application of nuclear reactor accident analysis code with the capability of internal assessment of uncertainty

International Nuclear Information System (INIS)

Borges, Ronaldo Celem

2001-10-01

This thesis presents an independent qualification of the CIAU code ('Code with the capability of - Internal Assessment of Uncertainty') which is part of the internal uncertainty evaluation process with a thermal hydraulic system code on a realistic basis. This is done by combining the uncertainty methodology UMAE ('Uncertainty Methodology based on Accuracy Extrapolation') with the RELAP5/Mod3.2 code. This allows associating uncertainty band estimates with the results obtained by the realistic calculation of the code, meeting licensing requirements of safety analysis. The independent qualification is supported by simulations with RELAP5/Mod3.2 related to accident condition tests of LOBI experimental facility and to an event which has occurred in Angra 1 nuclear power plant, by comparison with measured results and by establishing uncertainty bands on safety parameter calculated time trends. These bands have indeed enveloped the measured trends. Results from this independent qualification of CIAU have allowed to ascertain the adequate application of a systematic realistic code procedure to analyse accidents with uncertainties incorporated in the results, although there is an evident need of extending the uncertainty data base. It has been verified that use of the code with this internal assessment of uncertainty is feasible in the design and license stages of a NPP. (author)

Assessment of job-related educational qualifications for nuclear power plant operators

International Nuclear Information System (INIS)

Saari, L.M.; Melber, B.D.; White, A.S.

1985-04-01

This report identifies job-related educational qualifications for the nuclear power plant licensed operator positions of reactor operator (RO), senior reactor operator (SRO), and shift supervisor (SS). The extent to which college engineering curriculum covers job-related academic knowledge was assessed. The approach used was to have subject matter experts in the field of general and nuclear engineering curriculum systematically compare college engineering program content to specific academic knowledge identified by a job analysis as necessary for licensed operators. In addition, these experts made judgments concerning levels of formal engineering education necessary for application of knowledge on the job, based on job samples from a job analysis of activities under selected normal and emergency operating sequences

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

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

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

Energy Technology Data Exchange (ETDEWEB)

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

1994-04-01

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

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

International Nuclear Information System (INIS)

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

1994-04-01

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

The Nuclear Non-Proliferation Treaty: Regulating Nuclear Weapons around the World

Science.gov (United States)

Middleton, Tiffany Willey

2010-01-01

In May 2010, scientists, national security experts, and state delegates from nations around the world will convene in New York for the 2010 Nuclear Non-Proliferation Treaty Review Conference. They will review current guidelines for nuclear testing and possession of nuclear weapons in accordance with the Nuclear Non-Proliferation Treaty of 1968,…

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.)

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

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

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)

Process qualification and testing of LENS deposited AY1E0125 D-bottle brackets

International Nuclear Information System (INIS)

Atwood, Clinton J.; Smugeresky, John E.; Jew, Michael; Gill, David Dennis; Scheffel, Simon

2006-01-01

The LENS Qualification team had the goal of performing a process qualification for the Laser Engineered Net Shaping(trademark)(LENS(reg s ign)) process. Process Qualification requires that a part be selected for process demonstration. The AY1E0125 D-Bottle Bracket from the W80-3 was selected for this work. The repeatability of the LENS process was baselined to determine process parameters. Six D-Bottle brackets were deposited using LENS, machined to final dimensions, and tested in comparison to conventionally processed brackets. The tests, taken from ES1E0003, included a mass analysis and structural dynamic testing including free-free and assembly-level modal tests, and Haversine shock tests. The LENS brackets performed with very similar characteristics to the conventionally processed brackets. Based on the results of the testing, it was concluded that the performance of the brackets made them eligible for parallel path testing in subsystem level tests. The testing results and process rigor qualified the LENS process as detailed in EER200638525A

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

Towards a nuclear-test ban

International Nuclear Information System (INIS)

1991-01-01

In 1986 and again in 1987 the General Assembly adopted resolutions by which it called on States conducting nuclear-test explosions to notify the Secretary-General, within one week of each explosion, of the time, place, yield and site characteristics of the test and also invited all other States to provide any such data on nuclear explosions that they might have. Over the years, in the Conference on Disarmament, members of the Group of 21 (mostly neutral and non-aligned countries) have continued to attach the utmost importance to the urgent conclusion of a comprehensive test-ban treaty as a significant contribution to the aim of ending the qualitative refinement of nuclear weapons and the development of new types of such weapons as well as of reversing the nuclear-arms race and achieving nuclear disarmament. In 1995 a conference will be convened to decide whether the non-proliferation Treaty will continue in force indefinitely, or will be extended for an additional fixed period or periods. Many States support the view that a comprehensive test ban would be a significant contribution to the non-proliferation of nuclear weapons; and some believe that, without a cessation of nuclear testing, it may not be possible to extend the NPT well beyond 1995. Other States, however, are of the opinion that the NPT, independently, offers benefits for the security of all States and, by its extension, will continue to do so

Development of methods for nuclear power plant personnel qualifications and training

International Nuclear Information System (INIS)

Jorgensen, C.C.; Carter, R.J.

1984-01-01

The Nuclear Regulatory Commission (NRC) has proposed additions and revisions to Title 10 of the Code of Federal Regulations, Parts 50 and 55, and to Regulatory Guides 1.8 and 1.149. ORNL is developing methods and some aspects of the technical basis for the implementation and assessment of training programs, personnel qualifications, and simulation facilities. The paper describes the three methodologies which were developed during the FY-1984 research: a task sort procedure (TSORT); a simulation facility evaluation methodology; and a task analysis profiling system (TAPS)

Development of non-destructive testing. Turkey

International Nuclear Information System (INIS)

1991-01-01

A National Scheme for the qualification and certification of Non-Destructive Testing (NDT) personnel in various methods has been established as the first stage of implementation. Systematic training in such methods as radiography (RT), ultrasonics (UT), magnetic particles (MT), liquid penetrant (PT) and eddy currents (ET) at levels I, II and some at III has been initiated and should be continued. Direct link with the industry and continuous effort to extend practical applications is strongly recommended

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.

Training and qualification of licensed reactor operators at General Public Utilities Nuclear Corporation

International Nuclear Information System (INIS)

Long, R.L.; Coe, R.P.

1992-01-01

Following the Three Mile Island-2 (TMI-2) accident in 1979, the utility responsible for managing the facility has looked closely at the training and qualification of its reactor operators. Performance-based operator training programmes are now in place, as required by the United States National Academy for Nuclear Training. Operators also participate directly in the development of a professional code of behaviour. (UK)

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

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

46 CFR 54.20-5 - Welding qualification tests and production testing (modifies UW-26, UW-28, UW-29, UW-47, and UW-48).

Science.gov (United States)

2010-10-01

... 46 Shipping 2 2010-10-01 2010-10-01 false Welding qualification tests and production testing... OF HOMELAND SECURITY (CONTINUED) MARINE ENGINEERING PRESSURE VESSELS Fabrication by Welding § 54.20-5 Welding qualification tests and production testing (modifies UW-26, UW-28, UW-29, UW-47, and UW-48). (a...

Evaluation of environmental qualification period for Conax electrical penetration assemblies. Final report

International Nuclear Information System (INIS)

Doroshuk, B.; Hager, M.; Brown, R.

1995-05-01

This report evaluates the environmental qualification period of Conax electrical penetration assemblies (EPAs) for extension from forty (40) years to sixty (60) years. The evaluation was performed based on a review of Conax EPAs supplied to Baltimore Gas ampersand Electric's (BGE) Calvert Cliffs Nuclear Power Plant Units 1 and 2. The report has been prepared so that it may be of use to any utility involved in the extension of the environmental qualification period for Conax EPAs installed in their plant(s). The report includes a section on the strategy which was developed for the effort to extend the qualified lives of the Conax EPAs. A review of documentation and plant conditions specific to BGE is included in the report to demonstrate the methodology. The documentation included qualification testing performed by Conax of the materials of construction of the EPA models. The plant conditions reviewed included both normal and accident environments, both of which are specific to Calvert Cliffs Nuclear Power Plant Units 1 and 2. This report can be used as a guide in the evaluation of similar installations of Conax electrical penetration assemblies in other nuclear power plants by applying the methodologies used herein in conjunction with the plant specific test reports, materials, and conditions

Selected fault testing of electronic isolation devices used in nuclear power plant operation

International Nuclear Information System (INIS)

Villaran, M.; Hillman, K.; Taylor, J.; Lara, J.; Wilhelm, W.

1994-05-01

Electronic isolation devices are used in nuclear power plants to provide electrical separation between safety and non-safety circuits and systems. Major fault testing in an earlier program indicated that some energy may pass through an isolation device when a fault at the maximum credible potential is applied in the transverse mode to its output terminals. During subsequent field qualification testing of isolators, concerns were raised that the worst case fault, that is, the maximum credible fault (MCF), may not occur with a fault at the maximum credible potential, but rather at some lower potential. The present test program investigates whether problems can arise when fault levels up to the MCF potential are applied to the output terminals of an isolator. The fault energy passed through an isolated device during a fault was measured to determine whether the levels are great enough to potentially damage or degrade performance of equipment on the input (Class 1E) side of the isolator

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

International Nuclear Information System (INIS)

Liu Dong; Wang Hongyin; Zhang Yong

2013-01-01

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

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

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 of NEXUS/ANC Nuclear Design System for PWR Analyses

International Nuclear Information System (INIS)

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

2008-01-01

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

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

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).

Process Qualification Strategy for Advances Embedded Non Volatile Memory Technology : The Philips' 0.18um Embedded Flash Case

NARCIS (Netherlands)

Tao, Guoqiao; Scarpa, Andrea; van Dijk, Kitty; Kuper, Fred G.

2003-01-01

A qualification strategy for advanced embedded non-volatile memory technology has been revealed. This strategy consists of: a thorough understanding of the requirements, extensive use and frequent update of the FMEA (failure mode effect analysis), a qualification plan with excellent coverage of all

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.

Nuclear power plant Olkiluoto 3. Containment leakage test under extreme conditions

Energy Technology Data Exchange (ETDEWEB)

Fleckenstein, Tobias [TUEV SUED Industrie Service GmbH, Munich (Germany). Measaruement Technology Dept.

2015-01-15

Modern nuclear power plants place high demands on the design and execution of safety checks. TUEV SUED supported the containment leakage test for the largest- capacity third generation nuclear power plant in the world - Olkiluoto 3 in Finland. The experts successfully met the challenges presented by exceptional parameters of the project. The containment of Olkiluoto 3 is unique in that the vessel's volume is 80,000 m{sup 3} while measurements were carried out over a period of ten days. To execute the test, 75 temperature and 15 humidity sensors had to be installed and correctly interlinked by more than ten kilometres of cable. These instruments also needed to withstand an absolute pressure of 6 bar, ambient temperatures of 30 C and high levels of humidity. These conditions required comprehensive preparation and a high amount of qualification tests. Parts of the qualifications were carried out at the autoclave system of the Technical University in Munich, Germany, where the project test conditions could be simulated. The software required to determine the tests was developed by TUEV SUED and verified by German's national accreditation body DAkkS under ISO 17025. TUEV SUED enabled the test schedule to continue without delay by analysing all recorded data continuously on site, including pressure, temperature, humidity and leakage mass flow curves. With the comprehensive preparation, data acquisition system recording measurements continuously and the on-time result calculation, all components of the leak-tightness assessment were successfully completed in accordance with requirements.

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)

Low-level radioactive waste form qualification testing

International Nuclear Information System (INIS)

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

1998-06-01

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

Low-level radioactive waste form qualification testing

Energy Technology Data Exchange (ETDEWEB)

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

1998-06-01

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

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

Qualification of a truly distributed fiber optic technique for strain and temperature measurements in concrete structures

Science.gov (United States)

Henault, J. M.; Salin, J.; Moreau, G.; Delepine-Lesoille, S.; Bertand, J.; Taillade, F.; Quiertant, M.; Benzarti, K.

2011-04-01

Structural health monitoring is a key factor in life cycle management of infrastructures. Truly distributed fiber optic sensors are able to provide relevant information on large structures, such as nuclear power plants or nuclear waste disposal facilities. The sensing chain includes an optoelectronic unit and a sensing cable made of one or more optical fibers. A new instrument based on Optical Frequency Domain Reflectometry (OFDR), enables to perform temperature and strain measurements with a centimeter scale spatial resolution over hundred of meters and with a level of precision equal to 1 μ strain and 0.1 °C. Several sensing cables are designed with different materials targeting to last for decades, either embedded in the concrete or attached to the surface of the structure. They must ensure an optimal transfer of temperature and strain from the concrete matrix to the optical fiber. Based on the European guide FD CEN/TR 14748 "Non-destructive testing - Methodology for qualification of non-destructive tests", a qualification method was developed. Tests were carried out using various sensing cables embedded in the volume or fixed to the surface of plain concrete specimens and representative-scale reinforced concrete structural elements. Measurements were performed with an OFDR instrument, while mechanical solicitations were imposed to the concrete element. Preliminary experiments seem very promising since measurements performed with distributed sensing systems are found comparable to values obtained with conventional sensors used in civil engineering and with the Strength of Materials Modelling. Moreover, the distributed sensing system makes it possible to detect and localize cracks appearing in concrete during the mechanical loading.

Application of non-destructive methods for qualification of the U3O8-Al and U3Si2-Al dispersion fuels in the IEA-R1 Reactor

International Nuclear Information System (INIS)

Silva, Jose Eduardo Rosa da

2011-01-01

IPEN/CNEN-SP manufactures fuels to be used in its nuclear research reactor - the IEA-R1. To qualify those fuels, it is necessary to check if they have a good performance under irradiation. As Brazil doesn't have nuclear research reactors with high neutron fluxes, or suitable hot cells for carrying out post-irradiation examination of nuclear fuels, IPEN/CNEN-SP has conducted a fuel qualification program based on the use of uranium compounds, internationally tested and qualified to be used in research reactors, and has gotten experience in the technological development stages for the manufacturing of fuel plates, irradiation and non-destructive post-irradiation testing. Fuel elements containing low volume fractions of fuel in the dispersion were manufactured and irradiated successfully directly in the core of the IEA-R1. However, there are plans to increase the uranium density of these fuels. The objective of this thesis work was to study and to propose a set of non-destructive methods to qualify the dispersions fuels U 3 O 8 -Al e U 3 Si 2 -Al with high uranium density produced at IPEN/CNEN-SP. For that, the irradiation resources in the IEA-R1, and the application of non-destructive methods in the reactor pool available in the Institution were considered. The proposal is to specify, manufacture and irradiate fuel mini plates in IEA-R1 at the maximum densities, qualified internationally, and to monitor their general conditions during the period of irradiation, using non-destructive methods in the reactor pool. In addition to the non-destructive visual inspection and sipping methods, already used at the Institution, the infrastructure for dimensional sub-aquatic testing to evaluate the swelling of irradiated fuel mini plates was completed. The analyses of the results will provide means to assess and decide whether or not to continue with the irradiation of mini plates, until the desired burnup for the irradiation tests at IEA-R1 are reached. (author)

New technologies in electromagnetic non-destructive testing

CERN Document Server

Huang, Songling

2016-01-01

This book introduces novel developments in the field of electromagnetic non-destructive testing and evaluation (NDT/E). The topics include electromagnetic ultrasonic guided wave testing, pulsed eddy current testing, remote field eddy current testing, low frequency eddy current testing, metal magnetic memory testing, and magnetic flux leakage testing. Considering the increasing concern about the safety maintenance of critical structures in various industries and everyday life, these topics presented here will be of particular interest to the readers in the NDT/E field. This book covers both theoretical researches and the engineering applications of the electromagnetic NDT technology. It could serve as a valuable reference for college students and relevant NDT technicians. It is also a useful material for qualification training and higher learning for nondestructive testing professionals.

Non-destructive testing: significant facts

International Nuclear Information System (INIS)

Espejo, Hector; Ruch, Marta C.

2006-01-01

In the last fifty years different organisations, both public and private, have been assigned to the mission of introducing into the country the most relevant aspects of the modern technological discipline 'Non Destructive Testing' (NDT) through a manifold of activities, such as training and education, research, development, technical assistance and services, personnel qualification/certification and standardisation. A review is given of the significant facts in this process, in which the Argentine Atomic Energy Commission, CNEA, played a leading part, a balance of the accomplishments is made and a forecast of the future of the activity is sketched. (author) [es

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

International Nuclear Information System (INIS)

Bracey, W.; Chiocca, R.

2004-01-01

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

Beryllium irradiation embrittlement test programme. Material and specimen specification, manufacture and qualification

International Nuclear Information System (INIS)

Harries, D.R.; Dalle Donne, M.

1996-06-01

The report presents the specification, manufacture and qualification of the beryllium specimens to be irradiated in the BR2 reactor in Mol to investigate the effect of the neutron irradiation on the embrittlement as a function of temperature and beryllium oxide content. This work was been performed in the framework of the Nuclear Fusion Project of the Forschungszentrum Karlsruhe and is supported by the European Union within the European Fusion Technology Program. (orig.)

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.

Maintaining non-nuclear weapon status

International Nuclear Information System (INIS)

Muller, H.

1991-01-01

Among the some 170 sovereign states in the world, five are legally recognized as nuclear weapon states (NWS) under the terms of the 1968 Non-Proliferation Treaty (NPT). Six countries (Argentina, Brazil, India, Israel, Pakistan, and South Africa) are counted as threshold states: they possess sizeable unsafeguarded nuclear facilities or have passed the brink of a nuclear test or of clandestine weapon production. Six other countries (Iran, Iraq, Libya, Taiwan, and North and South Korea) have been suspected periodically of either considering the nuclear weapon option or of working secretly on the development of weapons. Thus, about 150 non-nuclear weapon states (NNWS) remain which neither possess nuclear weapons nor strive to acquire them. These states are distributed throughout the globe and encompass highly industrialized as well as underdeveloped countries, liberal democracies, socialist states, sheikdoms and dictatorships. Some NNWS face acute military threats; other are far removed from the quarrels of the world, as in the case of some remote fortunate islands. Furthermore, NNWS may be members of nuclear-umbrella alliances or may have opted for a policy of neutrality or non-alignment

Electrical equipment qualification

International Nuclear Information System (INIS)

Farmer, W.S.

1983-01-01

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

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

Science.gov (United States)

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

2009-01-01

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

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.)

The Indian nuclear test in a global perspective

International Nuclear Information System (INIS)

Subrahmanyam, K.

1974-01-01

A peaceful nuclear explosion test was carried out by India on 18 May, 1974 at Pokharan in the Rajasthan Desert. The test was carried out as a part of India's steady programme to develop nuclear energy for peaceful purposes and there was no diversion of resources from development as is charged by some nations. The test has broken the monopoly of the nuclear superpowers to conduct nuclear tests for which they are entiltled by the Non-proliferation Treaty (NPT) and at the same time, sharply focussed the attention on the discriminatory character of the NPT which does not allow non-nuclear states to carry out nuclear tests even for peaceful purposes. It is argued that India's going nuclear may prove, in the long run, beneficial to the cause of disarmament. (M.G.B.)

Analysis of the Qualification-Tests Performance of the Superconducting Cavities for the SNS Linac

CERN Document Server

Delayen, J R; Ozelis, O

2004-01-01

Thomas Jefferson National Accelerating Facility (Jefferson Lab) is producing superconducting radio frequency (SRF) cryomodules for the Spallation Neutron Source (SNS) cold linac. This consists of 11 medium-beta (β=0.61) cyomodules of 3 cavities each, and 12 high-beta (β=0.81) cryomodules of 4 cavities each. Before assembly into cavity strings the cavities undergo individual qualification tests in a vertical cryostat (VTA). In this paper we analyze the performance of the cavities during these qualification tests, and attempt to correlate this performance with cleaning, assembly, and testing procedures. We also compare VTA performance with performance in completed cryomodules.

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.

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.)

On-the-job training and qualification of nuclear power plant personnel. OJT at the Loviisa NPP

International Nuclear Information System (INIS)

1996-01-01

On-the-job training and qualification process of nuclear power plant personnel is described, including the following issues: educational system of technical studies in Finland; training methods at the Loviisa NPP; on-the-job training of control room operators,field operators, maintenance personnel, other groups of the plant; qualifying examinations for different jobs

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

International Nuclear Information System (INIS)

Sun Haipeng; Liu Zhijun; Li Tianshu

2013-01-01

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

Application of acoustic emission, as non destructive testing technique, to nuclear components inspection

International Nuclear Information System (INIS)

Sanchez Miro, J.J.

1980-01-01

A panorama of actual state of acoustic emission as non destructive testing technique, from stand point of its safety applications to nuclear reactor is offered. In first place the physic grounds of acoustic emission phenomenon is briefly exposed. After we speak about the experimental methods for detection, and overall is made an explanation of the problems which are found during the application of this technology to on-line inspection of nuclear oower plants. It is hoped that this repport makes a contribution in the sense of to create a favourable atmosphere toward the introduction in our country of this important technique, and concretely within the nuclear power industry. In this last field the employ of acoustic emission is overcoming the experimental stage. (author)

Can the deterrence survive to nuclear tests ban

International Nuclear Information System (INIS)

Gaffney, F.J. Jr.

1996-01-01

The problem of the soundness of the nuclear tests stopping is discussed here. The safety, the durability of nuclear weapons need nuclear tests. So, unless other means able to guarantee the deterrence, it is prejudicial to stop nuclear tests and to sign a non proliferation treaty with the option of zero nuclear explosion. (N.C.)

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

Training implementation matrix. Spent Nuclear Fuel Project (SNFP)

International Nuclear Information System (INIS)

EATON, G.L.

2000-01-01

This Training Implementation Matrix (TIM) describes how the Spent Nuclear Fuel Project (SNFP) implements the requirements of DOE Order 5480.20A, Personnel Selection, Qualification, and Training Requirements for Reactor and Non-Reactor Nuclear Facilities. The TIM defines the application of the selection, qualification, and training requirements in DOE Order 5480.20A at the SNFP. The TIM also describes the organization, planning, and administration of the SNFP training and qualification program(s) for which DOE Order 5480.20A applies. Also included is suitable justification for exceptions taken to any requirements contained in DOE Order 5480.20A. The goal of the SNFP training and qualification program is to ensure employees are capable of performing their jobs safely and efficiently

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

International Nuclear Information System (INIS)

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

2004-01-01

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

An overview of non destructive inspection services in nuclear power plants

International Nuclear Information System (INIS)

Farley, S.

2004-01-01

Worldwide nuclear power plants are obliged by international and local authorities to perform periodical inspection and maintenance of safety relevant components. Non-Destructive Testing (NDT) techniques such as eddy current, ultrasonic, visual, dye penetrant and radiographic testing have been used and continually developed to inspect a wide range of components and materials. Inspecting such components invariably poses an interesting chal-lenge due to complex component geometries, radiation exposure and the material make-up of the component or its welds. As a leader in services to the nuclear industry, Westinghouse has an immense knowl-edge and experience in inspecting and repairing primary circuit components such as steam generators, reactor vessels, core internals, primary coolant pumps and loops, fuel elements and many other components in hazardous environments. To fulfil the requirements posed by authorities and inspection standards, remotely operated manipulators and vehicles have been designed to bring a diverse variety of probes and cameras to the object of inspection. Each inspection process is tested and qualified by the relevant qualification body. In some cases the results of an inspection may require further in depth analysis or even repair of part of the component. These added challenges have often been met by specifically designed and qualified processes such as for the repair of vessel head penetrations or the re-pair of vessel nozzle safe end welds. This presentation will give a general overview of a range of inspection capabilities and give a few examples in which repair was successfully performed. (author)

Decree of the President of the Republic No. 1450 of 30 December 1970. Regulations concerning the recognition of the qualifications for technical operation of nuclear installations

International Nuclear Information System (INIS)

1971-01-01

This Decree made in implementation of Act No. 1860 establishes the requirements and the procedure for obtaining the qualifications necessary for the technical management of nuclear installations. It also determines the classes of installations connected with each type of qualification. (NEA) [fr

Destructive and non-destructive tests for radioactive waste packages Task 3 Characterization of radioactive waste forms. A series of final reports (1985-89) No 43

International Nuclear Information System (INIS)

Odoj, R.

1991-01-01

On the basis of preliminary waste acceptance requirements quality control of radioactive waste has to be performed prior to interim storage or final disposal. The quality control can either be achieved by random tests on conditioned radioactive waste packages or by process qualification of the conditioning processes. One of the most important criteria is the activity of the radioactive waste product or packages. To get some first information on the waste package γ-spectrometric measurement is performed as non-destructive test. Besides the γ-emitting nuclides the α and β-emitting nuclides can be estimated by calculation if the waste was generated in nuclear power plants and the nuclide relations are known. If the non-destructive determination of nuclides is not sufficient or the non-radioactive content of the waste packages has to be identified sampling from the waste packages has to be performed. This can best be done by core drilling. To avoid the need of water for cooling the drill head, air cooled core drilling is investigated. As mixed wastes is not allowed for final disposal the determination of possible organic toxic materials like PCB, dioxin and furane-compounds in cemented wastes is conducted by GC-MS-investigations. For getting more knowledge in the field of process qualification concerning super compaction, instrumentation of the super compaction process is investigated and tested

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

International Nuclear Information System (INIS)

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

1999-01-01

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

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.

A comprehensive nuclear test ban

International Nuclear Information System (INIS)

1985-01-01

The conclusion of a comprehensive nuclear test ban is of critical importance for the future of arms limitation and disarmament. As the 1980 report of the Secretary-General concluded, a comprehensive nuclear test ban is regarded as the first and most urgent step towards the cessation of the nuclear arms race and, in particular, of its qualitative aspects. It could serve as an important measure for the non-proliferation of nuclear weapons, both vertical and horizontal. It would have a major arms limitation impact in that it would make it difficult, if not impossible, to develop new designs of nuclear weapons and would also place constraints on the modification of existing weapon designs. The permanent cessation of all nuclear-weapon tests has long been sought by the world community and its achievement would be an event of great international significance

Limits to the Recognizability of Flaws in Non-Destructive Testing Steam-Generator Tubes for Nuclear-Power Plants

International Nuclear Information System (INIS)

Kuhlmann, A.; Adamsky, F.-J.

1965-01-01

In the Federal Republic of Germany there are nuclear reactors under construction with steam generators inside the reactor pressure-vessel. As a result design repairs of steam- generator tubes are very difficult and cause large shut-down times of the nuclear-power plant. It is known that numerous troubles in operating conventional power plants are results of steam-generator tube damages. Because of the high total costs of these reactors it. is necessary to construct the steam generators especially in such a manner that the load factor of the power plant is as high as possible. The Technischer Überwachungs-Verein Rheinland was charged to supervise and to test fabrication and construction of the steam generators to see that this part of the plant was as free of defects as possible. The experience gained during this work is of interest for manufacture and construction of steam generators for nuclear-power plants in general. This paper deals with the efficiency limits of non-destructive testing steam-generator tubes. The following tests performed will be discussed in detail: (a) Automatic ultrasonic testing of the straight tubes in the production facility; (b) Combined ultrasonic and radiographic testing of the bent tubes and tube weldings; (c) Other non-destructive tests. (author) [fr

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

TRAC-P validation test matrix. Revision 1.0

International Nuclear Information System (INIS)

Hughes, E.D.; Boyack, B.E.

1997-01-01

This document briefly describes the elements of the Nuclear Regulatory Commission's (NRC's) software quality assurance program leading to software (code) qualification and identifies a test matrix for qualifying Transient Reactor Analysis Code (TRAC)-Pressurized Water Reactor Version (-P), or TRAC-P, to the NRC's software quality assurance requirements. Code qualification is the outcome of several software life-cycle activities, specifically, (1) Requirements Definition, (2) Design, (3) Implementation, and (4) Qualification Testing. The major objective of this document is to define the TRAC-P Qualification Testing effort

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)

The NPT and nuclear testing

International Nuclear Information System (INIS)

Howlett, D.; Simpson, J.

1992-01-01

One of the oldest unachieved aims of international nuclear disarmament and arms limitation negotiations is a Comprehensive Test Ban Treaty (CTBT). The history of the international negotiations, their outcomes and the consequences of Test Ban for the nuclear arsenals of the nuclear weapons states is discussed. The linkage between a CTBT and the Non-Proliferation Treaty is examined. Two strategies for moving towards a CTBT are compared; one a direct one, the other an incremental route. Both have several alternatives which are considered. (UK)

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)

Experience with performance based training of nuclear criticality safety engineers

International Nuclear Information System (INIS)

Taylor, R.G.

1993-01-01

For non-reactor nuclear facilities, the U.S. Department of Energy (DOE) does not require that nuclear criticality safety engineers demonstrate qualification for their job. It is likely, however, that more formalism will be required in the future. Current DOE requirements for those positions which do have to demonstrate qualification indicate that qualification should be achieved by using a systematic approach such as performance based training (PBT). Assuming that PBT would be an acceptable mechanism for nuclear criticality safety engineer training in a more formal environment, a site-specific analysis of the nuclear criticality safety engineer job was performed. Based on this analysis, classes are being developed and delivered to a target audience of newer nuclear criticality safety engineers. Because current interest is in developing training for selected aspects of the nuclear criticality safety engineer job, the analysis is incompletely developed in some areas

Round Robin Test for Performance Demonstration System of Ultrasound Examination Personnel in Nuclear Power Plants

International Nuclear Information System (INIS)

Kim, Young Ho; Yang, Seung Han; Kim, Yong Sik; Yoon, Byung Sik; Lee, Hee Jong

2005-01-01

Ultrasound testing performance during in-service inspection for the main components of NPPs is strongly affected by each examination person. Therefore, ASME established a more strict qualification requirement in Sec. XI Appendix VIII for the ultrasound testing personnel in nuclear power plants. The Korean Performance Demonstration (KPD) System according to the ASME code for the ultrasonic testing personnel, equipments, and procedures to apply to the Class 1 and 2 piping ultrasound examination of nuclear power plants in Korea was established. And a round robin test was conducted in order to verify the effectiveness of PD method by comparing the examination results from the method of Performance Demonstration (PD) and a traditional ASME code dB-drop method. The round robin test shows that the reliability of the PD method is better than that of the dB-drop method. As a result, application of the PD method to the in-service inspection of the nuclear power plants will improve the performance of ultrasound testing

Seismic analysis and testing of nuclear power plants

International Nuclear Information System (INIS)

1979-01-01

The following subjects are discussed in this guide: General Recommendations for seismic classification, loading combinations and allowable limits; seismic analysis methods; implications for seismic design; seismic testing and qualification; seismic instrumentation; modelling techniques; material property characterization; seismic response of soil deposits and earth structures; liquefaction and ground failure; slope stability; sloshing effects in water pools; qualification testing by means of the transport vehicle

Analysis of factors affecting the LOCA test quality

International Nuclear Information System (INIS)

Wang Lu

2008-01-01

Localization of nuclear safety-related equipment has become an important way of nuclear power development in China. To meet this demand, the competence should be promoted in the following two areas, one is to develop the capability of R and D and manufacturing of nuclear safety-related equipment, the other is to implement equipment qualification according to relevant codes and standards. As LOCA test is one of the most important parts in the qualification test of nuclear safety-related equipment, the main factors related with the quality of the LOCA test are analyzed in this paper, and this may be a reference to improve the skills in designing, constructing and operating LOCA test devices. (authors)

TRAC-P validation test matrix. Revision 1.0

Energy Technology Data Exchange (ETDEWEB)

Hughes, E.D.; Boyack, B.E.

1997-09-05

This document briefly describes the elements of the Nuclear Regulatory Commission`s (NRC`s) software quality assurance program leading to software (code) qualification and identifies a test matrix for qualifying Transient Reactor Analysis Code (TRAC)-Pressurized Water Reactor Version (-P), or TRAC-P, to the NRC`s software quality assurance requirements. Code qualification is the outcome of several software life-cycle activities, specifically, (1) Requirements Definition, (2) Design, (3) Implementation, and (4) Qualification Testing. The major objective of this document is to define the TRAC-P Qualification Testing effort.

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

International Nuclear Information System (INIS)

1985-01-01

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

Tests of qualification of national components of nuclear power plants under design basis accident

International Nuclear Information System (INIS)

Mesquita, A.Z.

1990-01-01

With the purpose of qualifying national components of nuclear power plants, whose working must be maintained during and after an accident, the Thermohydraulic Division of CDTN have done tests to check the equipment stability, under Design Basis Accident conditions. Until this moment, the following components were tested: electrical junction boxes (connectors); coating systems for wall, inside cover and steel containment; hydraulics components of personnel and equipment airlock. This work describes the test instalation, the tests performed and its results. The components tested, in a general way, fulfil the specified requirements. (author) [pt

Current developments in mechanized non-destructive testing in nuclear power plants; Aktuelle Entwicklungen bei mechanisierten, zerstoerungsfreien Pruefungen in Kernkraftwerken

Energy Technology Data Exchange (ETDEWEB)

Zeilinger, R. [intelligeNDT System und Services GmbH und Co. KG, Erlangen (Germany)

2008-01-15

Nuclear power plants require frequent in-service activities to be carried out conscientiously in areas potentially hazardous to human operators (because of the associated radiation exposure), such as non-destructive testing of pressurized components of the steam system. Locations to be inspected in this way include the reactor pressure vessel, core internals, steam generators, pressurizers, and pipes. The codes to be used as a basis of these inspections demand high absolute positioning and repeating accuracy. These requirements can be met by mechanized test procedures. Accordingly, many new applications of, mostly mobile, robots have been developed over the past few years. The innovative control and sensor systems for stationary and mobile robots now on the market offer a potential for economic application in a large number of new areas in inspection, maintenance and service in nuclear power plants. More progress in this area is expected for the near future. Areva NP founded the new NDT Center, NETEC (Non-destructive Examination Technical Center), as a global technical center for non-destructive materials testing. NETEC is to advance research and development of all basic NDT technologies, robotics included. For many years, intelligeNDT has offered solutions and products for a variety of inspection and testing purposes and locations in nuclear power plants and is involved in continuous further development of the experience collected in nuclear power plants on the spot. (orig.)

IEEE Std 383-1974: IEEE standard for type test of Class IE electric cables, field splices, and connections for nuclear power generating stations

International Nuclear Information System (INIS)

Anon.

1992-01-01

This standard provides direction for establishing type tests which may be used in qualifying Class 1E electric cables, field splices, and other connections for service in nuclear power generating stations. General guidelines for qualifications are given in IEEE Std 323-1974, Standard for Qualifying Class IE Electric Equipment for Nuclear Power Generating Stations. Categories of cables covered are those used for power control and instrumentation services. Though intended primarily to pertain to cable for field installation, this guide may also be used for the qualification of internal wiring of manufactured devices. This guide does not cover cables for service within the reactor vessel

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.

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)

Testing and qualification of confidence in statistical procedures

Energy Technology Data Exchange (ETDEWEB)

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

2014-07-01

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

Seismic qualification of safety class components in non-reactor nuclear facilities at Hanford site

International Nuclear Information System (INIS)

Ocoma, E.C.

1989-01-01

This paper presents the methods used during the walkdowns to compile as-built structural information to seismically qualify or verify the seismic adequacy of safety class components in the Plutonium Finishing Plant complex. The Plutonium finishing Plant is a non-reactor nuclear facility built during the 1950's and was designed to the Uniform Building Code criteria for both seismic and wind events. This facility is located at the US Department of Energy Hanford Site near Richland, Washington

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

International Nuclear Information System (INIS)

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

1993-01-01

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

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.

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

Energy Technology Data Exchange (ETDEWEB)

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

2004-07-01

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

Nuclear non-proliferation

International Nuclear Information System (INIS)

Anon.

1984-01-01

DOE's nuclear non-proliferation responsibilities are defined by the provisions of the Atomic Energy Act of 1954, as amended, and of the Nuclear Non-Proliferation Act of 1978 (NNPA). The Department's major responsibilities in this area are to: (1) provide technical assistance to the Department of State in negotiating agreements for civil cooperation in the peaceful uses of nuclear energy with other countries and international organizations; (2) join with other agencies to reach executive branch judgments with respect to the issuance of export licenses by the Nuclear Regulatory Commission; (3) be responsible for processing subsequent arrangements with other agencies as required by the Nuclear Non-Proliferation Act; (4) control the distribution of special nuclear materials, components, equipment, and nuclear technology exports; (5) participate in bilateral and multilateral cooperation with foreign governments and organizations to promote the peaceful uses of nuclear energy; and (6) act as a primary technical resource with respect to US participation in the International Atomic Energy Agency

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 tests for ITER TF conductors in SULTAN

International Nuclear Information System (INIS)

Bruzzone, P.; Stepanov, B.; Wesche, R.

2009-01-01

From February 2007 to May 2008, 18 short length conductor sections have been tested in SULTAN for design verification and manufacturer qualification of the ITER Toroidal Field (TF) conductor. The test program is focussed on the current sharing temperature, T cs , at the nominal operating conditions, 68 kA current and 11.15 T effective field, which can be fully reproduced in the SULTAN test facility. A broad range of results was observed, with over 2 K difference among the T cs of the conductors. In average, the results are poorer compared to the potential performance estimated from the strand scaling law. The key parameters to mitigate the degradation are not yet clearly identified. The experimental challenges to test conductors with performance degradation are highlighted, including enhanced instrumentation sets, the application of gas flow calorimetry to sense the current sharing power and the post-processing of voltage data to cancel the transverse potential across the cable. The updated schedule of the tests in SULTAN is presented with the short-term action plan for conductor test.

Guide to good practices for the selection, training, and qualification of shift technical advisors

Energy Technology Data Exchange (ETDEWEB)

1993-02-01

The DOE Guide to Good Practices For The Selection, Training, and Qualification of Shift Technical Advisors can be used by any DOE nuclear facility that has implemented the shift technical advisor position. DOE Order 5480-20, ``Personnel Selection, Qualification, Training, and Staffing Requirements at DOE Reactor and Non-Reactor Nuclear Facilities,`` states that only Category A reactors must use shift technical advisor position. However, many DOE nuclear facilities have implemented the shift technical advisor position to provide independent on-shift technical advice and counsel to the shift operating personnel to help determine cause and mitigation of facility accidents. Those DOE nuclear facilities that have implemented or are going to implement the shift technical advisor position will find this guide useful. This guide addresses areas that may be covered by other training programs. In these cases, it is unnecessary (and undesirable) to duplicate these areas in the STA training program as long as the specific skills and knowledge essential for STAs are addressed. The guide is presented based on the premise that the trainee has not completed any facility-specific training other than general employee training.

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

Qualifying program on Non-Destructive Testing, Visual Inspection of the welding (level 2)

International Nuclear Information System (INIS)

Shafee, M. A.

2011-01-01

Nondestructive testing is a wide group of analysis technique used in science and industry to evaluate the properties of a material, component or system without causing damage. Common Non-Destructive Testing methods include ultrasonic, magnetic-particle, liquid penetrate, radiographic, visual inspection and eddy-current testing. AAEA put the new book of the Non-Destructive Testing publication series that focused on Q ualifying program on Non-Destructive Testing, visual inspection of welding-level 2 . This book was done in accordance with the Arab standard certification of Non-Destructive Testing (ARAB-NDT-CERT-002) which is agreeing with the ISO-9712 (2005) and IAEA- TEC-DOC-487. It includes twenty one chapters dealing with engineering materials used in industry, the mechanical behavior of metals, metal forming equipments, welding, metallurgy, testing of welds, introduction to Non-Destructive Testing, defects in metals, welding defects and discontinuities, introduction to visual inspection theory, properties and tools of visual testing, visual testing, quality control regulations, standards, codes and specifications, procedures of welding inspections, responsibility of welding test inspector, qualification of Non-Destructive Testing inspector and health safety during working.

Evaluating Russian space nuclear reactor technology for United States applications

International Nuclear Information System (INIS)

Polansky, G.F.; Schmidt, G.L.; Voss, S.S.; Reynolds, E.L.

1994-01-01

Space nuclear power and nuclear electric propulsion are considered important technologies for planetary exploration, as well as selected earth orbit applications. The Nuclear Electric Propulsion Space Test Program (NEPSTP) was intended to provide an early flight demonstration of these technologies at relatively low cost through extensive use of existing Russian technology. The key element of Russian technology employed in the program was the Topaz II reactor. Refocusing of the activities of the Ballistic Missile Defense Organization (BMDO), combined with budgetary pressures, forced the cancellation of the NEPSTP at the end of the 1993 fiscal year. The NEPSTP was faced with many unique flight qualification issues. In general, the launch of a spacecraft employing a nuclear reactor power system complicates many spacecraft qualification activities. However, the NEPSTP activities were further complicated because the reactor power system was a Russian design. Therefore, this program considered not only the unique flight qualification issues associated with space nuclear power, but also with differences between Russian and United States flight qualification procedures. This paper presents an overview of the NEPSTP. The program goals, the proposed mission, the spacecraft, and the Topaz II space nuclear power system are described. The subject of flight qualification is examined and the inherent difficulties of qualifying a space reactor are described. The differences between United States and Russian flight qualification procedures are explored. A plan is then described that was developed to determine an appropriate flight qualification program for the Topaz II reactor to support a possible NEPSTP launch

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

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.

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

Energy Technology Data Exchange (ETDEWEB)

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

1985-11-01

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

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

International Nuclear Information System (INIS)

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

1985-11-01

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

ELIMINATION OF THE CHARACTERIZATION OF DWPF POUR STREAM SAMPLE AND THE GLASS FABRICATION AND TESTING OF THE DWPF SLUDGE BATCH QUALIFICATION SAMPLE

Energy Technology Data Exchange (ETDEWEB)

Amoroso, J.; Peeler, D.; Edwards, T.

2012-05-11

A recommendation to eliminate all characterization of pour stream glass samples and the glass fabrication and Product Consistency Test (PCT) of the sludge batch qualification sample was made by a Six-Sigma team chartered to eliminate non-value-added activities for the Defense Waste Processing Facility (DWPF) sludge batch qualification program and is documented in the report SS-PIP-2006-00030. That recommendation was supported through a technical data review by the Savannah River National Laboratory (SRNL) and is documented in the memorandums SRNL-PSE-2007-00079 and SRNL-PSE-2007-00080. At the time of writing those memorandums, the DWPF was processing sludge-only waste but, has since transitioned to a coupled operation (sludge and salt). The SRNL was recently tasked to perform a similar data review relevant to coupled operations and re-evaluate the previous recommendations. This report evaluates the validity of eliminating the characterization of pour stream glass samples and the glass fabrication and Product Consistency Test (PCT) of the sludge batch qualification samples based on sludge-only and coupled operations. The pour stream sample has confirmed the DWPF's ability to produce an acceptable waste form from Slurry Mix Evaporator (SME) blending and product composition/durability predictions for the previous sixteen years but, ultimately the pour stream analysis has added minimal value to the DWPF's waste qualification strategy. Similarly, the information gained from the glass fabrication and PCT of the sludge batch qualification sample was determined to add minimal value to the waste qualification strategy since that sample is routinely not representative of the waste composition ultimately processed at the DWPF due to blending and salt processing considerations. Moreover, the qualification process has repeatedly confirmed minimal differences in glass behavior from actual radioactive waste to glasses fabricated from simulants or batch chemicals. In

Elimination Of The Characterization Of DWPF Pour Stream Sample And The Glass Fabrication And Testing Of The DWPF Sludge Batch Qualification Sample

International Nuclear Information System (INIS)

Amoroso, J.; Peeler, D.; Edwards, T.

2012-01-01

A recommendation to eliminate all characterization of pour stream glass samples and the glass fabrication and Product Consistency Test (PCT) of the sludge batch qualification sample was made by a Six-Sigma team chartered to eliminate non-value-added activities for the Defense Waste Processing Facility (DWPF) sludge batch qualification program and is documented in the report SS-PIP-2006-00030. That recommendation was supported through a technical data review by the Savannah River National Laboratory (SRNL) and is documented in the memorandums SRNL-PSE-2007-00079 and SRNL-PSE-2007-00080. At the time of writing those memorandums, the DWPF was processing sludge-only waste but, has since transitioned to a coupled operation (sludge and salt). The SRNL was recently tasked to perform a similar data review relevant to coupled operations and re-evaluate the previous recommendations. This report evaluates the validity of eliminating the characterization of pour stream glass samples and the glass fabrication and Product Consistency Test (PCT) of the sludge batch qualification samples based on sludge-only and coupled operations. The pour stream sample has confirmed the DWPF's ability to produce an acceptable waste form from Slurry Mix Evaporator (SME) blending and product composition/durability predictions for the previous sixteen years but, ultimately the pour stream analysis has added minimal value to the DWPF's waste qualification strategy. Similarly, the information gained from the glass fabrication and PCT of the sludge batch qualification sample was determined to add minimal value to the waste qualification strategy since that sample is routinely not representative of the waste composition ultimately processed at the DWPF due to blending and salt processing considerations. Moreover, the qualification process has repeatedly confirmed minimal differences in glass behavior from actual radioactive waste to glasses fabricated from simulants or batch chemicals. In contrast, the

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)

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

International Nuclear Information System (INIS)

1978-06-01

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

Australia - a nuclear weapons testing ground

International Nuclear Information System (INIS)

Dobbs, Michael.

1993-01-01

Between 1952 and 1958 Britain conducted five separate nuclear weapons trials in Australia. Australia had the uninhabited wide open spaces and the facilities which such tests need and Britain was able to use its special relationship with Australia to get agreement to conduct atomic tests in Australia and establish a permanent test site at Maralinga. Other non-nuclear tests were conducted between 1953-1963. The story of Britain's involvement in atomic weapons testing in Australia is told through its postal history. Both official and private covers are used to show how the postal communications were established and maintained throughout the test years. (UK)

Reliability Testing Beyond Qualification as a Key Component in Photovoltaic's Progress Toward Grid Parity: Preprint

Energy Technology Data Exchange (ETDEWEB)

Wohlgemuth, J. H.; Kurtz, S.

2011-02-01

This paper discusses why it is necessary for new lower cost PV modules to be tested using a reliability test sequence that goes beyond the Qualification test sequence now utilized for modules. Today most PV modules are warranted for 25 years, but the Qualification Test Sequence does not test for 25-year life. There is no accepted test protocol to validate a 25-year lifetime. This paper recommends the use of long term accelerated testing to compare now designs directly with older designs that have achieved long lifetimes in outdoor exposure. If the new designs do as well or better than the older ones, then it is likely that they will survive an equivalent length of time in the field.

Dynamic performance of concrete undercut anchors for Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

Mahrenholtz, Christoph, E-mail: christoph@mahrenholtz.net; Eligehausen, Rolf

2013-12-15

Graphical abstract: - Highlights: • Behavior of undercut anchors under dynamic actions simulating earthquakes. • First high frequency load and crack cycling tests on installed concrete anchors ever. • Comprehensive review of anchor qualification for Nuclear Power Plants. - Abstract: Post-installed anchors are widely used for structural and nonstructural connections to concrete. In many countries, concrete anchors used for Nuclear Power Plants have to be qualified to ensure reliable behavior even under extreme conditions. The tests required for qualification of concrete anchors are carried out at quasi-static loading rates well below the rates to be expected for dynamic actions deriving from earthquakes, airplane impacts or explosions. To investigate potentially beneficial effects of high loading rates and cycling frequencies, performance tests on installed undercut anchors were conducted. After introductory notes on anchor technology and a comprehensive literature review, this paper discusses the qualification of anchors for Nuclear Power Plants and the testing carried out to quantify experimentally the effects of dynamic actions on the load–displacement behavior of undercut anchors.

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...

Simulating Large Area, High Intensity AM0 Illumination – Test Results from Bepicolombo and Solar Orbiter Qualification

Directory of Open Access Journals (Sweden)

Oberhüttinger C.

2017-01-01

Specifically, the following topics will be treated. Different methods like electrical performance, thermo-optical and external quantum efficiency measurements have been used to characterize the behaviour of the solar cells after illumination under these conditions. A special focus has been put on the electrical performance. A comparison to other solar cell qualification tests under solely UV radiation has been undertaken. The results have also been compared to a theoretical model. However, the paper will not cover only characterization results but will also give some insight in challenges experienced during the test execution itself. Deviating from other solar cell qualification tests, a representatively equipped photovoltaic assembly on carbon fibre reinforced cyanate has also been included. On these coupon segments, solar cell assemblies connected to shunt diodes and placed next to optical surface reflectors have been exposed to AM0 illumination to qualify the solar cells including their surroundings which therefore covers also contamination effects. Last but not least, first results from the Solar Orbiter qualification are presented. This test with additional 1000 hours and increased intensity has been completed recently.

Training and qualification program for nuclear criticality safety technical staff

International Nuclear Information System (INIS)

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

1996-01-01

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

Qualification Tests of Micro-camera Modules for Space Applications

Science.gov (United States)

Kimura, Shinichi; Miyasaka, Akira

Visual capability is very important for space-based activities, for which small, low-cost space cameras are desired. Although cameras for terrestrial applications are continually being improved, little progress has been made on cameras used in space, which must be extremely robust to withstand harsh environments. This study focuses on commercial off-the-shelf (COTS) CMOS digital cameras because they are very small and are based on an established mass-market technology. Radiation and ultrahigh-vacuum tests were conducted on a small COTS camera that weighs less than 100 mg (including optics). This paper presents the results of the qualification tests for COTS cameras and for a small, low-cost COTS-based space camera.

Implementing nuclear non-proliferation in Finland. Regulatory control, international cooperation and the Comprehensive Nuclear-Test-Ban Treaty. Annual report 2011

Energy Technology Data Exchange (ETDEWEB)

Okko, O [ed.

2012-07-01

The regulatory control of nuclear materials (i.e. nuclear safeguards) is a prerequisite for the peaceful use of nuclear energy in Finland. Safeguards are required for Finland to comply with international agreements on nuclear non-proliferation - mainly the Non-Proliferation Treaty (NPT). This regulatory control is exercised by the Nuclear Materials Section of the Finnish Radiation and Nuclear Safety Authority (STUK). The results of STUK's nuclear safeguards inspection activities in 2011 continued to demonstrate that the Finnish licence holders take good care of their nuclear materials. There were no indications of undeclared nuclear materials or activities and the inspected materials and activities were in accordance with the licence holders' declarations.

Nuclear non-proliferation

International Nuclear Information System (INIS)

Anon.

1990-01-01

This patent describes the treaty on the non-proliferation of nuclear weapons which is the corner-stone of an international non-proliferation regime which has grown to embrace the overwhelming majority of countries in the world in the period since the Treaty. The other elements of the regime include, first of all, the safeguards system of IAEA-which operates to prevent the diversion of nuclear materials to military or other prohibited activities and must be accepted by all non-nuclear-weapon parties to the Treaty and, secondly, the Antarctic Treaty, the Treaty for the Prohibition of Nuclear Weapons in Latin America (Treaty of Tlatelolco) and the south Pacific Nuclear Free zone Treaty (Treaty of Rarotonga)-which serve to extend the regime geographically. The last two Treaties require safeguards agreements with IAEA. In addition, the Treaty of Tlatelolco contains provisions establishing the agency for the Prohibition of Nuclear Weapons in Latin America and the Caribbean to ensure compliance

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

International Nuclear Information System (INIS)

Skala, Z.; Vit, J.

2003-01-01

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

Nuclear stress test

Science.gov (United States)

... Persantine stress test; Thallium stress test; Stress test - nuclear; Adenosine stress test; Regadenoson stress test; CAD - nuclear stress; Coronary artery disease - nuclear stress; Angina - nuclear ...

Non-power application of nuclear energy: Bangladesh perspective

International Nuclear Information System (INIS)

Naiyyum Choudhury

2002-01-01

Radiation technology offers a very wide scope for utilisation and commercial exploitation in various fields. All over the world, this non-power nuclear energy is being favourably considered for different applications like radiation processing of polymeric materials, non-destructive testing, nuclear and nuclear-related analytical techniques, radiation sterilization of medical products and human tissue allografts, preservation of food by controlling the physiological processes for extending shelf-life and eradication of microbial and insect pests, nuclear technology in agriculture and treatment of sewage sludge. Bangladesh Atomic Energy Commission has taken radiation processing programmes in a big way right from its inception. This paper describes the studies carried out by various research groups in Bangladesh Atomic Energy Commission in the planning and development of non-power nuclear technology for peaceful uses in the fields of food, agriculture, medicine, industry and environment. Both food preservation and medical sterilization of medical products are now being commercially carried out in the Gammatech facility as a joint venture company of BAEC and a private entrepreneur. Bangladesh is soon going to establish a full-fledged Tissue Bank to cater the needs of various tissue allografts for surgical replacement. Recently Government of Bangladesh has allocated US$ 1.00 million for strengthening of the Tissue Banking Laboratory. Application of nuclear techniques in agriculture is also quite intensive. BAEC has made quite a good research contribution on vulcanization of natural rubber latex, wood plastic composites, surface coating curing, polymer modification etc. Bangladesh has also made a very good progress in the fields of non-destructive testing, tracer technology, nuclear analytical techniques and nucleonic control. The impact of non-power nuclear energy in selected areas will no doubt be significant in coming years. (Author)

Implementing nuclear non-proliferation in Finland. Regulatory control, international cooperation and the Comprehensive Nuclear-Test-Ban Treaty. Annual report 2011

Energy Technology Data Exchange (ETDEWEB)

Okko, O. (ed.)

2012-07-01

The regulatory control of nuclear materials (i.e. nuclear safeguards) is a prerequisite for the peaceful use of nuclear energy in Finland. Safeguards are required for Finland to comply with international agreements on nuclear non-proliferation - mainly the Non-Proliferation Treaty (NPT). This regulatory control is exercised by the Nuclear Materials Section of the Finnish Radiation and Nuclear Safety Authority (STUK). The results of STUK's nuclear safeguards inspection activities in 2011 continued to demonstrate that the Finnish licence holders take good care of their nuclear materials. There were no indications of undeclared nuclear materials or activities and the inspected materials and activities were in accordance with the licence holders' declarations.

Experimental qualification of nuclear components

Energy Technology Data Exchange (ETDEWEB)

Alliot, P; Fronte, T; Genty, F [FRAMATOME - Cedex 16, Paris la Defense (France)

1988-07-01

In the process of showing the adequacy of the seismic design of French PWR reactor, Fermat has repeatedly used dynamic testing on actual nuclear reactor components both on site and in manufacturing shops. The objective and results of a few representative examples of this on-site experimental verification are presented in this paper: the experimental dynamic analysis of a manipulator crane; the investigation of the seismic behaviour of fuel storage racks equipped with aseismic bearing devices. Difficulties to select satisfactory testing methods are also discussed for the particular case of the electrical cabinets. (author)

Experimental qualification of nuclear components

International Nuclear Information System (INIS)

Alliot, P.; Fronte, T.; Genty, F.

1988-01-01

In the process of showing the adequacy of the seismic design of French PWR reactor, Fermat has repeatedly used dynamic testing on actual nuclear reactor components both on site and in manufacturing shops. The objective and results of a few representative examples of this on-site experimental verification are presented in this paper: the experimental dynamic analysis of a manipulator crane; the investigation of the seismic behaviour of fuel storage racks equipped with aseismic bearing devices. Difficulties to select satisfactory testing methods are also discussed for the particular case of the electrical cabinets. (author)

Qualification and application of nuclear reactor accident analysis code with the capability of internal assessment of uncertainty; Qualificacao e aplicacao de codigo de acidentes de reatores nucleares com capacidade interna de avaliacao de incerteza

Energy Technology Data Exchange (ETDEWEB)

Borges, Ronaldo Celem

2001-10-15

This thesis presents an independent qualification of the CIAU code ('Code with the capability of - Internal Assessment of Uncertainty') which is part of the internal uncertainty evaluation process with a thermal hydraulic system code on a realistic basis. This is done by combining the uncertainty methodology UMAE ('Uncertainty Methodology based on Accuracy Extrapolation') with the RELAP5/Mod3.2 code. This allows associating uncertainty band estimates with the results obtained by the realistic calculation of the code, meeting licensing requirements of safety analysis. The independent qualification is supported by simulations with RELAP5/Mod3.2 related to accident condition tests of LOBI experimental facility and to an event which has occurred in Angra 1 nuclear power plant, by comparison with measured results and by establishing uncertainty bands on safety parameter calculated time trends. These bands have indeed enveloped the measured trends. Results from this independent qualification of CIAU have allowed to ascertain the adequate application of a systematic realistic code procedure to analyse accidents with uncertainties incorporated in the results, although there is an evident need of extending the uncertainty data base. It has been verified that use of the code with this internal assessment of uncertainty is feasible in the design and license stages of a NPP. (author)

SRNL PHASE 1 Assessment Of The WTP Waste Qualification Program

International Nuclear Information System (INIS)

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

2012-01-01

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

Qualification of the WIMS lattice code, for the design, operation and accident analysis of nuclear reactors

International Nuclear Information System (INIS)

Lerner, A.M.

1996-01-01

A basic problem in nuclear reactor physics in that of the description of the neutron population behaviour in the multiplicative medium of a nuclear fuel. Due to the magnitude of the physical problem involved and the present degree of technological evolution regarding computing resources, of increasing complexity and possibilities, the calculation programs or codes have turned to be a basic auxiliary tool in reactor physics. In order to analyze the global problem, several aspects should be taken into consideration. The first aspect to be considered is that of the availability of the necessary nuclear data. The second one is the existence of a variety of methods and models to perform the calculations. The final phase for this kind of analysis is the qualification of the computing programs to be used, i.e. the verification of the validity domain of its nuclear data and the models involved. The last one is an essential phase, and in order to carry it on great variety of calculations are required, that will check the different aspects contained in the code. We here analyze the most important physical processes that take place in a nuclear reactor cell, and we consider the qualification of the lattice code WIMS, that calculates the neutronic parameters associated with such processes. Particular emphasis has been put in the application to natural uranium fuelled reactor, heavy water cooled and moderated, as the Argentinean power reactors now in operation. A wide set of experiments has been chosen: a.-Fresh fuel in zero-power experimental facilities and power reactors; b.-Irradiated fuel in both types of facilities; c.-Benchmark (prototype) experiments with loss of coolant. From the whole analysis it was concluded that for the research reactors, as well as for the heavy water moderated power reactors presently operating in our country, or those that could operate in a near future, the lattice code WIMS is reliable and produces results within the experimental values and

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

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.

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

International Nuclear Information System (INIS)

Chapman, O.J.V.

1996-01-01

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

Manual on training, qualification and certification of quality assurance personnel

International Nuclear Information System (INIS)

1986-01-01

The Manual is applicable to those participants in a nuclear power project who are associated with establishment and implementation of the various quality assurance (QA) programmes during the life cycle of the project. It provides examples of typical QA functions to be undertaken and the associated qualification requirements, training programmes, training techniques and methods of certification of personnel implementing these functions. The necessary qualification and training requirements and practices for QA personnel are dependent primarily on the functions or activities to be performed. The two main functions of the QA unit noted previously as (a) ensuring QA programme establishment and execution and (b) verifying that activities have been correctly performed have been found in practice to require different qualifications and training of personnel. Therefore, for the purpose of this Manual the QA personnel may be classified in two groups who perform: QA programmatic and evaluation functions; Inspection and test functions. These titles do not necessarily represent separate or individual organizational groups or units and may be composed of one or of several different organizations

Inspection qualification programme for VVER reactors and review of round robin test results

International Nuclear Information System (INIS)

Horacek, L.; Zdarek, J.

1998-01-01

Experience obtained, especially from in-service inspections of VVER 440-type reactor pressure vessels and from the Czech round test trials with international participation of ultrasonic teams, has highlighted the need for an in-service inspection qualification programme in the Czech Republic focused on NDT procedures, equipment and personnel. Recently, several national and international regional projects included in the PHARE programme (projects 4.1.2/93 and 1.02/94), briefly described, have been initiated. These projects are to cover step by step the programme of the in-service inspection qualification in view of technical justification as well as of practical assessment-performance demonstration-for all the main VVER-type primary circuit components. (orig.)

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

Energy Technology Data Exchange (ETDEWEB)

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

2013-07-01

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

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

Directory of Open Access Journals (Sweden)

William Marcos Muniz Menezes

2014-03-01

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

Environmental qualification program of electric equipment for Angra 1

Energy Technology Data Exchange (ETDEWEB)

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

2017-11-01

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

Environmental qualification program of electric equipment for Angra 1

International Nuclear Information System (INIS)

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

2017-01-01

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

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

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)

Recent experience with testing of parallel disc gate valves under accident flow conditions

International Nuclear Information System (INIS)

LaPointe, P.A.; Clayton, J.K.

1992-01-01

This paper presents the nuclear valve industry's latest and most extensive valve qualification test program experience. The test program includes a variety of 25 different gate and globe valves. All the test valves are power operated using either air, electric, or gas/hydraulic operators. The valves are categorized in size and pressure class so as to form a group of appropriate parent valve assemblies. Parent valve assembly qualification is used as the basis for qualification of candidate valve assemblies. The parent and candidate valve assemblies are representative of a nuclear plant's safety-related valve applications. The test program was performed in accordance with ANSI B16.41-1983 'Functional Qualification Requirements for Power Operated Active Valve Assemblies for Nuclear Power Plants.' The focus of this paper is on functional valve qualification test experience and specifically flow interruption testing to Annex G of the aforementioned test standard. Results of the flow test are summarized, including the coefficient of friction for each of the gate type valves reported. Information on valve size, pressure class, and actuator are given for all valves in the program. Although all valves performed extremely well, only selected test data are presented. The effects of the speed of operation and the effects of different fluid flow rates as they relate to the coefficient of friction between the valve disc and seat are discussed. The variation in the coefficient of friction based on other variables in the thrust equation, namely, differential pressure area is cited

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

Guide to good practices for training and qualification of instructors. DOE handbook

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-03-01

Purpose of this guide is to provide contractor training organizations with information that can be used to verify the adquacy and/or modify existing instructor training programs, or to develop new training programs. It contains good practices for the training and qualification of technical instructors and instructional technologists at DOE reactor and non-reactor nuclear facilities. It addresses the content of initial and continuing instructor training programs, evaluation of instructor training programs, and maintenance of instructor training records.

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

International Nuclear Information System (INIS)

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

2009-01-01

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

Off reactor testings. Technological engineering applicative research

International Nuclear Information System (INIS)

Doca, Cezar

2001-01-01

By the end of year 2000 over 400 nuclear electro-power units were operating world wide, summing up a 350,000 MW total capacity, with a total production of 2,300 TWh, representing 16% of the world's electricity production. Other 36 units, totalizing 28,000 MW, were in construction, while a manifest orientation towards nuclear power development was observed in principal Asian countries like China, India, Japan and Korea. In the same world's trend one find also Romania, the Cernavoda NPP Unit 1 generating electrical energy into the national system beginning with 2 December 1996. Recently, the commercial contract was completed for finishing the Cernavoda NPP Unit 2 and launching it into operation by the end of year 2004. An important role in developing the activity of research and technological engineering, as technical support for manufacturing the CANDU type nuclear fuel and supplying with equipment the Cernavoda units, was played by the Division 7 TAR of the INR Pitesti. Qualification testings were conducted for: - off-reactor CANDU type nuclear fuel; - FARE tools, pressure regulators, explosion proof panels; channel shutting, as well as functional testing for spare pushing facility as a first step in the frame of the qualification tests for the charging/discharging machine (MID) 4 and 5 endings. Testing facilities are described, as well as high pressure hot/cool loops, measuring chains, all of them fulfilling the requirements of quality assurance. The nuclear fuel off-reactor tests were carried out to determine: strength; endurance; impact, pressure fall and wear resistance. For Cernavoda NPP equipment testings were carried out for: the explosion proof panels, pressure regulators, behaviour to vibration and wear of the steam generation tubings, effects of vibration upon different electronic component, channel shutting (for Cernavoda Unit 2), MID operating at 300 and 500 cycles. A number of R and D programs were conducted in the frame of division 7 TAR of INR

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

Operational experience, availability and reliability of nuclear power plants

International Nuclear Information System (INIS)

Kueffer, K.

1980-01-01

This lecture - presents a survey on nuclear power production and plant performance in the Western World covering all reactor types and light-water reactors in particular and discusses key parameters such as load factors and non-availability analysis. - outlines the main reasons for the reliable performance of Swiss nuclear power plants - quality equipment - operator qualification and training - engineering know how on site - maintenance philosophy and outage planning - information system and feedback of experience - explains the management functions as applied at the Beznau Nuclear Power Station to ensure high power productivity and reliability - improvement - a feedback control system - analysis of production losses - optimization in shut-down planning - minimizing disturbances during plant operation - optimizing personnel qualification and efficiency. (orig.)

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)

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

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.

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

Testing non-rigid registration of nuclear medicine data using synthetic derived SPECT images

International Nuclear Information System (INIS)

Todd-Pokropek, A.

2002-01-01

Aim: Non-rigid registration is needed to build atlas data to make statistical tests of significance of uptake in nuclear medicine (NM). Non-rigid registration is much more difficult than rigid registration to validate since some kind of matching function must be defined throughout the volume being registered, and no suitable gold standards exist. The aim here has been to assess non-rigid methods of registration and deformation for NM to NM and NM to MRI data. An additional aim has been to derive good synthetic SPECT images from other NM and MRI data to be used after as reference standards. Material and Methods: Phantom and patient test images have been acquired for both NM and MRI, which are then used to generate projections, where the characteristics of the images are modified to change both signal and noise properties. These derived images are different in character but perfectly registered with the original data, and can then be deformed in a known manner. The registration algorithm is then run backwards to re-register the modified deformed data with the original images. A technique has been developed to assess the vector fields of the original deformation to the reverse non-rigid registration field. Results: The main purpose of this paper is to describe a methodology for optimising algorithms, not to develop the algorithms themselves. Two different algorithms based on optic flow and thin plate spline interpolation have been intercompared and in particular the constraints imposed tested. Considerable differences in matching can be observed in different regions for example edge and centre of brain. Conclusions: Quadratic distance between known makers is a bad estimate to use to assess non-rigid registration. A robust statistic has been developed which can be used to optimise non-rigid algorithms based on the use of synthetic SPECT reference datasets. While the task being tested is simpler than the real clinical task, it is the first essential step in the

Qualification, certification and training of quality assurance personnel

International Nuclear Information System (INIS)

Ribeiro da Costa, J.

1982-01-01

The qualification and certification of technical personnel for activities related to nuclear quality is one of the most critical problems in developing countries which use nuclear power for peaceful purposes. A careful analysis of industrial quality levels is required in order to determine existing weaknesses, to correct deviations and to regulate quality-related activities so that nuclear power programmes can be implemented with no difficulties other than those inherent in the very complexity of nuclear technology. In this connection, indoctrination, training and qualification of technical personnel, in line with the requirements to quality assurance (QA), are tasks which must be undertaken right at the outset, taking into account the country's stage of technological development, its objectives and the necessity to increase its direct participation in QA activities in the shortest possible time. The paper shows how the problem was approached in Brazil, beginning with an analysis of the situation of industry in this field, the evolution of QA training programmes through several stages, leading to systematic training in the field of nuclear quality and, finally, the introduction of training in the more specific and sophisticated field of nuclear reliability. (author)

A uniform approach for on-site training and qualification of health physics technicians

International Nuclear Information System (INIS)

Till, J.E.

1977-01-01

Estimates show that in the U.S. approx. 75% of the health physics technicians received their training through courses offered by their employer. The quality and the extent of this training vary considerably among nuclear facilities. This paper describes a uniform approach for on-site training and qualification of health physics technicians applicable to all nuclear facilities. The program consists of four levels of qualification: Health Physics Technician Trainee, Technician I, Technician II and Senior Technician. The training is divided into modules that are composed of formal lectures, practical factors, experience, and a comprehensive examination. The minimum time required from hiring of inexperienced trainees to qualification as Senior Technicians is approx. 24 months. A qualification guide lists each step a technician must complete in the training program and provides documentation which facilitates audits by internal and external groups. Although items in the program would differ between facilities, the program provides specific titles for technicians, based on their training and experience, which would be applicable throughout the nuclear industry. (author)

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

International Nuclear Information System (INIS)

1977-12-01

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

Ministerial Decree of 1 March 1973. Approval of the models of documents concerning the professional qualifications for the management and operation of nuclear installations

International Nuclear Information System (INIS)

1973-01-01

This Decree by the Ministry of Labour implements Section 36 of DPR No. 1450 of 30 December 1970 (Regulations concerning the qualifications for technical operation of nuclear installations) made under Act no. 1860. (NEA) [fr

International guidance on the qualifications of nuclear power plant operations personnel

International Nuclear Information System (INIS)

Csik, B.J.

1984-01-01

Nuclear power plant operation and maintenance as well as training of operations personnel are activities where a large amount of experience is available. Though it would seem that the status of a well-established practice, requiring constant attention but no major efforts directed towards improvements, should have been reached, this is not the case. Currently, upgrading of the qualification requirements and training procedures of nuclear power plant operations personnel is a major issue and substantial efforts are being expended to this effect. The availability of international guidance in this field is perceived to be of benefit to all; therefore the Agency has undertaken to develop such guidance. In addition to earlier publications, a guidebook on this subject area is being prepared. Important problems and current issues have been identified and these are commented upon in the present paper. The specific topics referred to include: the role of the operating organization and the regulatory body; organizational aspects; staffing requirements; competence requirements for personnel; establishment and verification of competence; and personnel management. It is recognized that developing international guidance is a difficult and delicate task, especially when it is intended to go beyond stating the obvious and expressing generalities which are certain to meet a general consensus. (author)

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)

A study on the chemical cleaning process and its qualification test by eddy current testing

Energy Technology Data Exchange (ETDEWEB)

Shin, Ki Seok; Cheon, Keun Young; Nam, Min Woo [KHNP Central Research Institute, Daejeon (Korea, Republic of); Min, Kyoung Mahn [UMI Inc., Daejeon (Korea, Republic of)

2013-12-15

Steam Generator (SG) tube, as a barrier isolating the primary coolant system from the secondary side of nuclear power plants (NPP), must maintain the structural integrity for the public safety and their efficient power generation. So, SG tubes are subject to the periodic examination and the repairs if needed so that any defective tubes are not in service. Recently, corrosion related degradations were detected in the tubes of the domestic OPR-1000 NPP, as a form of axially oriented outer diameter stress corrosion cracking (ODSCC). According to the studies on the factors causing the heat fouling as well as developing corrosion cracking, densely scaled deposits on the secondary side of the SG tubes are mainly known to be problematic causing the adverse impacts against the soundness of the SG tubes. Therefore, the processes of various cleaning methods efficiently to dissolve and remove the deposits have been applied as well as it is imperative to maintain the structural integrity of the tubes after exposing to the cleaning agent. So qualification test (QT) should be carried out to assess the perfection of the chemical cleaning and QT is to apply the processes and to do ECT. In this paper, the chemical cleaning processes to dissolve and remove the scaled deposits are introduced and results of ECT on the artificial crack specimens to determine the effectiveness of those processes are represented.

On-the-job training and qualification of nuclear power plant personnel. Proceedings of a specialists' meeting. Working material

International Nuclear Information System (INIS)

1996-01-01

The topic of this meeting , on-the-job training, was selected by the International Working Group on Training and Qualification of Nuclear Power Plant Personnel, during their most recent meeting in 1994. This International Working Group is made up of representatives from all Member States who have operating nuclear power plants. This Group felt that there was a need to provide a forum for exchange of information among specialists from Member States on the topic of on-the-job training, and further that the Agency should publish the proceedings of this meeting for the use of those specialists who were not able to attend. Refs, figs, tabs

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.

Non-destructive testing. V. 2

International Nuclear Information System (INIS)

Farley, J.M.; Nichols, R.W.

1988-01-01

The book entitled 'Non-destructive Testing' Volume 2, contains the proceedings of the fourth European Conference, organized by the British Institute of Non-Destructive Testing and held in London, September 1987. The volume contains seven chapters which examine the reliability of NDT, the economics of NDT and the use of NDT in:- civil engineering; oil, gas, coal and petrochemical industries; iron and steel industries; aerospace industry; and the nuclear and electricity supply industries. The seven chapters contain 78 papers, of which 19 are selected for INIS and indexed separately. (U.K.)

Qualification standard for photovoltaic concentrator modules

Energy Technology Data Exchange (ETDEWEB)

McConnell, R.; Kurtz, S.; Bottenberg, W. R.; Hammond, R.; Jochums, S. W.; McDanal, A. J.; Roubideaux, D.; Whitaker, C.; Wohlgemuth, J.

2000-05-05

The paper describes a proposed qualification standard for photovoltaic concentrator modules. The standard's purpose is to provide stress tests and procedures to identify any component weakness in photovoltaic concentrator modules intended for power generation applications. If no weaknesses are identified during qualification, both the manufacturer and the customer can expect a more reliable product. The qualification test program for the standard includes thermal cycles, humidity-freeze cycles, water spray, off-axis beam damage, hail impact, hot-spot endurance, as well as electrical tests for performance, ground continuity, isolation, wet insulation resistance, and bypass diodes. Because concentrator module performance can not be verified using solar simulator and reference cell procedures suitable for flat-plate modules, the standard specifies an outdoor I-V test analysis allowing a performance comparison before and after a test procedure. Two options to this complex analysis are the use of a reference concentrator module for side-by-side outdoor comparison with modules undergoing various tests and a dark I-V performance check.

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

Energy Technology Data Exchange (ETDEWEB)

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

2011-10-01

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

Nuclear data needs for non-intrusive inspection

International Nuclear Information System (INIS)

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

2000-01-01

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

Nuclear data needs for non-intrusive inspection

International Nuclear Information System (INIS)

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

2001-01-01

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

Qualification of electronic components for use in nuclear power plants

International Nuclear Information System (INIS)

Zorrilla, J.; Antonaccio, E; Luraschi, C.; Rodriguez, F.; Ranalli, J.; Ponce, M.; Dotro, R.; Guinda, J.

2013-01-01

There are a large number of instrument subjected to different service condition in a NPP. For instance different instruments can be found working in environment where the dose rate goes from negligible levels up to very harsh radiation levels. When technical specification and or equipment purchasing should be carried out it is possible to find the total leak of qualified instrument. In this context there is a need of dedicated qualification. In this work two different radiation resistance for two different I&C equipment/component were studies. The first I&C equipment was an LVDT (liner variable differential transformer). This equipment was tested while it was actuated in a strong gamma field in order to evaluate possible electromagnetic interferences a number of cycles equivalent to one year of service. After that the component was subjected to accelerated radiation aging and then actuated test under gamma field were carried out. The second I&C component to be tested was an (author)

In search of extendable conditions for cable environmental qualification in nuclear power plants

International Nuclear Information System (INIS)

Alshaketheep, Tariq; Sekimura, Naoto; Itoi, Tatsuya; Murakami, Kenta

2016-01-01

The environmental qualification (EQ) for cable insulators in nuclear power plants (NPPs) has been developed on the basis of the design basis accident (DBA) to prevent reactor core damage. However, the latest safety principles require extending the design concept to prepare the utilized equipment for scenarios after core damage. Thus, we propose a modification to the EQ for cables connecting utilized equipment at design extension conditions. This paper surveys all electrical components for accident management in boiling water reactor-4 (BWR-4), and identifies their connecting cables' functional category as low-voltage power, instrumentation, and control cables. The EQ temperature profile of these cables during the incident phase was addressed for extension. This required postulating maximum temperature environments according to accident scenarios, knowledge of cable integrity degradation, and their current evaluation by the EQ. To evaluate whether these environments are suitable stressors, heat testing was conducted on flame-retardant ethylene propylene rubber (FR-EPR)-insulated cables. On the basis of those results, we suggest a maximum primary peak temperature of the EQ temperature profile of 250degC. We also suggest increasing the primary peak period of the EQ temperature profile to 48 h without experiment, on the basis of inherent excessive margin for mechanical integrity during the ageing phase. (author)

The qualification of reactor operators

International Nuclear Information System (INIS)

Lima, J.M. de; Soares, H.V.

1981-01-01

The qualification and performance of nuclear power personnel have an important influence on the availability and safety operation of these plants. This paper describes the Brazilian rules and norms established by the CNEN-Brazilian Atomic Energy Comission, as well as policy of other countries concerning training requirements and experiences of nuclear power reactor operators. Some coments are made about the im pact of the march 1979 Three Mile Island accident on upgrading the reactor training requirements in U.S.A. and its international implication. (Author) [pt

Design and Test Plans for a Non-Nuclear Fission Power System Technology Demonstration Unit

Science.gov (United States)