Remotely-operated equipment for inspection, measurement and handling

CERN Document Server

Bertone, C; CERN. Geneva. TS Department

2008-01-01

As part of the application of ALARA radiation dose reduction principles at CERN, inspection, measurement and handling interventions in controlled areas are being studied in detail. A number of activities which could be carried out as remote operations have already been identified and equipment is being developed. Example applications include visual inspection to check for ice formation on LHC components or water leaks, measurement of radiation levels before allowing personnel access, measurement of collimator or magnet alignment, visual inspection or measurements before fire service access in the event of fire, gas leak or oxygen deficiency. For these applications, a modular monorail train, TIM, has been developed with inspection and measurement wagons. In addition TIM provides traction, power and data communication for lifting and handling units such as the remote collimator exchange module and vision for other remotely operated units such as the TAN detector exchange mini-cranes. This paper describes the eq...

Equipment for inspection of austenitic stainless steel pipe welds

International Nuclear Information System (INIS)

Boehmer, W.D.; Horn, J.E.

1979-01-01

A computer controlled ultrasonic scanning system and a data acquisition and analysis system have been developed to perform the inservice inspection of welds in stainless steel sodium piping in the Fast Flux Test Facility. The scanning equipment consists of a six axis motion mechanism and control system which allows full articulation of an ultrasonic transducer as it follows the circumferential pipe welds. The data acquisition and analysis system consists of high speed ultrasonic waveform digitizing equipment, dedicated processors to perform on-line analysis, and data storage and display equipment

Application of wireless LAN technology to remote monitoring for inspection equipment

International Nuclear Information System (INIS)

Ishiyama, Koichi; Kimura, Takashi; Miura, Yasushi; Yamaguchi, Katsuhiro; Kabuki, Toshihide

2011-01-01

To support inspections under an Integrated Safeguards regime into Tokai Reprocessing Plant (TRP), the IAEA suggested making use of Remote Monitoring (RM) capabilities to the inspection equipment (surveillance camera and NDA systems) installed in the spent fuel storage area at TRP. Since TRP had no pre-prepared cabling infrastructure for data transmission in the spent fuel storage area, the option of wireless LAN was chosen over the telephone line due to its lower installation costs. Feasibility studies and tests were performed by TRP on communication and particularly on long-term continuous communication using wireless LAN equipment composed of APs (AP: Access Point) and the external antennas for introducing wireless LAN technology to RM. As a result it was recognized that wireless LAN has enough ability to communicate for long periods of time and consequently the IAEA installed the AP and the external antenna to each inspection equipment and the wireless LAN technology was applied for RM. In this paper, the summary of each test and the results are reported. (author)

33 CFR 157.150 - Crude Oil Washing Operations and Equipment Manual: Recording information after inspections.

Science.gov (United States)

2010-07-01

... Equipment Manual: Recording information after inspections. 157.150 Section 157.150 Navigation and Navigable... Vessels Inspections § 157.150 Crude Oil Washing Operations and Equipment Manual: Recording information... machines. (2) Revolutions, number of cycles, and length of cycles of each COW machine. (3) Pressure and...

The radioprotection inspection manual for odontologic X-rays equipment

International Nuclear Information System (INIS)

Almeida, C.D. de.

1988-01-01

The inspection manual for odontologic X-ray, using films and thermoluminescent dosemeters are showed, decreasing the time of exposition by some recommendation. Some calculations are also cited, for decrease the exposure time, for filtrating the equipment and for a radiometric survey. (C.G.C.) [pt

Application of risk-based inspection methods for cryogenic equipment

CERN Multimedia

CERN. Geneva

2016-01-01

Risk-based Inspection (RBI) is widely applied across the world as part of Pressure Equipment Integrity Management, especially in the oil and gas industry, to generally reduce costs compared with time-based approaches and assist in assigning resources to the most critical equipment. One of the challenges in RBI is to apply it for low temperature and cryogenic applications, as there are usually no degradation mechanisms by which to determine a suitable probability of failure in the overall risk assessment. However, the assumptions used for other degradation mechanisms can be adopted to determine, qualitatively and semi-quantitatively, a consequence of failure within the risk assessment. This can assist in providing a consistent basis for the assumptions used in ensuring adequate process safety barriers and determining suitable sizing of relief devices. This presentation will discuss risk-based inspection in the context of cryogenic safety, as well as present some of the considerations for the risk assessme...

The development of remote repairing system, decontamination and in-cell remote inspection equipment

International Nuclear Information System (INIS)

Ishibashi, Yuzo; Toyoda, Osamu; Haginoya, Isao; Yamamoto, Ryuichi; Tanaka, Yasumasa

1993-01-01

PNC has been developing remote repair and inspection technologies for in-cell components in reprocessing Plants. In this report, several remote technologies such as remote dismantling and removal, decontamination, remote pipe maintenance and remote in-cell inspection equipment are described. (author)

To the application of TV and optical equipment for in-service inspection of reactor vessel and primary circuit component materials

International Nuclear Information System (INIS)

Afonin, Eh.M.; Bachelis, I.M.; Tokarev, E.A.; Yastrebov, V.E.

1985-01-01

Some problems of application of TV and optical equipment for inspection of reactor vessel and primary circuit component materials are considered taking the most widespread WWER-440 type reactor as an example. The most advanrageous objects of the inspection and typical zones of equipment arrangement are shown. Methods and peculiarities of the inspection with the use of TV and optical equipment are presented. Recommendations on rational application of the equipment for the inspection of WWER-440 reactor vessel components are given

A MAINTENANCE STRATEGY MODEL FOR STATIC EQUIPMENT USING INSPECTION METHODOLOGIES AND RISK MANAGEMENT

Directory of Open Access Journals (Sweden)

J.K. Visser

2012-01-01

Full Text Available

ENGLISH ABSTRACT: Mechanical equipment used on process plants can be categorised into two main types, namely static and rotating equipment. A brief survey at a number of chemical process plants indicated that a number of maintenance strategies exist and are used for rotating equipment. However, some of these strategies are not directly applicable to static equipment, although the risk-based inspection (RBI methodology has been developed for pressure vessels. A generalised risk-based maintenance strategy for all types of static equipment does not currently exist. This paper describes the development of an optimised model of inspection methodologies, maintenance strategies, and risk management principles that are generically applicable for static equipment. It enables maintenance managers and engineers to select an applicable maintenance strategy and inspection methodology, based on the operational and business risks posed by the individual pieces of equipment.

AFRIKAANSE OPSOMMING: Meganiese toerusting wat op prosesaanlegte gebruik word kan in twee kategorieë verdeel word, naamlik statiese en roterende toerusting. 'n Bondige ondersoek by 'n aantal chemiese prosesaanlegte het aangedui dat 'n aantal strategieë vir instandhouding van roterende toerusting gebruik word, terwyl die risikogebaseerde inspeksiemetodologie wel vir drukvate gebruik word. 'n Algemene risikogebaseerde instandhoudingstrategie vir alle tipes statiese toerusting is egter nie tans beskikbaar nie. Hierdie artikel beskryf die ontwikkeling van 'n geoptimeerde model van inspeksiemetodologieë, instandhoudingstrategieë, en risikobestuursbeginsels wat algemeen gebruik kan word vir statiese toerusting. Dit stel die instandhouding-bestuurders en -ingenieurs in staat om 'n instandhoudingstrategie en inspeksie-metodologie te kies, gebaseer op die operasionele en besigheidsrisiko's van die individuele toerusting.

Design considerations, tooling and equipment for remote in-service inspection of radioactive piping and pressure vessel systems

International Nuclear Information System (INIS)

Schmoker, D.S.; Swannack, D.L.

1983-01-01

In-Service Inspection programs are performed to monitor and verify the integrity of a nuclear power plant's primary pressure boundaries. Early detection of abnormal structural or material degradation could preclude serious damage to plant systems. This paper summarizes results obtained in use of remotely-operated nondestructive testing (NDT) equipment for inspection of reactor system components. Experience obtained in operating the Fast Flux Test Facility (FFTF) has provided a basis for field verification of remote NDT equipment designs and has suggested development improvements. Remote Viewing and data gathering systems used include periscopes, borescopes, fiberscopes, hybrid borescopes/fiberscopes, and closed circuit television. A summary of design consideration for inspection equipment and power plant design is presented to achieve improved equipment operation and reduction of plant maintenance downtime

Survey on requirements for independent reviews and inspections of electrical and I and C equipment

International Nuclear Information System (INIS)

Byman, Karin; Groenkvist, Stefan; Egerbo, Anders; Nilsson, Thomas

2009-03-01

In this survey, licensing procedures for the implementation of different kinds of components and systems in nuclear power plants have been studied in four European countries: Belgium (Finland), Germany, and Switzerland. The main focus has been to describe the general features of the licensing procedures for electrical and for instrumentation and control (IandC) equipment and systems. The regulatory framework for the operation of nuclear power plants in Belgium is based on the American regulations. The licensing procedure for each modification of significance for the safety of a plant is carried out by the authorised inspection organisation (AVN), which follows its own procedures for the review of the modification file, the commissioning, and conformity check of the installation. These procedures are very general and independent of the technical domain of the equipment or system and AVN uses the US regulations standard review plan (SRP) as a reference for technical reviews. The Federal Agency for Nuclear Control (FANC) is responsible for the surveillance of all nuclear activities in Belgium, but the private non-profit authorised inspection organisation (AVN) does perform inspections and other regulatory tasks delegated by FANC. Controls of electrical components and systems with regard to the general Belgian electrical regulations are performed by accredited inspection organisations. The regulatory framework for the safety of nuclear activities in Finland is domestic and detailed safety requirements are provided by the Radiation and Nuclear Safety Authority (STUK). They cover specific requirements for the licensing procedure for electrical and IandC equipment. In Finland, there are no general differences in the licensing procedure for electrical, instrumentation, and mechanical equipment and the licensing procedure is basically the same for all types of systems, structures and equipment. STUK has the responsibility for the regulatory control in Finland and may seek

Towards a strengthening of inspections carried out on pressurised equipment and pipework..

International Nuclear Information System (INIS)

Noel, St.

2010-01-01

Following the fast presidential election, a major restructuring of the administrative landscape was set in motion. Tasks that historically were the responsibility of the Ministry of Industry are now carried out by the Ministry of Sustainable Development, which in particular is responsible for the whole policy to do with the prevention of technological risks. The General Directorate for the Prevention of Risks (Direction generale de la prevention des risques (DGPR)) of this ministry is now responsible for controlling technological risks, opening up new perspectives in terms of managing accidental risks and offering a new opportunity for an 'integrated' approach, making it possible to deal with an industrial installation in all its facets. Within the DGPR, the Office for the Safety of Industrial Equipment (bureau de la securite des equipements industriels (BSEI)) is responsible for the safety of pressurised equipment, as well as pipes carrying gas, inflammable liquids and chemical products. After a quick presentation of the inspections carried out on this equipment, issues to do with their safety will be dealt with and in particular: - the suitability of inspections carried out in the tight of faults that are likely to occur and develop in the structures; - control of ageing; - management of the quality of new equipment. (author)

Design considerations, tooling, and equipment for remote in-service inspection of radioactive piping and pressure-vessel systems

International Nuclear Information System (INIS)

Swannack, D.L.; Schmoker, D.S.

1983-01-01

This paper summarizes results obtained in use of remotely-operated nondestructive testing (NDT) equipment for inspection of reactor-system components. Experience obtained in operating the Fast Flux Test Facility (FFTF) has provided a basis for field verification of remote NDT equipment designs and has suggested development improvements. Remote Viewing and data gathering systems used include periscopes, borescopes, fiberscopes, hybrid borescopes/fiberscopes, and closed circuit television. A summary of design consideration for inspection equipment and power plant design is presented to achieve improved equipment operation and reduction of plant maintenance downtime

Regulations providing for the inspection of gamma radiography equipment

International Nuclear Information System (INIS)

1981-01-01

Pursuant to the 1938 Act on X-rays and radium, etc and the 1976 regulations on supervision and use of installations and apparatus which release radiation representing a hazard to health, the State Institute of Radiation Health issued these regulations providing for a system of periodic inspections of gamma radiography equipment for radiation protection purposes. They entered into force on 1 July 1981 [fr

The MCNP simulation of the X-ray leakage of X-ray security inspection equipment

International Nuclear Information System (INIS)

Wang Kai; Liu Bin; Hu Wenchao; Zhao Wei

2011-01-01

Objective: To simulate the radiation leakage of the X-ray security inspection equipment used in the subways stations. Methods: We use the MCNP4C code to simulate the X-ray leakage of the equipment during the working process. Result: the biggest amount of radiation received by the body is 8.26 μSv/a, however, if the Lead screens of the X-ray security equipment is intact, the amount of radiation received by the body is only 0.0727 μSv/a. The final. Conclusions: When the baggage get in /out the X-ray security inspection equipment, the gas in Lead screens was made, and then the amount of radiation received by human body increased; The amount of radiation received by the body is close to but still below 10 μSv/a which is the exemption criteria set by the 'safety of radiation sources of ionizing radiation protection and basic standards'(GB18871-2002). (authors)

Acceptance of the institutions and the organs of inspection for the nuclear under pressure equipment

International Nuclear Information System (INIS)

2006-05-01

The candidate companies in the acceptance have to justify their competence in inspection on one hand, in nuclear pressure equipment on the other hand. The guide defines the conditions of the acceptance (competence and modes of proof), the contents of the demand of acceptance, the procedure of instruction as well as the conditions of the preservation of the acceptance. The general direction of the nuclear safety and the radiation protection implements the control of the companies and the organs of inspection for their activities in nuclear equipment under pressure. (N.C.)

Automation and mechanization of in-service inspection of selected equipment in FRG's nuclear power plants

International Nuclear Information System (INIS)

Metke, E.

1988-01-01

The procedures and equipment are described for the automation and mechanization of in-service inspection in nuclear power plants in the FRG, used by the KWU company. Checks of the pressure vessel are done by visual means using a colour tv camera, the method of eddy currents and the ultrasonic method. An analysis is made of the time schedule of ultrasonic inspections, and the central column manipulator is described which allows to check all internal regions of the pressure vessel. Attention is also devoted to other devices, e.g., those for prestressing shanks, cleaning shanks, cleaning thread apertures, etc. A combined probe using the ultrasonic method and the eddy current method serves the inspection of heat exchange tubes in the steam generator. For inspecting the primary circuit the KWU company uses devices for checking and working the inner surface of pipes. Briefly described are examples of using KWU equipment in nuclear power plants in CMEA countries. (Z.M.). 11 figs., 6 refs

Survey on requirements for independent reviews and inspections of electrical and I and C equipment

Energy Technology Data Exchange (ETDEWEB)

Byman, Karin; Groenkvist, Stefan; Egerbo, Anders; Nilsson, Thomas (AaF Consult AB, Stockholm (Sweden))

2009-03-15

In this survey, licensing procedures for the implementation of different kinds of components and systems in nuclear power plants have been studied in four European countries: Belgium (Finland), Germany, and Switzerland. The main focus has been to describe the general features of the licensing procedures for electrical and for instrumentation and control (IandC) equipment and systems. The regulatory framework for the operation of nuclear power plants in Belgium is based on the American regulations. The licensing procedure for each modification of significance for the safety of a plant is carried out by the authorised inspection organisation (AVN), which follows its own procedures for the review of the modification file, the commissioning, and conformity check of the installation. These procedures are general and independent of the technical domain of the equipment or system and AVN uses the US regulations standard review plan (SRP) as a reference for technical reviews. The Federal Agency for Nuclear Control (FANC) is responsible for the surveillance of all nuclear activities in Belgium, but the private non-profit authorised inspection organisation (AVN) does perform inspections and other regulatory tasks delegated by FANC. Controls of electrical components and systems with regard to the general Belgian electrical regulations are performed by accredited inspection organisations. The regulatory framework for the safety of nuclear activities in Finland is domestic and detailed safety requirements are provided by the Radiation and Nuclear Safety Authority (STUK). They cover specific requirements for the licensing procedure for electrical and IandC equipment. In Finland, there are no general differences in the licensing procedure for electrical, instrumentation, and mechanical equipment and the licensing procedure is basically the same for all types of systems, structures and equipment. STUK has the responsibility for the regulatory control in Finland and may seek

Development of inspection equipment for fuel bundles of CANDU-PHWR using R981 underwater radiation tolerant camera

Energy Technology Data Exchange (ETDEWEB)

Koo, Dae-Seo; Cho, Moon-Sung; Jo, Chang-Keun; Jun, Ji-Su; Jung, Jong Yeob; Park, Kwang-June; Suk, Ho-Chun

2005-03-15

The inspection equipment of fuel bundles was developed, which could perform visual inspection and dimensional measurement on fuel bundles of CANDU-PHWR, to evaluate, analyze the defective behavior of fuel bundles and inner surface of pressure tubes of inherent two-phase flow over 24kg/s in CANDU-6. The R981 radiation tolerant camera system with pan and tilt function was ordered and manufactured, which was waterproof, shielding radiation in underwater 10m in depth. The performance test, of the system ,due to camera-object distance was carried out in air/underwater atmosphere. The results of performance test of R981 radiation tolerant camera system are good. The inspection equipment of fuel bundles using R981 radiation tolerant camera system and underwater-radiation tolerant LVDT sensor(D5/200AW) was fabricated, which could perform visual inspection and dimensional measurement on fuel bundles of CANDU-PHWR with measurement accuracy 10{mu}m. This equipment will be utilizable integrity evaluation of fuel bundles which are irradiated in pressure tube of CANDU-PHWR.

Remote-automated inspection and maintenance of nuclear power plant equipment

Energy Technology Data Exchange (ETDEWEB)

Sasaki, Masayoshi; Nakano, Yoshiyuki

1984-12-01

Employing remote-control inspection and maintenance equipment in nuclear power plants increases the plant availability by decreasing the annual shutdown time (outage), as well as radiation exposure and man-power. This paper presents an outline of the latest designs for an automatic refueling machine, a control rod drive handling machine, a fuel preparation machine, and a main steam line plug, which were supplied to the Fukushima Dai-Ni No. 2 Plant of the Tokyo Electric Power Co., Inc. (Fukushima 2-2). Also, the up-to-date developments of other new automatic machines, such as a CRD disassembly and cleaning system, spent fuel channel box volume reduction equipment, and robotics for nuclear plant use are presented.

Recommended safety procedures for the selection, installation and use of baggage inspection x-ray equipment

International Nuclear Information System (INIS)

1978-05-01

Good X-ray equipment alone will not preclude unnecessary exposure to x-radiation. The equipment must be installed, maintained and used by adequately trained personnel, with due regard for the inherent hazards of such equipment and an appreciation of the need to observe proper operational procedures. It is the intent of this Code to define equipment specifications and conditions of installation and use for baggage inspection X-ray equipment, such that the hazard to operating personnel and the general public from such devices remains negligibly small. (auth)

36 CFR 1254.12 - Will NARA log or inspect my computer, other equipment, and notes?

Science.gov (United States)

2010-07-01

... personal notes into the research room. In research rooms that permit taking in your notes, a NARA or... computer, other equipment, and notes? 1254.12 Section 1254.12 Parks, Forests, and Public Property NATIONAL... MATERIALS General Information § 1254.12 Will NARA log or inspect my computer, other equipment, and notes? (a...

Experience in industrial radiography equipment into carry out inspections in Brazil

International Nuclear Information System (INIS)

Lopes, Valdir Maciel; Silva, Joao

2008-01-01

The Nuclear and Energy Research Institute (IPEN), in accordance with the attributions given by the National Commission of Nuclear Energy (CNEN), has been supplying the market with radioactive sealed sources of Iridium 192 ( 192 Ir), for Brazil and some South America Countries, for more than 24 years. In this period, the experience acquired in the accompanied of the technological improvement in the industrial gammagraphy equipment; into Sealed Sources Production Laboratory (LPFS) will be show. Of the set of operations carry out in the LPFS, since the assemblies, tests of qualification of the sources also inspection at of the equipment for posterior applications in field, it is intended to demonstrate to the technological improvement associate to the radiological and operational security. In this work, the data base of the system of the LPFS will be used, as well as the professional experience of the laboratory team in the daily relationship with the companies responsible for the equipment operation. (author)

Investigation with automatic ultrasonic equipment to trace flaws in a large test piece, and experience gained in carrying out inspections

International Nuclear Information System (INIS)

Lindner, J.P.

1975-01-01

Based on the FRG codes providing guide lines for the Reactor Safety Commission regarding the size and location of flaws to be detected during in-service inspections, investigations were carried out into the possibility of detecting defects in thick-walled reactor pressure vessel components with the aid of ultrasonic inspection systems. A large test rig was used and, in a similar manner to the in-service inspections on a reactor, the tests were carried out with remote-controlled, automatically guided inspection equipment. For this purpose, a test specimen weighing about 10 tons was produced and provided with two weld seams having a large number of artificial defects. Essential parameters for the various reflectors in the test specimen were the size, location, angle and roughness or structure of the reflecting surfaces. As it is known that austenitic cladding has a considerable influence on flaw detection, the tests were undertaken first without cladding and then with cladding. A manipulator was designed for automatic remote-controlled inspection with which the inspection system travels on a meandering route over the area to be inspected. The inspection system employed was of the same type as the one used for baseline tests during external inspections of reactor vessel walls with parallel surfaces. Digital data collection was by a magnetic tape recorder designed to store both the data of the ultrasonic inspection system as well as the allied position data. The data stored on the tape are evaluated with electronic data processing programmes especially developed for this purpose. These programmes allow locally coherent indication patterns to be prepared, thus simplifying the interpretation of the data obtained. The author initially describes the equipment with the aid of which the studies were undertaken. A detailed discussion is then presented on the design of the test specimen and the inspection systems employed. Following this, the results obtained are explained and

Evaluation of gamma-spectrometry equipment for on-site inspection

International Nuclear Information System (INIS)

Burnett, J.L.; Milbrath, B.D.; Mueller, W.F.

2017-01-01

An On-site Inspection (OSI) is an important component of the verification regime of the Comprehensive Nuclear-Test-Ban Treaty (CTBT), with the objective of gathering evidence of a possible Treaty violation. This includes the use of gamma-spectrometry equipment to identify 17 particulate radionuclides that are indicative of a nuclear explosion. This research provides an evaluation of high- (germanium), medium- (cadmium zinc telluride) and low-resolution (sodium iodide and lanthanum bromide) detectors using modelled radionuclide signatures from a nuclear explosion and Monte Carlo simulations of a detector response. The complex radionuclide signatures are shown to only be distinguishable using a high-resolution system for 1 week and 1 year post-detonation cases. (author)

46 CFR 153.812 - Inspection for Certificate of Inspection.

Science.gov (United States)

2010-10-01

... 46 Shipping 5 2010-10-01 2010-10-01 false Inspection for Certificate of Inspection. 153.812... CARGOES SHIPS CARRYING BULK LIQUID, LIQUEFIED GAS, OR COMPRESSED GAS HAZARDOUS MATERIALS Design and Equipment Testing and Inspection § 153.812 Inspection for Certificate of Inspection. The rules governing the...

Visual inspection equipment for the secondary side of steam generators. Final report

International Nuclear Information System (INIS)

Hinton, M.S.; Chagnon, C.W.

1981-05-01

The development of miniature visual examination equipment capable of inspecting regions inside the tube bundles of nuclear steam generators to determine such factors as gap condition, tube outside surface condition, and material buildup is described. Tube-to-support plate interface regions at the tenth-support plate level in a once-through steam generator (Oconee 1) were visually examined. Other areas in the peripheral region were examined for conditions associated with available eddy-current and profilometer data

Remote-automation of nuclear power plant equipment inspection and maintenance

International Nuclear Information System (INIS)

Sasaki, Masayoshi; Kawamura, Hironobu; Nakano, Yoshiyuki; Izumi, Shigeru.

1984-01-01

The remotely operated automation of the checkup and maintenance of nuclear power generation facilities has largely contributed to the rise of capacity ratio of plants due to the shortening of regular inspection period and to the reduction of radiation exposure dose during working, the labor saving in working and so on. In this paper, the new technologies adopted in an automatic fuel exchanger, a remotely operated automatic CRD exchanger, a new type channel handling machine, pressure-withstanding main steam line plugs and so on for No.2 plant in the Fukushima No.2 Nuclear Power Station, Tokyo Electric Power Co., Inc., are reported. Besides, the state of development of new remotely operated automatic machines for nuclear power use, such as CRD disassembling and cleaning device, volume reduction equipment for spent fuel channel boxes and control rods, multi-functional robots for use under high radiation and so on is described. Also the trend of development of latest robot technology which will be put in practical use in near future is outlined, such as a running manipulator for checkup and inspection, a variable form crawler vehicle and a five-leg movable manipulator. (Kako, I.)

Equipment for inspection and carrying out repairs, if required, for tube bundles of steam raising units

International Nuclear Information System (INIS)

Gugel, G.

1976-01-01

The equipment solves the problem of being able to inspect and possibly to repair U-tubes of a vertical steam raising unit standing on a tube floor, without draining the primary medium and bringing the test equipment and tools into the inside of the boiler first. This is achieved by leaving a considerable part of the equipment permanently in the hemispherical space under the tube floor and operating it from the outside, on the other side of the concrete shielding. An inspection tube is threaded in turn horizontally through a concrete shield, a tube duct in the heat insulation of the steam raising unit, and through a hole in the hemispherical space under the tube floor into this space. The end of an angle tube can be moved axially from outside the concrete shield and can be rotated in a semicircle above the tube axis. By interposing a, for example, 12 part distributor with 12 short, differently bent tubes 12 adjacent tubes opening into the tube floor can be controlled and tested, by axial movement of the angle tube together with the distributor, e.g. 4 x 12 other U tubes. A turbulent flow sensor, for example, can be introduced through the angle tube and distributor. In the non-operational condition the equipment is moved into a recess via a supporting angle and stopped there. (ORU) [de

Periodic and in-service inspection programs

International Nuclear Information System (INIS)

Dinu, M.

2000-01-01

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

Computerized automated remote inspection system

International Nuclear Information System (INIS)

The automated inspection system utilizes a computer to control the location of the ultrasonic transducer, the actual inspection process, the display of the data, and the storage of the data on IBM magnetic tape. This automated inspection equipment provides two major advantages. First, it provides a cost savings, because of the reduced inspection time, made possible by the automation of the data acquisition, processing, and storage equipment. This reduced inspection time is also made possible by a computerized data evaluation aid which speeds data interpretation. In addition, the computer control of the transducer location drive allows the exact duplication of a previously located position or flaw. The second major advantage is that the use of automated inspection equipment also allows a higher-quality inspection, because of the automated data acquisition, processing, and storage. This storage of data, in accurate digital form on IBM magnetic tape, for example, facilitates retrieval for comparison with previous inspection data. The equipment provides a multiplicity of scan data which will provide statistical information on any questionable volume or flaw. An automatic alarm for location of all reportable flaws reduces the probability of operator error. This system has the ability to present data on a cathode ray tube as numerical information, a three-dimensional picture, or ''hard-copy'' sheet. One important advantage of this system is the ability to store large amounts of data in compact magnetic tape reels

46 CFR 71.25-25 - Hull equipment.

Science.gov (United States)

2010-10-01

... 46 Shipping 3 2010-10-01 2010-10-01 false Hull equipment. 71.25-25 Section 71.25-25 Shipping COAST... Inspection § 71.25-25 Hull equipment. (a) At each annual inspection, the inspector shall conduct the following tests and inspections of hull equipment: (1) All subdivision bulkheads shall be examined to...

46 CFR 91.25-25 - Hull equipment.

Science.gov (United States)

2010-10-01

... 46 Shipping 4 2010-10-01 2010-10-01 false Hull equipment. 91.25-25 Section 91.25-25 Shipping COAST... CERTIFICATION Inspection for Certification § 91.25-25 Hull equipment. (a) At each inspection for certification and periodic inspection, the inspectors shall conduct the following tests and inspections of hull...

46 CFR 189.25-25 - Hull equipment.

Science.gov (United States)

2010-10-01

... 46 Shipping 7 2010-10-01 2010-10-01 false Hull equipment. 189.25-25 Section 189.25-25 Shipping... CERTIFICATION Inspection for Certification § 189.25-25 Hull equipment. (a) At each inspection for certification and periodic inspection the inspector shall conduct the following tests and inspections of hull...

Plant equipment integrity monitoring and diagnosing method and device therefor, plant equipment maintenance and inspection time determining method and device therefor, as well as nuclear power plant

International Nuclear Information System (INIS)

Kato, Takahiko; Ando, Masashi; Osumi, Katsumi; Horiuchi, Tetsuo; Asakura, Yamato; Akamine, Kazuhiko.

1995-01-01

The present invention can accurately forecast a time for occurrence of troubles of plant equipments in contact with recycling water, to conduct its maintenance and inspection before occurrence of the troubles. Namely, change of water quality in plant equipments caused by corrosion of recycling water occurred in constitutional parts of the plant equipments is measured. The time upon occurrence of the troubles of the plant equipments to corrosion of the recycling water is forecast based on the measured value. A time till the occurrence of the change of water quality after starting the use of the plant equipments is calculated based on the measured value. The calculated time is compared with a correlation between the time of occurrence of the troubles after starting the use of the plant equipments and the time of occurrence of change of the water quality, to forecast the time of occurrence of the troubles. Preferably, electroconductivity and pH of recycling water in the inside or at the exit of the plant equipments are measured as an object for the measurement of change of water quality. (I.S.)

Runway Inspection by RPAS

Directory of Open Access Journals (Sweden)

Stanislav Absolon

2015-10-01

Full Text Available This article discusses the use of the RPAS for the inspection of the airport operating areas. The paper compares the current process of the inspection of the airport operating areas by the airport staff with the possibilities which are offered by the use of the modern technology RPAS. The following text also describes how to inspect airport operating areas by the RPAS, specific technical possibilities and the applicable technical solutions. Furthermore there are variants of piloting the RPAS, comparing usable equipment, equipment for video recording and the possibility of using thermal imaging camera in the article.

In-pile inspections of the Calder and Chapelcross nuclear reactors

International Nuclear Information System (INIS)

Stewart, G.

1984-01-01

The subject is discussed under the headings: introduction (relevant data about the reactors); inspection policy; photographic inspection (equipment; inspection results (vessel seam welds and plates; top dome welds; top dome internals)); ultrasonic equipment; manipulator; television inspections; concluding remarks. (U.K.)

Apparative developments for inservice inspections of reactor pressure vessels

International Nuclear Information System (INIS)

Bohn, H.; Ruthrof, K.; Barbian, O.A.; Kappes, W.; Neumann, R.; Stanger, H.K.

1987-01-01

Emphasizing PWR pressure vessel (RPV) inspections, recent developments of new generations of automated and mechanized ultrasonic inspection equipment are presented. Starting from general equipment design and inservice implenentation criteria, specific examples are given. Main attention is directed to equipment realization of phased array and ALOK inspection techniques, especially in their combination. Refined aspects of subsequent computer processing and evaluation of defect detection data are described. Analytical features and potential for further developments become evident. Remote controlled RPV inspections are stressed by describing a new generation of central mast manipulators, forming an integral part of total inservice inspection system. (orig./HP)

Development of a remote inspection system for NSSS components

International Nuclear Information System (INIS)

Choi, Yoo Rark; Kim, Jae Hee; Lee, Jae Cheol

2004-03-01

Different operating systems of computerized inspection equipment cause serious problems in graphic user interface between control computers of inspection equipment and remote user computers. Management cost of interface version is very expensive even if the system has been developed. A solution for the interface problems in accessing the remote inspection system is web-based technology. But time-delay problem of web and java, a compiled type S/W that cooperates with web in control computers of inspection equipment is necessary to solve it. This report describes solutions for developing a remote inspection system based on web and java technology

The inspection of equipment in the Amazon region: from ACFM to electronic PIG in Urucu; A inspecao de equipamentos na Amazonia: do ACFM ao pig instrumentado em Urucu

Energy Technology Data Exchange (ETDEWEB)

Mac-Culloch, Joao Nazareth Lafayette de Mello [PETROBRAS S.A., Salvador, BA (Brazil). Exploracao e Producao. Unidade de Servicos de Sondagem Auto-Elevatoria; Beuren, Jair; Quadrado, Flavio Emir; Dunham, Paulo Cezar da Costa Lino [PETROBRAS S.A., Manaus, AM (Brazil). Exploracao e Producao. Unidade de Negocio da Bacia do Solimoes

2003-07-01

This paper presents the historical evolution of the activity of equipment inspection of the PETROBRAS/UN-BSOL, in which the developments of a motivation program of the personnel from the effort developed for the certification of inspectors since the techniques more known most modern for the examination of installations and equipment was of great importance. PETROBRAS was introduced in the ACFM by TSC-Technical Software Consultants, during NDT (Non Destructive Test) Congress in 1994. PETROBRAS/UN-BSOL was the first unit to acquire the last equipment, called Amigo. In 2002 has qualified three professionals to ACFM level I. Nowadays, five inspectors level I and one level II and the technique has been used through inspections in several equipment with very well satisfactory. The Duto de Coleta de oleo de LUC de 10in and the Duto de Coleta de gas de LUC de 14in had been inspected with the PIG using the technique of Magnetic flux leakage (MFL), being that in the first one it was used Quantitative Smart PIG (High Resolution) and in as it was used Qualitative Smart PIG (Low Resolution). The results show that, despite the raised cost of the High Resolution PIG, this still is indicated for in-line inspection of pipelines of the UN-BSOL. (author)

Development of the pellet grinding and inspection system

International Nuclear Information System (INIS)

Yamaguchi, Toshihiro; Kawasaki, Takao; Inui, Toshihiko; Yamada, Hiroyuki.

1996-01-01

The pellet grinding and inspection system is the facility of producing the MOX fuel for FBRs, and it was delivered in March, 1996 to the No. 3 Development Office of the plutonium fuel shop in Tokai of Power Reactor and Nuclear Fuel Development Corporation. This facility realized the high speed processing using the compact facility by combining the grinding of pellets, the inspection of outer density and appearance, the rationalization of the facility and the high performance automation equipment. The production processes of MOX comprise the processes of powder, sinter, finish and inspection, fabrication and assembling. The requirement for developing these facilities is shown. The features of this pellet grinding and inspection system are the compact facility by the combination of functions, high speed processing, the reduction of holdup in processes and the improvement of maintenance. These features are explained. The main components are simple sorting equipment, grinder, grinding dust recovering equipment, outside diameter and density sorting equipment and appearance inspection equipment. The constitution and the main functions of the control facility are described. The operational process is explained. (K.I.)

Design and implementation for integrated UAV multi-spectral inspection system

Science.gov (United States)

Zhu, X.; Li, X.; Yan, F.

2018-04-01

In order to improve the working efficiency of the transmission line inspection and reduce the labour intensity of the inspectors, this paper presents an Unmanned Aerial Vehicle (UAV) inspection system architecture for the transmission line inspection. In this document, the light-duty design for different inspection equipment and processing terminals is completed. It presents the reference design for the information-processing terminal, supporting the inspection and interactive equipment accessing, and obtains all performance indicators of the inspection information processing through the tests. Practical application shows that the UAV inspection system supports access and management of different types of mainstream fault detection equipment, and can implement the independent diagnosis of the detected information to generate inspection reports in line with industry norms, which can meet the fast, timely, and efficient requirements for the power line inspection work.

SICOM: On-site inspection systems

International Nuclear Information System (INIS)

Serna, J.J.; Quecedo, M.; Fernandez, J.R.

2002-01-01

As the irradiation conditions become more demanding for the fuel than in the past, there is a need for surveillance programs to gather in-reactor operating experience. The data obtained in these programs can be used to assess the performance of current fuel designs and the improvements incorporated to the fuel assembly design, the performance of the advanced cladding alloys, etc. In these regards, valuable data is obtained from on-site fuel inspections. These on-site data comprise fuel assembly dimensional data such as length and distortion (tilt, twist and bow) and fuel rod data such as length and oxide thickness. These data have to be reliable and accurate to be useful thus, demanding a high precision inspection equipment. However, the inspection equipment has to be also robust and flexible enough to operate in the plant spent fuel pool and, sometimes, without interfering in the works carried out during a plant outage. To meet these requirements, during the past years ENUSA and TECNATOM have developed two on-site inspection systems. While the first system can perform most of the typical measurements in a stand-alone manner thus, without interfering with the critical path of the reload, the second one reduces the inspection time but requires using the plant capabilities. The paper describes both equipment for fuel on-site inspection, their characteristics and main features. (author)

Employing innovative techniques to reduce inspection times

International Nuclear Information System (INIS)

Heumueller, R.; Guse, G.; Dirauf, F.; Fischer, E.

1997-01-01

Shorter inspection periods mean lower revision costs and less tight revision schedules, but must not detract from the quality of inspection findings. This requirement imposes upon the company performing the inspection the need for top achievements both in quality management and in the use of innovative techniques. Flexible equipment systems and inspection techniques adapted to specific purposes are able to reduce inspection times in many inspection jobs. As part of a complete system designed to reduce inspection times, the new Saphir (Siemens Alok Phased Array Integrated Reliable UT-System) inspection equipment system is the core of most of the recent innovations. Being an integrated inspection equipment system, it is able to handle conventional US probes as well as arrays and phased arrays. It is open for further matching to specific inspection and administrative requirements and developments, and it may be incorporated in the network of an integrated system with a database. A technological leap in probe design in the past few years has allowed controllable wave fields to be generated which are in no way inferior to those of conventional probes with fixed angles of incidence. In this way, a number of inspection techniques can be implemented with a single probe. This reduces inspection times, setup and retooling times, and doses. Typical examples already used in practice are the LLT (longitudinal-longitudinal-transverse waves) technique and the integration of inspections for longitudinal and transverse defects in a single run. In the near future, surfaces with complicated curvatures will be inspected by novel modular robot systems consisting of individual modules of linear axes and rotational axes. (orig.) [de

Double-shell tank ultrasonic inspection plan. Revision 1

International Nuclear Information System (INIS)

Pfluger, D.C.

1994-01-01

The waste tank systems managed by the Tank Waste Remediation System Division of Westinghouse Hanford Company includes 28 large underground double-shell tanks (DST) used for storing hazardous radioactive waste. The ultrasonic (UT) inspection of these tanks is part of their required integrity assessment (WAC 1993) as described in the tank systems integrity assessment program plan (IAPP) (Pfluger 1994a) submitted to the Ecology Department of the State of Washington. Because these tanks hold radioactive waste and are located underground examinations and inspections must be done remotely from the tank annuli with specially designed equipment. This document describes the UT inspection system (DSTI system), the qualification of the equipment and procedures, field inspection readiness, DST inspections, and post-inspection activities. Although some of the equipment required development, the UT inspection technology itself is the commercially proven and available projection image scanning technique (P-scan). The final design verification of the DSTI system will be a performance test in the Hanford DST annulus mockup that includes the demonstration of detecting and sizing corrosion-induced flaws

Risk-based inspection of nuclear power plants

International Nuclear Information System (INIS)

Masopust, R.

1995-01-01

A multidiscipline research programme was developed in the USA to establish risk-based inspections for NPP structures and equipment components. Based on this US research effort, the risk-based procedure for developing inspection guidelines for NPPs is described. The procedure includes the definition of systems, qualitative risk assessment, qualitative risk analysis and development of the inspection programme. The method, when adopted and modified, is recommended also for risk-based inspections of structures and equipment of WWER-type NPPs. A pilot application of the method to unit 1 of the Surry NPP is summarized. (Z.S.) 1 tab., 1 fig., 5 refs

In-service inspection guidelines for composite aerospace structures

International Nuclear Information System (INIS)

Heida, Jaap H.; Platenkamp, Derk J.

2012-01-01

The in-service inspection of composite aerospace structures is reviewed, using the results of a evaluation of promising, mobile non-destructive inspection (NDI) methods. The evaluation made use of carbon fibre reinforced specimens representative for primary composite aerospace structures, including relevant damage types such as impact damage, delaminations and disbonds. A range of NDI methods were evaluated such as visual inspection, vibration analysis, phased array ultrasonic inspection, shearography and thermography inspection. Important aspects of the evaluation were the capability for defect detection and characterization, portability of equipment, field of view, couplant requirements, speed of inspection, level of training required and the cost of equipment. The paper reviews the damage tolerance design approach for composites, and concludes with guidelines for the in-service inspection of composite aerospace structures.

40 CFR 63.11089 - What requirements must I meet for equipment leak inspections if my facility is a bulk gasoline...

Science.gov (United States)

2010-07-01

... equipment leak inspections if my facility is a bulk gasoline terminal, bulk plant, pipeline breakout station... gasoline service at the facility. (c) Each detection of a liquid or vapor leak shall be recorded in the log... shall be completed within 15 calendar days after detection of each leak, except as provided in paragraph...

46 CFR 169.253 - Miscellaneous systems and equipment.

Science.gov (United States)

2010-10-01

... VESSELS Inspection and Certification Inspections § 169.253 Miscellaneous systems and equipment. (a) At each inspection for certification and periodic inspection all items in the ship's outfit, such as...

The development of in-cell remote inspection system in Tokai reprocessing plant

International Nuclear Information System (INIS)

Ishibashi, Yuzo

1985-01-01

In the Tokai fuel reprocessing plant, the containment is triple, i.e. the vessel containing radioactive material, then the concrete cell structure and finally the housing building. The fuel reprocessing plant is now proceeding with the development of an in-cell remote inspection system. The inspection system is for inspection of the cell itself and the equipment etc. in the cell, concerning the integrity. Described are the following: the course taken and problems in development of the remote inspection system; development of the floor rambling type remote inspection equipment and the multiple armed type, both for inspection of in-cell ''drip trays''; in-cell equipment inspection devices in specifications etc.; problems in its future development. (Mori, K.)

Ultrasound periodic inspections of reactor pressure vessels

International Nuclear Information System (INIS)

Haniger, L.

1980-01-01

Two versions are described of ultrasonic equipment for periodic inspections of reactor pressure vessels. One uses the principle of exchangeable programmators with solid-state logic while the other uses programmable logic with semiconductor memories. The equipment is to be used for inspections of welded joints on the upper part of the V-1 reactor pressure vessel. (L.O.)

Machine vision system for remote inspection in hazardous environments

International Nuclear Information System (INIS)

Mukherjee, J.K.; Krishna, K.Y.V.; Wadnerkar, A.

2011-01-01

Visual Inspection of radioactive components need remote inspection systems for human safety and equipment (CCD imagers) protection from radiation. Elaborate view transport optics is required to deliver images at safe areas while maintaining fidelity of image data. Automation of the system requires robots to operate such equipment. A robotized periscope has been developed to meet the challenge of remote safe viewing and vision based inspection. (author)

Automatic inspection Pads second generation; Inspeccion automatica de pastillas de segunda generacion

Energy Technology Data Exchange (ETDEWEB)

Gallardo-Lancho gonzalez, J. F.

2010-07-01

In recent years, development has addressed Enusa a second generation robot for automatic inspection of tablets incorporating the following advances: more advanced systems that improve vision quality inspection equipment, conducting the inspection in line with the grinding operation, increased productivity of the inspection process to be unnecessary pills buildup in trays and lay-out of the most rational equipment allowing cleaning it easier and faster. This second generation machine is already part of the automatic inspection equipment developed by Enusa and is an example of the ongoing commitment to the development Enusa and innovation in nuclear technology.

The Ontario hydro low pressure turbine disc inspection program automated ultrasonic inspection systems - an overview

International Nuclear Information System (INIS)

Huggins, J.W.; Chopcian, M.; Grabish, M.

1990-01-01

An overview of the Ontario Hydro Low Pressure Turbine Disc Inspection Program is presented. The ultrasonic inspection systems developed in-house to inspect low pressure turbine discs at Pickering and Bruce Nuclear Generating stations are described. Three aspects of the program are covered: PART I - Background to inspection program, disc cracking experience, and development of an in-house inspection capability: PART II - System development requirements; ultrasonic equipment, electromechanical subsystems and instrumentation console: PART III - Customized software for flaw detection, sizing, data acquisition/storage, advanced signal processing, reports, documentation and software based diagnostics

30 CFR 18.97 - Inspection of machines; minimum requirements.

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Inspection of machines; minimum requirements... TESTING, EVALUATION, AND APPROVAL OF MINING PRODUCTS ELECTRIC MOTOR-DRIVEN MINE EQUIPMENT AND ACCESSORIES Field Approval of Electrically Operated Mining Equipment § 18.97 Inspection of machines; minimum...

Generic data base for security equipment and its utility in the safeguards inspection process. Final report 8151-79-FR-16

International Nuclear Information System (INIS)

Scala, S.

1979-01-01

This report contains material presented at the Nuclear Regulatory Commission (NRC) conference of regional inspectors in Atlanta, Georgia, on January 17, 1979. It describes the contents of the generic data base for security equipment, which was developed by SRI for NRC under a Sandia Laboratories' subcontract, and examines its potential utility in the process of inspection of NRC-licensed facilities

Travelling type monitoring and inspection device

International Nuclear Information System (INIS)

Ito, Takao; Maruki, Hideaki.

1994-01-01

The present invention sufficiently ensures video output images even if lenses of a television camera of a monitoring means are degraded to reduce the quantity of transmission light. That is, a light amount control mechanism capable of controlling the quantity of illumination light irradiated from an illumination device at an output level of a sensor of an inspection device main body. A test chart for measuring a luminance which is an output level of the sensor is disposed. During plant operation, the lenses of the television camera undergo influences of radioactivity and are degraded to reduce the quantity of transmission light on every periodical monitoring and inspection using a travelling type monitoring inspection device. In this case, the test chart disposed near the equipment to be monitored and inspected is caught by the television camera to measure a sensor output luminance. Then, the light amount control mechanism of the illumination device is controlled so as to provide a luminance which has been set at an initial stage of the plant inspection. With such procedures, video data of the objective equipment to be monitored and inspected can be obtained at a constant luminance during inspection. (I.S.)

Visual Inspection of the Flow Distribution Plate Bolts of a Nuclear Steam Generator

International Nuclear Information System (INIS)

Jeong, Woo Tae; Kim, Suk Tae; Sohn, Wook; Kang, Duk Won; Kang, Seok Chul

2007-01-01

To develop a system for visually inspecting the flow distribution plate (FDP) bolts of a nuclear steam generator, we reviewed several types of similar inspection equipment. The equipment which are currently available are mostly for inspecting lower part of a steam generator such as tube sheets and annulus except ELVS (Eggcrate Visual Inspection System). However, the design concept of ELVS could not be used for developing a device which enables the visual inspection of flow distribution plate bolts. Therefore, based on the current state of the art technology on the similar equipment, we conceptually designed a new inspection system for checking the FDP bolts

Boresonic inspection of power plant rotors

International Nuclear Information System (INIS)

Rennie, I.S.

1990-01-01

Continental Field Machining and NEI Parsons together are able to provide an on site machining and boresonic inspection service. NEI Parsons existing boresonic equipment is described together with a summary of results obtained during the inspection of eighty rotors. A computer controlled automatic inspection system, planned to be in operation early in 1990, is also described

Equipment for fully automatic radiographic pipe inspection

International Nuclear Information System (INIS)

Basler, G.; Sperl, H.; Weinschenk, K.

1977-01-01

The patent describes a device for fully automatic radiographic testing of large pipes with longitudinal welds. Furthermore the invention enables automatic marking of films in radiographic inspection with regard to a ticketing of the test piece and of that part of it where testing took place. (RW) [de

Operational inspections

International Nuclear Information System (INIS)

Bystersky, M.

1997-01-01

Special equipment is described, designed for inspection of reactor pressure vessels performed from the inside. Central shaft manipulator ZMM-5 is available for crack detection control using ultrasound and eddy currents, for visual check of surfaces, repair works at the reactor pressure vessel, and hardness measurements. The manipulator consists of the manipulator bridge, a cable container, shaft segments, a control mechanism and auxiliary parts. Eight inspections were performed at the Bohunice nuclear power plant and two at the Paks nuclear power plant. (M.D.)

Savannah River Plant waste tank inspection manual

International Nuclear Information System (INIS)

McNatt, F.G.

1979-01-01

This manual is to aid in making visual and photographic inspections and steel thickness measurements of Building 241-F and -H underground waste storage tanks. It describes the inspection program, the storage tanks, the equipment and techniques used and the results of their application, and the inspection recordkeeping methods

Development of diaphragm automatic homing equipment

International Nuclear Information System (INIS)

Kobayashi, Hidetoshi; Yamada, Koji; Moriya, Shinichi; Koike, Jiro; Okabe, Masao; Oyama, Akihiro.

1996-01-01

In steam-turbine overhaul inspection, one of the most important processes is to remove rust and deposited contaminants on the surface of turbine parts, while the turbine is in operation, to recover thermal efficiency and prepare good surface conditions for color penetrant inspection. These processes generally are done by dry honing, but this generates dust. To protect laborers against these conditions, Hitachi, Ltd. has developed automatic honing equipment for the diaphragms of the nuclear steam turbine. This equipment was first used in the first annual inspection and overhaul of Hamaoka Nuclear Power Plant No.4 of Chubu Electric Power Inc. (author)

47 CFR 80.1067 - Inspection of station.

Science.gov (United States)

2010-10-01

... Inspection of station. (a) Ships must have the required equipment inspected at least once every 12 months by an FCC-licensed technician holding a GMDSS Radio Maintainer's License. If the ship passes the... 47 Telecommunication 5 2010-10-01 2010-10-01 false Inspection of station. 80.1067 Section 80.1067...

30 CFR 18.96 - Preparation of machines for inspection; requirements.

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Preparation of machines for inspection... TESTING, EVALUATION, AND APPROVAL OF MINING PRODUCTS ELECTRIC MOTOR-DRIVEN MINE EQUIPMENT AND ACCESSORIES Field Approval of Electrically Operated Mining Equipment § 18.96 Preparation of machines for inspection...

46 CFR 176.816 - Miscellaneous systems and equipment.

Science.gov (United States)

2010-10-01

... 100 GROSS TONS) INSPECTION AND CERTIFICATION Material Inspections § 176.816 Miscellaneous systems and equipment. At each initial and subsequent inspection for certification the owner or managing operator shall be prepared to test and make available for inspection all items in the ship's outfit, such as ground...

Examination of the association between announced inspections and inspection scores.

Science.gov (United States)

Waters, A Blake; VanDerslice, James; Porucznik, Christina A; Kim, Jaewhan; DeLegge, Royal; Durrant, Lynne

2013-09-01

In 2010 the Salt Lake Valley Health Department conducted a pilot of an announced inspection program utilizing a randomized assignment of restaurants to an intervention group with announced inspections and a control group that remained on the usual schedule of unannounced inspections. After adjusting for food type, visible kitchen, outside quality assurance, season, and standardized inspector, significant reductions were found in the odds ratios of personal hygiene (adjusted odds ratios [aOR] = 0.11, p = .00) and equipment cleanliness (aOR = 0.19, p = .00) violations. In the models for the control group, none of the odds ratios were statistically different from one, indicating no change in the postintervention time period as compared to the preintervention period.

A compliance testing program for diagnostic X-ray equipment

International Nuclear Information System (INIS)

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

1999-01-01

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

Hoisting appliances and fuel handling equipment at nuclear facilities

International Nuclear Information System (INIS)

1987-01-01

The guide is followed by the Finnish Centre for Radiation and Nuclear Safety (STUK) in regulating hoisting and handling equipment Class 3 at nuclear facilities. The guide is applied e.g. to the following equipment: reactor building overhead cranes, hoisting appliances at nuclear fuel storages, fuel handling machines, other hoisting appliances, which because of nuclear safety aspects are classified in Safety Class 3, and load-bearing devices connected with the above equipment, such as replaceable hoisting tools and auxiliary lifting devices. The regulating of hoisting and handling equipment comprises the following stages: handling of preliminary and final safety analysis reports, inspection of the construction plan, supervision of fabrication and construction inspection, and supervision of initial start-up and commissioning inspection

Waste Calcining Facility remote inspection report

International Nuclear Information System (INIS)

Patterson, M.W.; Ison, W.M.

1994-08-01

The purpose of the Waste Calcining Facility (WCF) remote inspections was to evaluate areas in the facility which are difficult to access due to high radiation fields. The areas inspected were the ventilation exhaust duct, waste hold cell, adsorber manifold cell, off-gas cell, calciner cell and calciner vessel. The WCF solidified acidic, high-level mixed waste generated during nuclear fuel reprocessing. Solidification was accomplished through high temperature oxidation and evaporation. Since its shutdown in 1981, the WCFs vessels, piping systems, pumps, off-gas blowers and process cells have remained contaminated. Access to the below-grade areas is limited due to contamination and high radiation fields. Each inspection technique was tested with a mock-up in a radiologically clean area before the equipment was taken to the WCF for the actual inspection. During the inspections, essential information was obtained regarding the cleanliness, structural integrity, in-leakage of ground water, indications of process leaks, indications of corrosion, radiation levels and the general condition of the cells and equipment. In general, the cells contain a great deal of dust and debris, as well as hand tools, piping and miscellaneous equipment. Although the building appears to be structurally sound, the paint is peeling to some degree in all of the cells. Cracking and spalling of the concrete walls is evident in every cell, although the east wall of the off-gas cell is the worst. The results of the completed inspections and lessons learned will be used to plan future activities for stabilization and deactivation of the facility. Remote clean-up of loose piping, hand tools, and miscellaneous debris can start immediately while information from the inspections is factored into the conceptual design for deactivating the facility

40 CFR 265.403 - Inspections.

Science.gov (United States)

2010-07-01

... must inspect, where present: (1) Discharge control and safety equipment (e.g., waste feed cut-off systems, by-pass systems, drainage systems, and pressure relief systems) at least once each operating day... equipment is being operated according to its design; (3) The construction materials of the treatment process...

Regulatory process for material handling equipment

International Nuclear Information System (INIS)

Rajendran, S.; Agarwal, Kailash

2017-01-01

Atomic Energy (Factories) Rules (AEFR) 1996, Rule 35 states, 'Thorough inspection and load testing of a Crane shall be done by a Competent Person at least once every 12 months'. To adhere to this rule, BARC Safety Council constituted 'Material Handling Equipment Committee (MHEC)' under the aegis of Conventional Fire and Safety Review Committee (CFSRC) to carry out periodical inspection and certification of Material Handling Equipment (MHE), tools and tackles used in BARC Facilities at Trombay, Tarapur and Kalpakkam

Licensing of non intrusive inspection equipment s for load and passengers vehicles that use X rays with energies up to 9 MeV. Mexican experience

International Nuclear Information System (INIS)

Munoz M, G. A.; Jimenez C, I.

2013-10-01

In the last years and like part of the extensive program of national security, in Mexico have been introduced a great quantity of non intrusive inspection equipment s for load and passengers vehicles that use X rays up to 9 MeV. Due to the great variety of equipment s, the Comision Nacional de Seguridad Nuclear y Salvaguardias (Mexican regulator organ) has established specific guidelines for their licensing and use supervision. In this work the adopted guidelines are exposed in the technical and administrative evaluation for the later licensing of these equipment s. Relative particular questions to the site of these equipment s and the impact in the public opinion that their use can generate are discussed. (author)

Designing for in-service inspection

International Nuclear Information System (INIS)

Dixit, K.B.

2002-01-01

The process of design of components, equipment and systems normally focuses on functional requirements, integrity and environmental conditions. Manufacturing processes, fabricability, inspectability and maintainability in service are considered while designing. Provisions for the requirements of ISI also need to be given due consideration while designing the systems, equipment and components

AECL experience in fuel channel inspection

Energy Technology Data Exchange (ETDEWEB)

Van Drunen, G. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada); Gunn, R. [Atomic Energy of Canada Limited, Mississauga, Ontario (Canada); Mayo, W.R. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada); Scott, D.A. [Atomic Energy of Canada Limited, Mississauga, Ontario (Canada)

1999-06-01

Inspection of CANDU fuel channels (FC) is performed to ensure safe and economic reactor operation. CANDU reactor FCs have features that make them a unique non-destructive testing (NDT) challenge. The thin, 4 mm pressure-tube wall means flaws down to about 0.1 mm deep must be reliably detected and characterized. This is one to two orders of magnitude smaller than is usually considered of significant concern for steel piping and pressure vessels. A second unique feature is that inspection sensors must operate in the reactor core--often within 20 cm of highly radioactive fuel. Work on inspection of CANDU reactor FCs at AECL dates back over three decades. In that time, AECL staff have provided equipment and conducted or supervised in-service inspections in about 250 FCs, in addition to over 8000 pre-service FCs. These inspections took place at every existing CANDU reactor except those in India and Romania. Early FC inspections focussed on measurement of changes in dimensions (gauging) resulting from exposure to a combination of neutrons, stress and elevated temperature. Expansion of inspection activities to include volumetric inspection (for flaws) started in the mid-1970s with the discovery of delayed hydride cracking in Pickering 3 and 4 rolled joints. Recognition of other types of flaw mechanisms in the 1980s led to further expansion in both pre-service and in-service inspections. These growing requirements, to meet regulatory as well as economic needs, led to the development of a wide spectrum of inspection technology that now includes tests for hydrogen concentration, structural integrity of core components, flaws, and dimensional change. This paper reviews current CANDU reactor FC inspection requirements. The equipment and techniques developed to satisfy these requirements are also described. The paper concludes with a discussion of work in progress in AECL aimed at providing state-of-the-art FC inspection services. (author)

Programmable - logic equipment for ultrasound periodic inspections of reactor pressure vessels

International Nuclear Information System (INIS)

Haniger, L.

1980-01-01

Two alternatives are presented of programmable logic corresponding to the 2nd generation of the apparatus for performing periodic ultrasonic inspections of power reactor pressure vessels and a solution is outlined of inspecting the circumferential weld on the pressure vessel head. The apparatus will allow using any measuring head taken into consideration for operational inspection. Command words are taken from a punched type reader. Czechoslovak made RAM memories are used. The algorithm of instrument function is supposed to be controlled by a microprocessor as soon as necessary preconditions for this technology are created in Czechoslovakia

Inspection of austenitic welds with ultrasonic phased array technology

Energy Technology Data Exchange (ETDEWEB)

Garcia, A.; Fernandez, F. [Tecnatom (Spain); Dutruc, R.; Ferriere, R. [Metalscan (France)

2011-07-01

This series of slides presents the use of ultrasonic phased array technology in the inspection of austenitic welds. The inspection from outside surface (the inspection is performed in contact using wedges to couple the probe to the outer surface of the component) shows that longitudinal wave is the most adequate for perpendicular scans and transversal ultrasonic wave is the most adequate for parallel scans. Detection and length sizing are performed optimally in perpendicular scans. The inspection from inside surface shows: -) Good results in the detection of defects (Sizing has met the requirements imposed by the Authority of the Russian Federation); -) The new design of the mechanical equipment and of the numerous ultrasonic beams refracted by the array probes has increased the volume inspected. The design of the mechanical equipment has also allowed new areas to be inspected (example a piping weld that was not accessible from the outer surface; -) The ultrasonic procedure and Inspection System developed have been validated by the Authority of the Russian Federation. Phase array technique supplies solutions to solve accessibility concerns and improve the ultrasonic inspections of nuclear components

Operation of inspection data acquisition and evaluation system

International Nuclear Information System (INIS)

Takahashi, Yoichi; Harada, Hiroshi; Watanabe, Masayuki; Sakaguchi, Makoto; Ishikawa, Masayuki

2016-01-01

Rokkasho Reprocessing Plant (RRP) is a large scale plant to treat a huge amount of Plutonium significant for safeguards. The LArge SCAle Reprocessing plant safeguards (LASCAR) Forum recommended an effective utilization of unattended verification systems and automated data acquisition system etc. Based on LASCAR recommendation, Nuclear Material Control Center (NMCC) has developed the inspection data acquisition system as the automated data acquisition system from the unattended verification systems (including non-destructive assay equipment, solution monitoring system and surveillance camera). The data gathered from the unattended verification system are provided to the inspection data evaluation system for the State and the IAEA. In this development, redundancy concepts for data transfer line, in order to prevent inspection data missing, were introduced, and the timely confirmation of solution behaver such as material flows and inventories by the solution monitoring can be achieved. Furthermore, for purpose of efficiency of evaluation of inspection activity for the State, NMCC has developed the inspection data evaluation system which operates automated partition of inspection data coming from each verification equipment. Additionally, the inspection data system evaluation can manage the inspection activities and their efforts. These development and operation have been funded by JSGO (Japan Safeguards Office). This paper describes development history and operation of the inspection data acquisition and evaluation system. (author)

Inspection of dissimilar metal welds in reactor pressure vessels in Spain

Energy Technology Data Exchange (ETDEWEB)

Gadea, J.R.; Regidor, J.J.; Pelaez, J.A.; Serrano, P. [Tecnatom, S.A., San Sebastian de los Reyes, Madrid (Spain)

2011-07-01

MRP-139 recommendations for inspection of dissimilar metal (DM) welds in PWR vessels were launched in the last years in the USA. Basically, it increases the frequency of the examinations in these type of welds, with major emphasis in the hot loops, adding one intermediate inspection at the ten years interval in outlet nozzles. The spanish nuclear power plants (NPP's) have begun the implementation of this type of inspections on the vessel nozzles DM welds. As this type of inspections could have an impact in the critical path duration of the outage, it is necessary the use of a mechanical equipment able to examine the nozzles DM welds in a short vessel occupation time (VOT) with high quality, qualified techniques and minimum requirements of the refuelling platform. Tecnatom undertook the design and development of a new more advanced equipment, named TENIS-DM, for implementing the reactor pressure vessel (RPV) nozzles examination. This equipment was designed in order to accomplish the stringent requirements and the updated examination techniques; it was used for the inspection of the DM welds of Asco 1 NPP inlet and outlet nozzles in March 2011. Examination techniques and procedures were qualified through the GRUVAL validation program, based on ENIC methodology. Mechanical scanner was equipped with a large number of examination probes, and TV cameras -for visual inspection and also for monitoring the ultrasonic inspections. A remote operated submarine was also used to give support to the operational personnel during the manipulation of the equipment and its movements from one nozzle to the others. During two months before the inspection, tests of the complete inspection system were made on a nozzle mock-up installed in a 4 meters deep well at Tecnatom's facilities; this scenario was also used during the training sessions of the inspection crew. The defined technical and practical objectives were achieved: use of qualified techniques and minimal impact on the

Inspection of dissimilar metal welds in reactor pressure vessels in Spain

International Nuclear Information System (INIS)

Gadea, J.R.; Regidor, J.J.; Pelaez, J.A.; Serrano, P.

2011-01-01

MRP-139 recommendations for inspection of dissimilar metal (DM) welds in PWR vessels were launched in the last years in the USA. Basically, it increases the frequency of the examinations in these type of welds, with major emphasis in the hot loops, adding one intermediate inspection at the ten years interval in outlet nozzles. The spanish nuclear power plants (NPP's) have begun the implementation of this type of inspections on the vessel nozzles DM welds. As this type of inspections could have an impact in the critical path duration of the outage, it is necessary the use of a mechanical equipment able to examine the nozzles DM welds in a short vessel occupation time (VOT) with high quality, qualified techniques and minimum requirements of the refuelling platform. Tecnatom undertook the design and development of a new more advanced equipment, named TENIS-DM, for implementing the reactor pressure vessel (RPV) nozzles examination. This equipment was designed in order to accomplish the stringent requirements and the updated examination techniques; it was used for the inspection of the DM welds of Asco 1 NPP inlet and outlet nozzles in March 2011. Examination techniques and procedures were qualified through the GRUVAL validation program, based on ENIC methodology. Mechanical scanner was equipped with a large number of examination probes, and TV cameras -for visual inspection and also for monitoring the ultrasonic inspections. A remote operated submarine was also used to give support to the operational personnel during the manipulation of the equipment and its movements from one nozzle to the others. During two months before the inspection, tests of the complete inspection system were made on a nozzle mock-up installed in a 4 meters deep well at Tecnatom's facilities; this scenario was also used during the training sessions of the inspection crew. The defined technical and practical objectives were achieved: use of qualified techniques and minimal impact on the critical

Boiler inspection manipulator for Torness Power Station

International Nuclear Information System (INIS)

Carrey, R.T.A.; Yule, I.Y.; Sibson, S.; Playle, M.J.

1996-01-01

The Advanced Gas-cooled Reactors at Torness and Heysham 2 are provided with dedicated access for remote inspection equipment. These in-service inspection (ISI) accesses comprise 12 penetrations above the core for inspection of the above core area and boilers, 12 below core penetrations for inspection of the lower boiler area and access through any of the 8 gas circulator penetrations for inspection of the sub-diagrid area. This paper describes a manipulator which will access the reactor from above the core via any of the 8 peripheral penetrations. (UK)

Licensee contractor and vendor inspection status report. Quarterly progress report, April 1996--June 1996

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-08-01

The federal government and nuclear industry have established a system for the inspection of commercial nuclear facilities to provide for multiple levels of inspection and verification. The Vendor Inspection System (VIS) of the Special Inspection Branch reviews and inspects the quality and suitability of vendor products, licensee-vendor interface, environmental qualification of equipment, and review of equipment problems found during operation and their corrective action. This report contains copies of all vendor inspection reports issued during the calendar year for which it is published.

Licensee contractor and vendor inspection status report. Quarterly progress report, April 1996--June 1996

International Nuclear Information System (INIS)

1996-08-01

The federal government and nuclear industry have established a system for the inspection of commercial nuclear facilities to provide for multiple levels of inspection and verification. The Vendor Inspection System (VIS) of the Special Inspection Branch reviews and inspects the quality and suitability of vendor products, licensee-vendor interface, environmental qualification of equipment, and review of equipment problems found during operation and their corrective action. This report contains copies of all vendor inspection reports issued during the calendar year for which it is published

Subsea Infrastructure Inspection

DEFF Research Database (Denmark)

Mai, Christian; Pedersen, Simon; Hansen, Leif

2016-01-01

Due to the increasing energy demands, the offshore energy business has boomed in recent decades. Sub-sea pipeline and power transmission cable installations are commonly applied worldwide. Any potential breakages can cause equipment damage and also damage the environment. The majority...... (S-AUVs) can significantly change the inspections of infrastructure, as these vehicles could be much cheaper to deploy. S-AUVs can potentially conduct faster data collection and provide higher inspection data quality. However, there are still some technical challenges related to: underwater wireless...

Utilization of aging program results in plant inspections

International Nuclear Information System (INIS)

Gunther, W.; Fullwood, R.

1989-01-01

Research conducted under the auspices of the US Nuclear Regulatory Commission Nuclear Plant Aging Research (NPAR) Program has resulted in a large data base of component and system operating experience. This data base has been used to determine equipment aging susceptibility and the potential for equipment aging to impact plant safety and reliability. Methods of detecting and mitigating component and system aging have also been identified. This paper discusses how the NPAR results could be used to focus inspection activities on age-sensitive components and systems and on the specific modes and mechanisms of age degradation. These activities range from the regular inspections conducted by resident inspectors to extensive special inspections such as the Safety System Functional Inspection typically conducted by a team of inspectors. 5 refs., 3 figs., 1 tab

Utilization of aging program results in plant inspections

International Nuclear Information System (INIS)

Gunther, W.; Fullwood, R.

1988-01-01

Research conducted under the auspices of the US Nuclear Regulatory Commission Nuclear Plant Aging Research (NPAR) Program has resulted in a large data base of component and system operating experience. This data base has been used to determine equipment aging susceptibility and the potential for equipment aging to impact plant safety and reliability. Methods of detecting and mitigating component and system aging have also been identified. This paper discusses how the NPAR results could be used to focus inspection activities on age-sensitive components and systems and on the specific modes and mechanisms of age degradation. These activities range from the regular inspections conducted by resident inspectors to extensive special inspections such as the Safety System Functional Inspection typically conducted by a team of inspectors. 5 refs., 3 figs., 1 tab

Development of Universal Methodology of Specimen Free Nondestructive Inspection (Control) of Mechanical Properties of NPP Equipment Metal in all Stages of Lifetime

International Nuclear Information System (INIS)

Bakirov, M.; Chubarov, S.; Frolov, I.; Kiselev, I.; Gastrock, J.; Dripke, M.

2011-01-01

Ever-increasing requirements for reliability and safety of equipment in nuclear power plants (NPP) dictate a necessity to obtain reliable and validated information about the condition of materials in the most safety-relevant and economically vital systems structures and components (SSC). Thus it is a state of science and technology approach to use one method, one methodic and one methodology to facilitate these goals with the purpose of keeping NPPs operating safely by virtue of knowing the state of ageing they are in (with respect to design limits and margins). Method of the control/measurement/testing - how to conduct measurements; methodic - how to interpret the results of measurement; methodology - the program of the control/inspection and testing programmes: localities to conduct the tests, how often, and to follow evolution of test results with the aim of acting before a failure occurs. Such methodology should be based on the use of specimen-free nondestructive method of the inspection (control), which could be used, successfully at all stages of life cycle of the equipment: manufacturing, construction, installation of NPP, operation and during the NPP operation through integration into the Plant Life Management (PLiM) Programme. It will facilitate a real picture of change (degradation) of a SSC material's condition in the zones subjected to the harshest stressors (neutron irradiation, erosion-corrosion/flow, thermal fatigue, vibration etc). Currently, there are various approaches used in the world to follow NPP ageing degradation, but until now, no specific methodology is used that could supply all the necessary information. Therefore, there is no way to use various results. Thanks to considerable advances over the last 20 years or so, the science of hardness testing offers an elegant, non-destructive way to obtain vital materials properties - even in-situ on operating SSC. In particular, the material's elastic-plastic condition may be measured, giving

Remote inspection system for nuclear power plants

International Nuclear Information System (INIS)

Inagaki, K.; Fujii, M.; Doi, A.; Harima, T.

1977-01-01

A remote inspection system for nuclear power plants was constructed based on an analysis of inspections performed by an operator on patrol. This system consists of an operator's console and a remote station. The remote station, equipped with five kinds of sensors, is steered along the inspection route by a photoelectric guiding system or may be manually controlled from an operator's console in a main control room. Signals for control and inspection data are multiplexed and transmitted through a coaxial cable

Chapter 4. Assessment and inspection of nuclear installations

International Nuclear Information System (INIS)

2001-01-01

Supervisory activity of Nuclear Regulatory Authority of the Slovak Republic (UJD) upon the safety of nuclear installations in compliance with the 'Atomic Act' and other legal regulations includes also inspection and assessment activities of UJD. Assessment activity of UJD in relation to nuclear installations lies in assessment of safety documentation for constructions realised as nuclear installations, or constructions through which changes are realised on nuclear installations. The scope of safety documentation required for the assessment is stipulated in the Atomic Act. In 2000 the assessment activity focused first of all on Unit 1 of NPP Bohunice after completing its Gradual Reconstruction Programme, on National Repository of Radioactive waste in Mochovce and on radioactive waste conditioning and treatment technology in Jaslovske Bohunice. Activities of UJD in assessment focused mainly on control of compliance with requirements for nuclear safety, assessment of commissioning programmes, operating procedures, limits and conditions, etc. The assessment of changes, which influence nuclear safety of nuclear installations in operation, realisation of which is conditioned by the approval from UJD, is a significant part of the assessment activity of UJD. Mainly it is the assessment of design changes, changes in limits and conditions, operating procedures, changes in programmes of periodical testing of equipment important in terms of nuclear safety, changes in physical protection of nuclear equipment, etc. The assessment of nuclear installations operational safety, based on assessment of operational events, on maintaining limits and conditions of safe operation, on operational safety performance indicators and on inspection results is a separate category in the assessment activity of UJD. Inspection activity specified in the 'Atomic Act' is governed by an internal guideline, an important part of which is an annual inspection plan that considers the following types of

Magnetic particle inspection

Science.gov (United States)

Sastri, Sankar

1990-01-01

The purpose of this experiment is to familiarize the student with magnetic particle inspection and relate it to classification of various defects. Magnetic particle inspection is a method of detecting the presence of cracks, laps, tears, inclusions, and similar discontinuities in ferromagnetic materials such as iron and steel. This method will most clearly show defects that are perpendicular to the magnetic field. The Magnaglo method uses a liquid which is sprayed on the workpiece to be inspected, and the part is magnetized at the same time. The workpiece is then viewed under a black light, and the presence of discontinuity is shown by the formation of a bright indication formed by the magnetic particles over the discontinuity. The equipment and experimental procedures are described.

What kinds of injuries do OSHA inspections prevent?

Science.gov (United States)

Haviland, Amelia; Burns, Rachel; Gray, Wayne; Ruder, Teague; Mendeloff, John

2010-08-01

OSHA's enforcement program is one of the major public efforts to protect American workers. We examine both the scope of injury prevention that inspections can contribute and the types of standards that contribute the most. We linked Pennsylvania Department of Labor and Industry files for lost-time injuries and employment to calculate injury rates for 1998-2005 for all single-establishment manufacturing firms. We linked these to OSHA inspection records. Inspections with penalties did affect injury types unrelated to standards as well as those related. We also found again that citations for violations of the standard requiring personal protective equipment had the largest impact on preventing injuries. Programs requiring protective equipment use deserve added attention from consultants and inspectors. In addition, some inspections spur managers to undertake safety measures that go beyond compliance with standards. 2010 Elsevier Ltd. All rights reserved.

GIMIS - Integral Solution for the In-Service Inspection Management of Components in NPPs

International Nuclear Information System (INIS)

Borovic, Damir; Vukovic, Igor

2014-01-01

Performance of in-service testing and inspection of components and systems in nuclear power plants are required in order to maintain the nuclear power plant while in operation and to return the plant to service, following plant outages. GIMIS is comprehensive software that integrates all processes, functions and data related to planning, administrating and executing inspections on systems, structures and components in nuclear power plants. The software is designed as a web application developed using the Microsoft ASP.NET technology, database is a Microsoft SQL, and client is composed of JavaScript frameworks. It can be adapted to local language, regulations, and requirements according to the power plant needs. The application consists of seven interdependent modules, namely: components, equipment, personnel, requirements, inspection planning, inspection execution, and reports. GIMIS deals with component, equipment and personnel management (both internally employed and outsourced), also provides full component history including uploaded documentation, drawings, previous inspection results, and supports various types of requirements. It enables scheduling facilitation using component data and compliance requirements, offers generation of all inspection relevant documentation and reports, and covers the equipment management including calibration requirements, certification of equipment and allocation to specific inspections/outages, as well as personnel certifications and allocation to specific inspections/outages. The paper describes the content and functionality of the GIMIS application and provides information of its built-in capabilities and features. (authors)

International cooperation in production inspections

International Nuclear Information System (INIS)

Limousin, S.

2009-01-01

Nuclear pressure equipment, like the reactor pressure vessel or steam generators, are manufactured in many countries all around the world. As only few reactors were built in the 90's, most of the nuclear safety authorities have lost part of their know how in component manufacturing oversight. For these two reasons, vendor inspection is a key area for international cooperation. On the one hand, ASN has bilateral relationships with several countries (USA, Finland, China...) to fulfill specific purposes. On the other hand, ASN participates in international groups like the MDEP ( Multinational Design Evaluation Program). A MDEP working group dedicated to vendor inspection cooperation enables exchanges of informations (inspection program plan, inspection findings...) among the regulators. Join inspections are organized. International cooperation could lead in the long term to an harmonization of regulatory practices. (author)

Improvements in televisual and photographic inspections of AGRs

International Nuclear Information System (INIS)

Hayter, R.; Wadsworth, A.

1988-01-01

The visual inspection techniques and equipment used at AGR Power Stations have been improved and updated in the light of need and technological advance, new equipment being developed and introduced where necessary. Specifically this report covers the development and use of: a short TRIUMPH compatible photographic camera 600 mm long x 75 mm dia taking 50 shots on a 35 mm film; a 240 mm dia photographic pod taking high quality 70 mm format photographs of large in-reactor volumes; a photographic camera of cross section 37 x 17 mm for the inspection of helically wound AGR boilers and the subsequent development of this latter device into a state of the art TV inspection camera. (author)

Use of remote visual in-service inspection on nuclear power plants of the CEGB

International Nuclear Information System (INIS)

James, D.W.

1985-01-01

The main responsibility of the Remote Inspection Group is the design, development and procurement of the remote visual inspection equipment provided by the Generation Development and Construction Division as part of the extent of the supply for all the Central Electricity Generating Board's (CEGB) advanced gas-cooled reactors (AGR). The paper describes the operation of this equipment, together with the low light-level TV cameras that have been developed for carrying out routine remote visual inspections. The camera, known as the television remote inspection unit multi-purpose head (TRIUMPH), has been designed as a series of modules. With this system it is possible to take advantage of improvements in a particular part of the camera system and to arrange to backfit an improved module to existing TRIUMPHs. To minimize the time for carrying out routine inspections during shutdown, the AGRs have been provided with storage training and test facilities. These facilities are provided with full size mock-ups of the reactor internals so that the inspection equipment can be tested and the operating staff trained before the equipment is used on the reactor. One of the other responsibilities of the Remote Inspection Group is to carry out specific power plant remote visual inspections which are required to minimize costly plant shutdowns and construction delays. Examples are given of successful inspections that have been carried out. Over 12 years' experience has now been obtained in carrying out, at short notice, difficult inspections which involve tortuous access routes. The CEGB now holds a wide range of fibrescope and small TV cameras, together with the equipment for placing the viewing device in the correct location. A number of special fibrescopes have been developed for specific inspection needs and details of these, together with other fibrescopes owned by the CEGB, are provided. (author)

Hoisting appliances and fuel handling equipment at nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

NONE

1988-12-31

The guide is followed by the Finnish Centre for Radiation and Nuclear Safety (STUK) in regulating hoisting and handling equipment Class 3 at nuclear facilities. The guide is applied e.g. to the following equipment: reactor building overhead cranes, hoisting appliances at nuclear fuel storages, fuel handling machines, other hoisting appliances, which because of nuclear safety aspects are classified in Safety Class 3, and load-bearing devices connected with the above equipment, such as replaceable hoisting tools and auxiliary lifting devices. The regulating of hoisting and handling equipment comprises the following stages: handling of preliminary and final safety analysis reports, inspection of the construction plan, supervision of fabrication and construction inspection, and supervision of initial start-up and commissioning inspection. 36 refs. Translation. The original text is published under the same guide number. The guide is valid from 5 January 1987 and will be in force until further notice.

Gentilly 2 steam generators Spring 2000 outage: tubesheet waterlance cleaning and inspection; upper bundle inspection

International Nuclear Information System (INIS)

Akeroyd, J.K.; Plante, S.

2000-01-01

A review of the secondary side maintenance activities recently completed during the Gentilly 2 Annual Spring 2000 Maintenance Outage. Activities included: 1) Tubesheet intertube waterlance cleaning and visual inspection, 2) First tube support plate, in-bundle visual inspection of the hot leg, and 3) Upper bundle tube support plate visual inspection. A description of the waterlancing and inspection equipment and setup in the RB at Gentilly 2 is provided. Several innovative techniques were successfully employed and yielded savings in critical path duration, labour and personnel radiation dose. These included accessing the SG tubesheet region through one handhole only and sludge removal utilizing the SG blowdown system. Plant personnel judged tubesheet sludge removal successful. Before and after results of the cleaning process along with samples of the visual inspection results are provided. Inspection of the first support plate, which was a repeat of an inspection done in 1997, was conducted along with an in-bundle inspection of the upper tube supports. Results are presented along with a discussion of the implications for future steam generator maintenance. (author)

Seismic resistance of WWER equipment (systematization and generalization)

International Nuclear Information System (INIS)

Kaznovski, S.; Chechenov, H.

1999-01-01

Within the scope of the contract with IAEA, calculational and experimental investigations of equipment seismic resistance were carried out. Systematic seismic inspection was conducted for 21 WWER type reactors in Armenia, Bulgaria, Russia, Slovakia and Ukraine. On the base of generalisation of extensive real data accumulated during inspection of equipment seismic resistance at different WWER-type NPPs the classification of seismic instability reasons and working out of generalised recommendations were carried out. It gives the possibility to specialists in many cases to expose the seismic insufficiency of equipment and to choose the suitable measures without laborious experimental investigations, tests, and calculations

Verification tests for remote controlled inspection system in nuclear power plants

International Nuclear Information System (INIS)

Kohno, Tadaaki

1986-01-01

Following the increase of nuclear power plants, the total radiation exposure dose accompanying inspection and maintenance works tended to increase. Japan Power Engineering and Inspection Corp. carried out the verification test of a practical power reactor automatic inspection system from November, 1981, to March, 1986, and in this report, the state of having carried out this verification test is described. The objects of the verification test were the equipment which is urgently required for reducing radiation exposure dose, the possibility of realization of which is high, and which is important for ensuring the safety and reliability of plants, that is, an automatic ultrasonic flaw detector for the welded parts of bend pipes, an automatic disassembling and inspection system for control rod driving mechanism, a fuel automatic inspection system, and automatic decontaminating equipments for steam generator water chambers, primary system crud and radioactive gas in coolant. The results of the verification test of these equipments were judged as satisfactory, therefore, the application to actual plants is possible. (Kako, I.)

Development of remote automatic equipment for BWR power plants

International Nuclear Information System (INIS)

Sasaki, Masayoshi

1984-01-01

The development of remote control, automatic equipment for nuclear power stations has been promoted to raise the rate of operation of plants by shortening regular inspection period, to improve the safety and reliability of inspection and maintenance works by mechanization, to reduce the radiation exposure dose of workers and to reduce the manpower required for works. The taking-off of control rod drives from reactors and fixing again have been mechanized, but the disassembling, cleaning, inspection and assembling of control rod drives are manually carried out. Therefore, Hitachi Ltd. has exerted effort to develop the automatic equipment for this purpose. The target of development, investigation, the construction and function of the equipment, the performance and the effect of adopting it are reported. The equipment for the volume reduction of spent fuel channel boxes and spent control rods is developed since these are major high level radioactive solid wastes, and their apparent volume is large. Also the target of development, investigated things, the construction and function of the equipment, the performance and the effect of adopting it are reported. (Kako, I.)

Inspection technologies -Development of national safeguards technology-

International Nuclear Information System (INIS)

Hong, J. S.; Kim, B. K.; Kwack, E. H.

1996-12-01

17 facility regulations prepared by nuclear facilities according to the Ministerial Notices were evaluated. Safeguards inspection activities under Safeguards are described. Safeguards inspection equipments and operation manuals to be used for national inspection are also described. Safeguards report are produced and submitted to MOST by using the computerized nuclear material accounting system at state level. National inspection support system are developed to produce the on-site information for domestic inspection. Planning and establishment of policy for nuclear control of nuclear materials, international cooperation for nuclear control, CTBT, strengthening of international safeguards system, and the supply of PWRs to North Korea are also described. (author). 43 tabs., 39 figs

Development and operation of the Above Dome Inspection Rig (ADIR)

International Nuclear Information System (INIS)

Dickson, R.P.; Moorby, J.

1984-01-01

Hinkley Point 'B' is developing its remote inspection equipment in order to be able to inspect reactor internals adequately without manned vessel entry. The Above Dome Inspection Rig has been built to allow a number of inspection systems to be introduced and operated within the reactor. The ability to introduce, use and remove inspection equipment without the necessity to lift the rig from the reactor is a vital feature in the speed achieved in completing inspections quickly. Television was selected for the A.D.M. because it has significant advantages in terms of operational convenience. However the quality of image obtained in terms of information available compares unfavourably with photography. The sharpness of a photographic image is largely dictated by the chemical structure of the emulsion, whereas video is limited by the picture line structure and bandwidth. The need for a photographic system for in reactor use is therefore essential for high definition inspection requirements. The first inspection system that has been developed for the ADIR is the Telefilm camera. It consists of a Hasselblad photographic camera using an Insight television camera looking through its viewfinder. The characteristics of television and photography have been combined. (author)

Quality assurance for IAEA inspection planning

International Nuclear Information System (INIS)

Markin, J.T.

1986-01-01

Under the provisions of the Treaty on Nonproliferation of Nuclear Weapons and other agreements with states, the International Atomic Energy Agency (IAEA) conducts inspections at nuclear facilities to confirm that their operation is consistent with the peaceful use of nuclear material. The Department of Safeguards at the IAEA is considering a quality assurance program for activities related to the planning of these facility inspections. In this report, we summarize recent work in writing standards for planning inspections at the types of facilities inspected by the IAEA. The standards specify the sequence of steps in planning inspections, which are: (1) administrative functions, such as arrangements for visas and travel, and communications with the state to confirm facility operating schedules and the state's acceptance of the assigned inspectors; (2) technical functions including a specification of the required inspection activities, determination of personnel and equipment resources, and a schedule for implementing the inspection activities at the facility; and (3) management functions, such as pre- and post-inspection briefings, where the planned and implemented inspection activities are reviewed

Color image digitization and analysis for drum inspection

International Nuclear Information System (INIS)

Muller, R.C.; Armstrong, G.A.; Burks, B.L.; Kress, R.L.; Heckendorn, F.M.; Ward, C.R.

1993-01-01

A rust inspection system that uses color analysis to find rust spots on drums has been developed. The system is composed of high-resolution color video equipment that permits the inspection of rust spots on the order of 0.25 cm (0.1-in.) in diameter. Because of the modular nature of the system design, the use of open systems software (X11, etc.), the inspection system can be easily integrated into other environmental restoration and waste management programs. The inspection system represents an excellent platform for the integration of other color inspection and color image processing algorithms

Proceedings of a specialist meeting on the ultrasonic inspection of reactor components

International Nuclear Information System (INIS)

1976-01-01

Beside synthesis of two conferences on nondestructive testing and on inspection, the contributions of this conference are reporting experimental observations and research works on ultrasonic techniques, methods, procedures (pre-service or in-service) and equipment for the inspection of nuclear reactor components (pressure vessels, tubing and piping), generally in stainless steel (often austenitic or ferritic) material or in zirconium alloy. Some contributions are also dealing with the relationship between material microstructure and ultrasonic inspection method and equipment, or with the detection and sizing precision of flaws (cracks)

Development of ultrasonic testing equipment incorporating electromagnetic acoustic transducer

International Nuclear Information System (INIS)

Sato, Michio; Kimura, Motohiko; Okano, Hideharu; Miyazawa, Tatsuo; Nagase, Koichi; Ishikawa, Masaaki

1989-01-01

An ultrasonic testing equipment for use in in-service inspection of nuclear power plant piping has been developed, which comprises an angle-beam electromagnetic acoustic transducer mounted on a vehicle for scanning the piping surface to be inspected. The transducer functions without direct contact with the piping surface through couplant, and the vehicle does not require a guide track installed on the piping surface, being equipped with magnetic wheels that adhere to the piping material, permitting it to travel along the circumferential weld joint of a carbon steel pipe. The equipment thus dispenses with the laborious manual work involved in preparing the piping for inspection, such as removal of protective coating, surface polishing and installation of guide track and thereby considerably reduces the duration of inspection. The functioning principle and structural features of the transducer and vehicle are described, together with the results of trial operation of a prototype unit, which proved a 1mm deep notch cut on a test piece of 25mm thick carbon steel plate to be locatable with an accuracy of ±2mm. (author)

The Opportunities and Challenges of Bringing New Metrology Equipment to Market

Science.gov (United States)

Perloff, David S.

2005-09-01

This paper provides an overview of the economic and technological factors which are driving the demand for new metrology and inspection equipment, the challenges and opportunities facing new companies in bringing such equipment to market, and the funding environment in which new companies must raise capital to finance their efforts. Seven metrology companies and one inspection equipment company that have received first-time venture backing since 2000 are used to illustrate how these specialized businesses are launched and funded.

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)

Radiographic inspection on offshore platforms

International Nuclear Information System (INIS)

Soares, Sergio Damasceno; Sperandio, Augusto Gasparoni

1994-01-01

One of the great challenges for non-destructive inspection is on offshore platforms, where safety is a critical issue. Inspection by gammagraphy is practically forbidden on the platform deck due to problems to personnel safety and radiological protection. Ir-192 sources are used and the risk of an accident with loss of radioisotope must be considered. It is unfeasible to use gammagraphy, because in case of an accident the rapid evacuation from the platform would be impossible. This problem does not occur when X-ray equipment is used as the radiation source. The limited practicality and portability of the X-ray equipment have prevented its use as a replacement for the gammagraphy. This paper presents the preliminary tests to see the viable use of radiographic tests with constant potential on offshore platforms. (author). 2 refs., 1 fig., 2 tabs, 3 photos

In-service inspections of V-230 reactor

International Nuclear Information System (INIS)

Prepechal, J.

1984-01-01

It is stated that despite certain constraints the configuration of the WWER-440 is such that it allows to make in-service inspections on a fully satisfactory scale. Three factors are discussed whose existence is necessary for the implementation of in-service inspections. The program defining the scale of inspections is satisfactory with regard to the safety and reliability of reactor operation. Its further development must result in reducing time consumption and radiation burden of personnel. Regulations for the implementation and evaluation of inspections represent the weakest link in the system of in-service inspections. At present, various organizations are dealing with the said problem within international cooperation. Equipment for in-service inspections of WWER-440 reactors is relatively good. The most important knowledge is summed up gained from the ten pre-service and in-service inspections of reactors of this type made so far. (Z.M.)

DWPF liquid sample station: Status of equipment development

International Nuclear Information System (INIS)

Caplan, J.R.

1987-01-01

This report summarizes operating experience and equipment status of the DWPF liquid sample cell. Operation hours to date, results of equipment inspections and problems encountered and their solutions are discussed. An equipment and instrumentation status updating DPST-85-592, DWPF LIQUID SAMPLE CELL MOCK-UP, is presented. Remaining development items are also outlined

Handling system for nuclear fuel pellet inspection

International Nuclear Information System (INIS)

Nyman, D.H.; McLemore, D.R.; Sturges, R.H.

1978-11-01

HEDL is developing automated fabrication equipment for fast reactor fuel. A major inspection operation in the process is the gaging of fuel pellets. A key element in the system has been the development of a handling system that reliably moves pellets at the rate of three per second without product damage or excessive equipment wear

Remote inspection of steam turbine blades

International Nuclear Information System (INIS)

Anon.

1987-01-01

During the past five years Reinhart and Associates, Inc. has been involved in remote examination of L-0 and L-1 steam turbine blade rows of in-place LP turbines using visual and eddy current techniques. These tests have concentrated on the trailing edge and blade-to-rotor attachment (Christmas tree) areas. These remote nondestructive examinations were performed through hand access ports of the inner shell. Since the remote scanning system was in a prototype configuration, the inspection was highly operator-dependent. Refinement of the scanning equipment would considerably improve the efficiency of the test; however, the feasibility of remote in-place inspection of turbine blades was established. To further improve this technology, and to provide for remote inspection of other areas of the blade and additional turbine designs, EPRI is funding a one-year project with Reinhart and Associates, Inc. This project will develop a new system that employs state-of-the-art multifrequency eddy current techniques, a miniature charged coupled device (CCD) television camera, and remote positioning equipment. Project results from the first six months are presented

Ultrasonic inspection experience of steam generator tubes at Ontario Hydro and the TRUSTIE inspection system

International Nuclear Information System (INIS)

Choi, E.I.; Jansen, D.

1998-01-01

Ontario Hydro have been using ultrasonic test (UT) technique to inspect steam generator (SG) tubes since 1993. The UT technique has higher sensitivity in detecting flaws in SG tubes and can characterize the flaws with higher accuracy. Although an outside contractor was used initially, Ontario Hydro has been using a self-developed system since 1995. The TRUSTIE system (Tiny Rotating UltraSonic Tube Inspection Equipment) was developed by Ontario Hydro Technologies specifically for 12.7 mm outside diameter (OD) tubes, and later expanded to larger tubes. To date TRUSTIE has been used in all of Ontario Hydro's nuclear generating stations inspecting for flaws such as pitting, denting, and cracks at top-of-tubesheet to the U-bend region. (author)

Incore inspection device

International Nuclear Information System (INIS)

Ogisu, Tatsuki; Taguchi, Kosei.

1995-01-01

The device of the present invention can inspect surfaces of equipments in reactor water in a nuclear reactor in a state of atmospheric air. Namely, an inspection device is movable forwardly and backwardly in a water-proof vessel. An annular sucker with pleats is disposed to the outer side of a lid of the water-proof vessel. A television camera for an under water monitoring is disposed to the inner side of the lid of the water-proof vessel by way of a partitioning wall with lid. Transferring screws are disposed at the back and on the side of the water-proof vessel. In the device having such a constitution, (1) the inside of the water-proof vessel is at first made water-tight by closing the partitioning wall with lid, (2) the back and the side screws are operated by the guide of the underwater monitoring television camera, to transfer the water-proof vessel to the surface of the reactor core to be inspected, (3) the annular sucker with pleats is urged on the surface to be inspected by the back screw, to fix the water-proof vessel, (4) reactor water in a space of the annular sucker with pleats is discharged and replaced with air, and (5) the lid of the partition wall with lid is opened and the inspection device is disposed at a position of the underwater monitoring television camera, to inspect the surface to be inspected in a state of atmospheric air. (I.S.)

Comparison of API 510 pressure vessels inspection planning with API 581 risk-based inspection planning approaches

International Nuclear Information System (INIS)

Shishesaz, Mohammad Reza; Nazarnezhad Bajestani, Mohammad; Hashemi, Seyed Javad; Shekari, Elahe

2013-01-01

To ensure mechanical integrity, all pressure vessels shall be inspected at the intervals provided in inspection codes or based on a risk-based inspection (RBI) assessment. The RBI assessment may allow previously established inspection intervals to be extended. This paper describes the methodology, analysis and results of two RBI studies conducted on 293 pressure vessel components in two crude oil distillation units. Based on API RBI methodology in API 581 (2008), risk target concept was used for determining inspection dates. It was shown that when thinning is the major active damage, the RBI recommended intervals are as long as twice the API 510 intervals. This paper summarizes that, as a fundamental step in the risk calculation, RBI has a more defined methodology for evaluating equipment for multiple damage mechanisms and a more defined approach to specify the use of other inspection technologies beyond the traditional visual, ultrasonic, and radiography tests. -- Highlights: • RBI calculated inspection intervals are as long as twice of API 510 inspection code. • Two case studies verified the advantage of RBI in inspection planning. • RBI is a more reliable methodology when evaluating multiple damage mechanisms. • Damage factor calculations can be used for determining RSFa value in FFS assessments

33 CFR 106.255 - Security systems and equipment maintenance.

Science.gov (United States)

2010-07-01

... 33 Navigation and Navigable Waters 1 2010-07-01 2010-07-01 false Security systems and equipment... Shelf (OCS) Facility Security Requirements § 106.255 Security systems and equipment maintenance. (a) Security systems and equipment must be in good working order and inspected, tested, calibrated, and...

Ultrasonic inspection of the Calder Hall and Chaplecross reactor pressure vessels

International Nuclear Information System (INIS)

Pennick, A.M.

1993-01-01

This paper describes the ultrasonic inspection surveys that have recently been carried out on the Calder Hall and Chapelcross Magnox steel reactor pressure vessels. The development of the inspection system, which is based on the Rediman manipulator and uses the Sonomatic Zipscan equipment and Time-of-Flight diffraction techniques is discussed. The inspection results are presented and compared with the original inspection findings and limiting crack sizes. (author)

9 CFR 381.305 - Equipment and procedures for heat processing systems.

Science.gov (United States)

2010-01-01

... AND VOLUNTARY INSPECTION AND CERTIFICATION POULTRY PRODUCTS INSPECTION REGULATIONS Canning and Canned... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Equipment and procedures for heat processing systems. 381.305 Section 381.305 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE...

Wall thinning inspection technique for large-diameter piping using guided wave

International Nuclear Information System (INIS)

Miki, Masahiro; Nagashima, Yoshiaki; Endou, Masao; Kodaira, Kojiro; Maniwa, Kazuhiko

2009-01-01

Guided wave inspection technique is effective for detecting defects like corrosion in piping, because it can perform long range inspection. It is possible to expect this inspection as a method that leads to the decrease of the inspection process and its cost, because the incidental work can be reduced. Especially, the contraction effect of the inspection work is extensive in large-diameter piping inspection. In this paper, we introduce the guided wave inspection system to large-diameter piping. The feature is a guided wave sensor that can freely transform according to the curvature of inspection object, and portable inspection equipment. We discuss the result of detection examination for artificial wall-thinning in large-diameter piping using this system. (author)

9 CFR 355.17 - Tagging equipment “U.S. rejected.”

Science.gov (United States)

2010-01-01

... INSPECTION AND CERTIFICATION CERTIFIED PRODUCTS FOR DOGS, CATS, AND OTHER CARNIVORA; INSPECTION... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Tagging equipment âU.S. rejected.â 355.17 Section 355.17 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF...

NDT in inspection-repairing of boiler AE-101 of fertilizers Plant-Talara-Peru

International Nuclear Information System (INIS)

Torres, F.

1988-01-01

Experiences got from the use of NDT in inspection-repairing of boiler AE-101 of fertilizers Plant-Talara is presented after failures by pipes breakage. Applying liquid penetrant testing and visual inspection it was possible to determine the seriousness of the equipment the use of metallographic copies, ultrasonic measurements and hardness gave us an idea of the actual condition of the equipment, allowing a safe performance

14 CFR 91.409 - Inspections.

Science.gov (United States)

2010-01-01

... instructions for their use; (3) Enough housing and equipment for necessary disassembly and proper inspection of... rotorcraft unless the replacement times for life-limited parts specified in the aircraft specifications, type... time in service, calendar times, or cycles of operation accumulated under the previous program must be...

Optimizing and joining future safeguards efforts by 'remote inspections'

International Nuclear Information System (INIS)

Zendel, M.; Khlebnikov, N.

2009-01-01

Full-text: Remote inspections have a large potential to save inspection effort in future routine safeguards implementation. Such inspections involve remote activities based on the analysis of data acquired in the field without the physical presence of an inspector, shifting the inspectors' priorities further toward unannounced inspections, complementary access activities and data evaluation. Large, automated and complex facilities require facility resident and specific safeguards equipment systems with features for unattended and remotely controlled operation as well as being integrated in the nuclear process. In many instances the use of such equipment jointly with the SSAC/RSAC and the operator is foreseen to achieve affordable effectiveness with a minimum level of intrusiveness to the facility operation. Where it becomes possible to achieve independent conclusions by this approach, the IAEA would make full use of the SSAC/RSAC, involving State inspectors and/or facility operators to operate inspection systems under remotely controlled IAEA mechanisms. These mechanisms would include documented procedures for routine joint-use, defining arrangements for data sharing, physical security and authentication mechanisms, recalibration and use of standards and software, maintenance, repair, storage and transportation. The level of cooperation and willingness of a State to implement such measures requested and properly justified by the IAEA will demonstrate its commitment to full transparency in its nuclear activities. Examples of existing remote inspection activities, including joint-use activities will be discussed. The future potential of remote inspections will be assessed considering technical developments and increased needs for process monitoring. Enhanced cooperation with SSAC/RSAC within the framework of remote inspections could further optimize the IAEA's inspection efforts while at the same time maintaining effective safeguards implementation. (author)

Skills of Asn inspectors responsible for inspecting pressurised equipment

International Nuclear Information System (INIS)

Colonna, F.

2010-01-01

ASN relies on the unique competencies of its staff to assure that it can complete its mission of maintaining public health and safety. Since 1975, personnel at ASN Nuclear Pressure Equipment Department have played a major role in the oversight of pressure boundary equipment by verifying that equipment is manufactured in compliance with regulatory requirements. This has called for highly competent individuals trained in a variety of technical and regulatory backgrounds. ASN is meeting the challenge of keeping its staff trained and prepared to continue its oversight of nuclear boilers. This has included ensuring that its organization is welt suited to meet the demands, and relying on third-party experts when necessary. With the implementation of the 2006 transparency law, ASN has taken necessary steps to ensure that it will maintain its high level of expertise going forward. (author)

Risk based inspection for atmospheric storage tank

Science.gov (United States)

Nugroho, Agus; Haryadi, Gunawan Dwi; Ismail, Rifky; Kim, Seon Jin

2016-04-01

Corrosion is an attack that occurs on a metallic material as a result of environment's reaction.Thus, it causes atmospheric storage tank's leakage, material loss, environmental pollution, equipment failure and affects the age of process equipment then finally financial damage. Corrosion risk measurement becomesa vital part of Asset Management at the plant for operating any aging asset.This paper provides six case studies dealing with high speed diesel atmospheric storage tank parts at a power plant. A summary of the basic principles and procedures of corrosion risk analysis and RBI applicable to the Process Industries were discussed prior to the study. Semi quantitative method based onAPI 58I Base-Resource Document was employed. The risk associated with corrosion on the equipment in terms of its likelihood and its consequences were discussed. The corrosion risk analysis outcome used to formulate Risk Based Inspection (RBI) method that should be a part of the atmospheric storage tank operation at the plant. RBI gives more concern to inspection resources which are mostly on `High Risk' and `Medium Risk' criteria and less on `Low Risk' shell. Risk categories of the evaluated equipment were illustrated through case study analysis outcome.

Surveillance - filling the gap between audits and inspection

International Nuclear Information System (INIS)

Coulombe, C.T.

1987-01-01

Historically, two major verification activities are accomplished at nuclear plants: audits and inspections. Both have their roots firmly planted in regulation. They are required elements of a quality assurance (QA) program. Inspection, focused on hardware, verifies that equipment meets its specified requirements. Auditing, focused on documentation, verifies, through objective evidence, that the QA program is being effectively implemented. Quality surveillance, focused on performance, verifies effective use of the plant's procedures and quality program. The surveillance concept provides a method to assure that the gap between the inspection function and the audit function is filled in

Cecil gives in-bundle access for inspection and lancing [steam generators

International Nuclear Information System (INIS)

Trovato, S.A.; Ruggieri, S.K.

1989-01-01

Cecil (Consolidated Edison Combined Inspection and Lancing System) is a robotic device which makes it possible to take inspection and sludge lancing equipment deep inside steam generator tube bundles. Cecil is teleoperated to perform tube bundle inspections, sludge sampling and sludge lancing. The first field test of Cecil at Indian Point 2 reactor, successfully demonstrated its capability for high quality inspection, and its potential for improved sludge removal, both with reduced personnel radiation exposure. (U.K.)

75 FR 56015 - Vessel Inspection Alternatives

Science.gov (United States)

2010-09-15

... DEPARTMENT OF HOMELAND SECURITY Coast Guard 46 CFR Part 8 Vessel Inspection Alternatives CFR... Certificate; (ii) International Tonnage Certificate; (iii) Cargo Ship Safety Construction Certificate; (iv) Cargo Ship Safety Equipment Certificate; and (v) International Oil Pollution Prevention Certificate; and...

Mechanized inspection of steam generator components during manufacture

International Nuclear Information System (INIS)

Otte, H.-J.; Leupoldt, K.; Meister, W.

2009-01-01

Steam Generator (SG) parts are intensively inspected by UT in the course of the manufacturing process. These inspections - mostly performed manually using different codes - are time consuming and call for a sophisticated documentation, figuring part of the life time documentation package. In order to reduce time and costs mechanized inspection equipment is introduced, combining short inspection times, avoiding influence of the human factor and providing proper electronic storage of all inspection results prepared for comparison with data generated during in-service inspection. Since 2001 Cegelec delivered various UT systems for gas turbine disks and rotor ends called SIRO-MAN. Within only a few years the majority of important providers of such components successfully switched from manual inspection to mechanized inspection following the requirements of manufacturers like ALSTOM, GE and Siemens. The SIRO-MAN is now adapted to the needs of mechanized inspection of SG components. The inspection is performed on the products during rotation around the vertical axis. The multi - probe assemblies are manoeuvred on the products by a manipulator system backed by a NC control unit. Acoustic coupling of UT probes to the product surface is performed with oil or water in a closed circuit. UT and - if requested ET - data along with position information of the probe assembly provided by the control unit are acquired, processed and evaluated by an UT / ET electronic system delivered by either Olympus or ZETEC. As performed already on rotor ends a sequence of inspections using different parameter settings can be programmed with simple means (Teach In) so that such inspection sequence can be executed without operating personnel. Probe assemblies allow for individual operation of probes out of the probe assembly according to the individual needs. Conventional UT and phased array applications or combination of both techniques can be provided. The UT / ET electronic equipment offers

Ultrasonic inspection development at HEDL

International Nuclear Information System (INIS)

Day, C.K.; Mech, S.J.; Michaels, T.E.; Dixon, N.E.

1978-01-01

Ultrasonic testing methods and equipment are being developed to support preservice and in-service inspection of selected FFTF welds. A digital computer system is employed in the analysis of both simulated FFTF pipe sections and plate specimens containing fatigue cracks. It is anticipated that test evaluation standards containing fatigue cracks will partially eliminate questions formerly associated with weld test calibration producers by providing natural cracks which follow grain boundaries and stress patterns resembling piping situ conditions. Studies have revealed that commercial transducers may satisfy LMFBR ultrasonic pipe inspection applications: The test system evaluation included transducers and wedge coupling and fluid coupling materials which exhibited acceptable performance at temperatures to 2300C. Results are presented that demonstrate the feasibility of ultrasonic inspection of components immersed in sodium at temperatures to 2600C. (UK)

Remote repair and inspection technics in Tokai reprocessing plant

International Nuclear Information System (INIS)

Koyama, Kenji; Ishibashi, Yuzo; Otani, Yosikuni

1986-01-01

Tokai reprocessing plant of Power Reactor and Nuclear Fuel Development Corp. is the only factory in Japan which treats 0.7 t/day of the spent fuel from LWR power stations and recovers remaining uranium and newly produced plutonium. Since the reprocessing plant started the hot test in September, 1977, about eight years have elapsed, and 233 t of spent fuel was treated as of August, 1985. During this period, the development of various remote working techniques have been carried out to cope with the failure of equipment and to strengthen the preventive maintenance of equipment. In this report, the development of the techniques for the remote repair of leaking dissolving tanks and the development of the remote inspection system for confirming the soundness of equipment in cells are described. In nuclear facilities, from the viewpoint of the reduction of radiation exposure accompanying the works under high radiation, labor saving, the increase of capacity factor by shortening the period of repair works, the improvement of safety and reliability of the facilities by perfecting checkup and inspection and so on, it is strongly desired to put robots in practical use for maintenance and inspection. (Kako, I.)

46 CFR 159.007-5 - Production inspections and tests: Application for acceptance.

Science.gov (United States)

2010-10-01

... acceptance. 159.007-5 Section 159.007-5 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) EQUIPMENT, CONSTRUCTION, AND MATERIALS: SPECIFICATIONS AND APPROVAL APPROVAL OF EQUIPMENT AND MATERIALS...) Is accepted by the Commandant for approval inspections and tests of the equipment or material under...

Holographic inspection of nuclear plant

International Nuclear Information System (INIS)

Gordon, A.L.; Armour, I.A.; Glanville, R.; Malcolm, G.J.; Wright, D.G.

1988-01-01

The high resolution, enormous depth of field and high tolerance to radiation of holography mean that it has great potential as an inspection tool in the nuclear industry. In addition, the ability of double-pulse holography to yield detailed information on vibration over the whole field of both large and small structures provides measurements that often cannot be obtained in any other way. This paper reviews the development of equipment for the holographic inspection of nuclear fuel elements; a portable holocamera for use inside reactors; and the application of holographic techniques for vibration measurements in a nuclear power station. (author)

Development of manufacturing equipment and QC equipment for DUPIC fuel

International Nuclear Information System (INIS)

Yang, Myung Seung; Park, J.J.; Lee, J.W.; Kim, S.S.; Yim, S.P.; Kim, J.H.; Kim, K.H.; Na, S.H.; Kim, W.K.; Shin, J.M.; Lee, D.Y.; Cho, K.H.; Lee, Y.S.; Sohn, J.S.; Kim, M.J.

1999-05-01

In this study, DUPIC powder and pellet fabrication equipment, welding system, QC equipment, and fission gas treatment are developed to fabricate DUPIC fuel at IMEF M6 hot cell. The systems are improved to be suitable for remote operation and maintenance with the manipulator at hot cell. Powder and pellet fabrication equipment have been recently developed. The systems are under performance test to check remote operation and maintenance. Welding chamber and jigs are designed and developed to remotely weld DUPIC fuel rod with manipulators at hot cell. Remote quality control equipment are being tested for analysis and inspection of DUPIC fuel characteristics at hot cell. And trapping characteristics is analyzed for cesium and ruthenium released under oxidation/reduction and sintering processes. The design criteria and process flow diagram of fission gas treatment system are prepared incorporating the experimental results. The fission gas treatment system has been successfully manufactured. (Author). 33 refs., 14 tabs., 91 figs

Automated ultrasonic pipe weld inspection. Part 1

International Nuclear Information System (INIS)

Karl Deutsch, W.A.; Schulte, P.; Joswig, M.; Kattwinkel, R.

2006-01-01

This article contains a brief overview on automated ultrasonic welded inspection for various pipe types. Some inspection steps might by carried out with portable test equipment (e.g. pipe and test), but the weld inspection in all internationally relevant specification must be automated. The pipe geometry, the production process, and the pipe usage determine the number of required probes. Recent updates for some test specifications enforce a large number of ultrasonic probes, e.g. the Shell standard. Since seamless pipes are sometimes replaced by ERW pipes and LSAW pipes (in both cases to save production cost), the inspection methods change gradually between the various pipe types. Each testing system is unique and shows its specialties which have to be discussed by supplier, testing system user and final customer of the pipe. (author)

Advanced Approach of Reactor Pressure Vessel In-service Inspection

International Nuclear Information System (INIS)

Matokovic, A.; Picek, E.; Pajnic, M.

2006-01-01

The most important task of every utility operating a nuclear power plant is the continuously keeping of the desired safety and reliability level. This is achieved by the performance of numerous inspections of the components, equipment and system of the nuclear power plant in operation and in particular during the scheduled maintenance periods at re-fueling time. Periodic non-destructive in-service inspections provide most relevant criteria of the integrity of primary circuit pressure components. The task is to reliably detect defects and realistically size and characterize them. One of most important and the most extensive examination is a reactor pressure vessel in-service inspection. That inspection demand high standards of technology and quality and continual innovation in the field of non-destructive testing (NDT) advanced technology as well as regarding reactor pressure vessel tool and control systems. A remote underwater contact ultrasonic technique is employed for the examination of the defined sections (reactor welds), whence eddy current method is applied for clad surface examinations. Visual inspection is used for examination of the vessel inner surface. The movement of probes and data positioning are assured by using new reactor pressure vessel tool concept that is fully integrated with NDT systems. The successful performance is attributed thorough pre-outage planning, training and successful performance demonstration qualification of chosen NDT techniques on the specimens with artificial and/or real defects. Furthermore, use of advanced approach of inspection through implementation the state of the art examination equipment significantly reduced the inspection time, radiation exposure to examination personnel, shortening nuclear power plant outage and cutting the total inspection costs. The advanced approach as presented in this paper offer more flexibility of application (non-destructive tests, local grinding action as well as taking of boat samples

Application of corrosion screening tools for riser inspection

International Nuclear Information System (INIS)

Zamir Mohamed Daud; Vijayan, S.

2003-01-01

As offshore facilities approach the end of their design life, owners would like to assess the condition and integrity of plant and equipment. Detailed inspection, including non-destructive testing (NDT), are implemented and results are utilised for predictive maintenance and estimating useful remaining life. Except for risk based inspection, the extent of surface coverage required would be more compared to inspection of pre-determined spots. Risers, for example, usually have several layers of coating that prevent use of conventional techniques for inspection of corrosion. Complete coverage requires access (including removal coatings and insulation). Inspection utilising the conventional NDT tools can be very slow and expensive. However, recent advances have forwarded the use of specialised NDT techniques that were developed for inspection of corrosion under insulation (CUI). This paper details two screening inspection tools, LIXI Profiler and RTD-INCOTEST that have been applied to inspection of risers. LIXI Profiler is based on attenuation of penetrating radiation by materials, and RTD-INCOTEST is based on decay of pulsed eddy current in materials. (Author)

21 CFR 1210.15 - Pasteurization; equipment and methods.

Science.gov (United States)

2010-04-01

... 21 Food and Drugs 8 2010-04-01 2010-04-01 false Pasteurization; equipment and methods. 1210.15... UNDER THE FEDERAL IMPORT MILK ACT Inspection and Testing § 1210.15 Pasteurization; equipment and methods... into the United States shall employ adequate pasteurization machinery of a type easily cleaned and of...

In-service inspection of nuclear power-plant pressure components

International Nuclear Information System (INIS)

Lautzenheiser, C.E.

1976-01-01

The early light-water-reactor systems for production of commercial power were designed and fabricated in accordance with the codes then being used for fossil-fired power-generating stations with some design changes for increased inspectability during fabrication. Over the past few years, major strides have been made in in-service inspection technology. Work has been under way to determine the reliability of nondestructive testing methods and to develop formal inspection programs throughout the world. The major problems associated with in-service inspection are the scarcity of qualified personnel, the variability in procedures and data recording between inspection agencies, and exposure of inspection personnel to radiation. Further work will be required to more completely mechanize piping inspections to reduce radiation exposure and to standardize inspection procedures, equipment, and certification of personnel. Worldwide attention to the requirements of the American Society of Mechanical Engineers' Boiler and Pressure Vessel Code, the size and integrity of inspection agencies, and efforts such as the development of personnel qualification and certification guides emphasize the importance of in-service inspection to nuclear safety

24 CFR 84.34 - Equipment.

Science.gov (United States)

2010-04-01

... ADMINISTRATIVE REQUIREMENTS FOR GRANTS AND AGREEMENTS WITH INSTITUTIONS OF HIGHER EDUCATION, HOSPITALS, AND OTHER... the physical inspection and those shown in the accounting records shall be investigated to determine... requirement for the equipment exists in other Federal agencies. HUD shall issue instructions to the recipient...

Human performance in nondestructive inspections and functional tests: Final report

International Nuclear Information System (INIS)

Harris, D.H.

1988-10-01

Human performance plays a vital role in the inspections and tests conducted to assure the physical integrity of nuclear power plants. Even when technically-sophisticated equipment is employed, the outcome is highly dependent on human control actions, calibrations, observations, analyses, and interpretations. The principal consequences of inadequate performance are missed or falsely-reported defects. However, the cost-avoidance that stems from addressing potential risks promptly, and the increasing costs likely with aging plants, emphasize that timeliness and efficiency are important inspection-performance considerations also. Human performance issues were studied in a sample of inspections and tests regularly conducted in nuclear power plants. These tasks, selected by an industry advisory panel, were: eddy-current inspection of steam-generator tubes; ultrasonic inspection of pipe welds; inservice testing of pumps and valves; and functional testing of shock suppressors. Information was obtained for the study from industry and plant procedural documents; training materials; research reports and related documents; interviews with training specialists, inspectors, supervisory personnel, and equipment designers; and first-hand observations of task performance. Eleven recommendations are developed for improving human performance on nondestructive inspections and functional tests. Two recommendations were for the more-effective application of existing knowledge; nine recommendations were for research projects that should be undertaken to assure continuing improvements in human performance on these tasks. 25 refs., 9 figs., 1 tab

Risk-based inspection--Development of guidelines

International Nuclear Information System (INIS)

1993-07-01

Effective inservice inspection programs can play a significant role in minimizing equipment and structural failures. Most of the current inservice inspection programs for light water reactor (LWR) nuclear power plant components are based on experience and engineers' qualitative judgment. These programs include only an implicit consideration of risk, which combines the probability of failure of a component under its operation and loading conditions and the consequences of such failure, if it occurs. This document recommends appropriate methods for establishing a risk-based inspection program for LWR nuclear power plant components. The process has been built from a general methodology (Volume 1) and has been expanded to involve five major steps: defining the system; evaluating qualitative risk assessment results; using this and information from plant probabilistic risk assessments to perform a quantitative risk analysis; selecting target failure probabilities; and developing an inspection program for components using economic decision analysis and structural reliability assessment methods

A study on the test of efficiency of the diagnostic X-ray equipment according to their rectifications

International Nuclear Information System (INIS)

Seon, Jong Ryul

1997-01-01

For the efficient management of the diagnostic x-ray equipment, a nation-wide inspection of hospitals was performed by an inspection institute in Taejon in the first half of 1997. Among those hospitals inspected, 28 equipments(machines) which were over 500 mA were randomly selected according to their characteristics : 7 condenser type x-ray equipments, 7 three control phase of full wave rectification of type remote control x-ray equipments, 7 single phase of full wave rectification type for general radiography equipments, and 7 single phase of full wave rectification type of R/F equipments. We obtained the following results by conducting the experiment based on the efficiency of the equipments mentioned above. 1) When te equipments are analyzed, 2 out of 7 single phase of full wave rectification type of general radiography equipments(28.6%), 3 out of 7 single phase of full wave rectification type of R/F equipments(42.9%), 5 out of 7 three phase of full wave rectification type remote of control x-ray equipments(71.4%), and 4 out of 7 condenser type of x-ray equipments(57.1%) showed suitability. It proves the superiority of the three phase of full wave rectification type of remote control x-ray equipments. 2) From the overall analysis, only about 50% of the equipments(suitability of 14 out of 28) maintain the efficient management. Therefore, maintenance management of equipments is more necessary. If the efficiency of the x-ray equipment is uniformly maintained and managed to prevent the breakdown(trouble) beforehand especially through the continuous inspection of tube voltage, tube current, exposure time, and collimator, the financial loss and exposure dose to the patient, as well as the workers engaged in radiation, can be reduced for better medical service

46 CFR 159.007-11 - Production inspections and tests: Yearly report.

Science.gov (United States)

2010-10-01

... 46 Shipping 6 2010-10-01 2010-10-01 false Production inspections and tests: Yearly report. 159.007-11 Section 159.007-11 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) EQUIPMENT, CONSTRUCTION, AND MATERIALS: SPECIFICATIONS AND APPROVAL APPROVAL OF EQUIPMENT AND MATERIALS Production...

9 CFR 318.305 - Equipment and procedures for heat processing systems.

Science.gov (United States)

2010-01-01

... processing systems. 318.305 Section 318.305 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE AGENCY ORGANIZATION AND TERMINOLOGY; MANDATORY MEAT AND POULTRY PRODUCTS INSPECTION... PREPARATION OF PRODUCTS Canning and Canned Products § 318.305 Equipment and procedures for heat processing...

Eddy current automatic inspection of heat exchangers in nuclear power stations

International Nuclear Information System (INIS)

Cazal, M.; Scopelliti, J.D.; Mendez, J.

1997-01-01

This presentation describes the eddy current tube inspection techniques for heavy heat exchangers in nuclear power stations. The purpose of these eddy current tests, is first to determine the integrity of the heat exchanger tubes, and to characterize the related types of defects in each case following to their analysis and cause determination and subsequent inspection planning. This task requires a group highly qualified personnel with high tech automate equipment. The organization of the group required a correct function and task assignment in order to achieve efficiency in scheduling, with simultaneous inspection to different components in a continuous base and uninterruptedly. A lead specialist is in charge of the group, which is set up by several shift supervisors, a qualified tele manipulator installation crew a number of qualified tele manipulator operators, and the specialist for data acquisition and certified eddy current signal evaluators plus some other support technicians and administrations helpers. In order to comply with inspection requirements, a bunch of technical procedures had to be developed. The following equipment is available nowadays: Zetec SM-13, SM-23 and SM-22 tele manipulators for inspection probes positioning, with different shapes and configuration (rotating probes, flexible probes for U-Bends, and magnetic saturation probes endowed with their own driving units) and remote data acquisition units identified as MIZ-18 A and MIZ-30, which are remotely operated from a mobile lab installed in a trailer, outside the reactor building. The available equipment allows a simultaneous inspection of three different plant components (two steam generators and a moderator heat exchanger). We are also in a position of performing eddy current tube inspection in more than a NSP at the same time. The Zetec Eddynet software is used in the manipulator operation and for the data acquisition and defect evaluation. This software operates within Windows

Terahertz Radome Inspection

Directory of Open Access Journals (Sweden)

Fabian Friederich

2018-01-01

Full Text Available Radomes protecting sensitive radar, navigational, and communications equipment of, e.g., aircraft, are strongly exposed to the environment and have to withstand harsh weather conditions and potential impacts. Besides their significance to the structural integrity of the radomes, it is often crucial to optimize the composite structures for best possible radio performance. Hence, there exists a significant interest in non-destructive testing techniques, which can be used for defect inspection of radomes in field use as well as for quality inspection during the manufacturing process. Contactless millimeter-wave and terahertz imaging techniques provide millimeter resolution and have the potential to address both application scenarios. We report on our development of a three-dimensional (3D terahertz imaging system for radome inspection during industrial manufacturing processes. The system was designed for operation within a machining center for radome manufacturing. It simultaneously gathers terahertz depth information in adjacent frequency ranges, from 70 to 110 GHz and from 110 to 170 GHz by combining two frequency modulated continuous-wave terahertz sensing units into a single measurement device. Results from spiraliform image acquisition of a radome test sample demonstrate the successful integration of the measurement system.

Inspection of fuel elements in the cooling pond of a research reactor

International Nuclear Information System (INIS)

Pavlov, S.V.; Mestnikov, A.V.

1992-01-01

Nondestructive testing methods for fuel bundles and fuel elements in the cooling ponds of atomic power plants, using special inspection stands, have come into widespread use during the past decade. This paper describes a methodological stand that was built for the laboratory development of methods and individual units of inspection stands for fuel bundles of RBMK and VVER-1000 reactors. A complex of equipment was developed for the study of irradiated fuel elements, thus creating a methodological base for developing techniques for nondestructive testing of irradiated fuel elements and equipment to obtain information about the state of the fuel elements in a reactor expeditiously. The time required to inspect a fuel element can be shortened using some techniques simultaneously. The length of a fuel element can be measured simultaneously with visual inspection, eddy-current flaw detection can be preformed at the same time as the tranverse size of the fuel element is being determined. 6 refs., 5 figs

Applicability of PSA Issues for Risk Assessment during Optimisation of In-Service Inspection

International Nuclear Information System (INIS)

Kolykhanov, V.; Skalozubov, V.; Kovrigkin, Y.

2006-01-01

The current codes determining periodicity of in-service inspection of the NPP equipment have been formed using deterministic approaches and have an unnecessary degree of conservatism. A perspective direction of perfection of normative base is decision making on a basis of risk-informed methodologies. It allows to increase safety of NPP equipment's operation and to optimise programs on inspection of the equipment subject to limited resources by focusing efforts on the most safety significant elements of the equipment. It is internationally accepted that methodology of the probabilistic safety analysis (PSA) is the most universal and comprehensive tool focused on the general assessment of safety of NPP as a whole. By now, PSA Level 1 is fulfilled for all pilot units of the Ukrainian NPPs that is a valuable result, which should be taken into account at an assessment of reliability of the equipment. However, specificity of PSA methodology should be taken into account at the decision of the particular tasks aimed at optimisation of maintenance of the equipment within individual systems. The estimation of the contribution to core damage frequency (CDF) is a PSA issue usually used to assess the significance of consequences of failure of a system/equipment during risk-informed decision-making. This work shows that above factor is only a part of assessment of the significance of consequences as core damage can be expressed in different amount of the damaged fuel elements and, hence, severity of consequences. Besides CDF is directly affected only by active elements which failure can be an initiating event. PSA methodology uses averaged reliability factors of the equipment for all possible operating modes occurring at transitive accident process. Here, there are limited opportunities to account impact of periodicity of maintenance of the equipment on reliability and to predict impact of change of the inspection program. PSA methodology does not allow taking into account

Scheduling and coordination for in-service inspection of nuclear power plant

International Nuclear Information System (INIS)

Li Songbai

1996-11-01

Based on the practice and experiences of pre-service and in-service inspections for Daya Bay Nuclear Power Plant (NPP) by Research Institute of Nuclear Power Operation (RINPO) following RSEM code, requirements of utility and actual situation in China, the in-service inspection preparation for organization, techniques and equipment/tooling, materials, personnel and documentation is briefly described. And the scheduling and coordinating consideration for planed in-service inspection activities during NPP outage is emphatically introduced. (2 refs., 4 figs.)

46 CFR 133.45 - Tests and inspections of lifesaving equipment and arrangements.

Science.gov (United States)

2010-10-01

... of flotation equipment such as lifebuoys, lifejackets, immersion suits, work vests, lifefloats... mechanisms; (3) The proper condition of flotation equipment such as lifebuoys, lifejackets, immersion suits, work vests, lifefloats, buoyant apparatus, and associated equipment; (4) That each inflatable liferaft...

On site PWR fuel inspection measurements for operational and design verification

International Nuclear Information System (INIS)

1996-01-01

The on-site inspection of irradiated Pressurized Water Reactor (PWR) fuel and Non-Fuel Bearing Components (NFBC) is typically limited to visual inspections during refuelings using underwater TV cameras and is intended primarily to confirm whether the components will continue in operation. These inspections do not normally provide data for design verification nor information to benefit future fuel designs. Japanese PWR utilities and Nuclear Fuel Industries Ltd. designed, built, and performed demonstration tests of on-site inspection equipment that confirms operational readiness of PWR fuel and NFBC and also gathers data for design verification of these components. 4 figs, 3 tabs

Licensee contractor and vendor inspection status report. Quarterly report, January-March 1986. Volume 10, No. 1

International Nuclear Information System (INIS)

1986-05-01

The NRC vendor inspection focus has been shifted to vendor activities associated with nuclear plant operation, maintenance, and modifications, more than firms designing nuclear steam supply systems, architect engineering firms designing nuclear plants, and major equipment vendors. Results of 16 inspections are reported, giving for each organization inspected, their activity, inspection bases and scope, and any violations, nonconformances, or unresolved items found. The status of previous inspection findings are also given

Remote controlled ultrasonic pre-service and in-service inspections of reactor pressure vessels

International Nuclear Information System (INIS)

Mueller, G.

1990-01-01

The first mechanised in-service inspection of the reactor pressure vessel on unit one of Eskom's Koeberg nuclear power station has been carried out. Since 1968 a whole range of manipulators to carry out remote controlled ultrasonic inspections of nuclear power station equipment has been developed. The inspection of a reactor pressure vessel using a central mast manipulator is described. 3 figs., 1 ill

Ultrasonic inspection of AA6013 laser welded joints

Directory of Open Access Journals (Sweden)

Adriano Passini

2011-09-01

Full Text Available Interest in laser beam welding for aerospace applications is continuously growing, mainly for aluminum alloys. The joints quality is usually assessed by non-destructive inspection (NDI. In this work, bead on plate laser welds on 1.6 mm thick AA6013 alloy sheets, using a 2 kW Yb-fiber laser were obtained and inspected by pulse/echo ultrasonic phased-array technique. Good and poor quality welds were inspected in order to verify the limits of inspection, comparing also to X-ray radiography and metallographic inspections. The results showed that ultrasonic phased array technique was able to identify the presence of grouped porosity, through the attenuation of the amplitude of the echo signal. This attenuation is attributed to the scattering of the waves caused by micro pores, with individual size below the resolution limit of the equipment, but when grouped, can cause a perceptive effect on the reflection spectra.

Full-scale testing of waste package inspection system

International Nuclear Information System (INIS)

Yagi, T.; Kuribayashi, H.; Moriya, Y.; Fujisawa, H.; Takebayashi, N.

1989-01-01

In land disposal of low-level radioactive waste (LLW) in Japan, it is legally required that the waste packages to be disposed of be inspected for conformance to applicable technical regulations prior to shipment from each existing power station. JGC has constructed a fully automatic waste package inspection system for the purpose of obtaining the required design data and proving the performance of the system. This system consists of three inspection units (for visual inspection, surface contamination/dose rate measurement and radioactivity/weight measurement), a labelling unit, a centralized control unit and a drum handling unit. The outstanding features of the system are as follows: The equipment and components are modularized and designed to be of the most compact size and the quality control functions are performed by an advanced centralized control system. The authors discuss how, as a result of the full-scale testing, it has been confirmed that this system satisfies all the performance requirements for the inspection of disposal packages

Development of Remote Inspection Systems with the Java Applet

International Nuclear Information System (INIS)

Choi, Yoo Rark; Lee, Jae Cheol; Kim, Jae Hee

2005-01-01

The world wide web and java are powerful networking technologies on the internet. An applet is a program written in the java programming language that can be included in an HTML page, much in the same way as an image is included. When we use a Java technology-enabled browser to view a page that contains an applet, the applet code is transferred to a client's system and executed by the browser's Java Virtual Machine (JVM). We have developed two remote inspection systems for a reactor wall inspection and guide tube spilt pin inspection based on the java and traditional programming language. The java is used on a GUI(graphic user interface) and the traditional visual C++ programming language is used to control the inspection equipments

46 CFR 185.726 - Annual inspections.

Science.gov (United States)

2010-10-01

... repairs made at least once each year, including emptying and cleaning of each fuel tank, and refilling it with fresh fuel. (b) Each davit, winch, fall and other launching appliance must be thoroughly inspected, and any necessary repairs made, at least once each year. (c) Each item of lifesaving equipment with an...

Restoration to serviceability of Bruce 'A' heat transfer equipment

International Nuclear Information System (INIS)

Gammage, D.; Machowski, C.; McGillivray, R.; Durance, D.; Kazimer, D.; Werner, K.

2009-01-01

Bruce Units 1 to 4 were shut down during the 1990s by the former Ontario Hydro, due in part to a long list of system and equipment deficiencies and concerns, including steam generator tube degradation as a consequence of the then-existing steam generator secondary side water chemistry conditions. Upon its creation in 2001, and following a program of condition assessment, Bruce Power was able to determine that Units 3 and 4 could return to service; but that Units 1 and 2 would require refurbishment. That Refurbishment Program, which is currently well advanced, included the re-assessment of the condition of equipment throughout the plant including the heat transfer equipment; and determination item-by-item as to what inspection, cleaning, repair, or even replacement would be required to put the equipment into a condition where it could be expected to operate reliably for the additional 30 years expected from the plant. Clearly the objective is to suitably restore the equipment to serviceability without doing more refurbishment work than is warranted - without replacing equipment except where absolutely necessary. The first task in such a program is determination of its scope - i.e. a listing of all heat exchangers. That list included everything from the steam generators (which required replacement, now completed), to much smaller heat exchangers in the heavy water upgrader systems (which were found to be in very good overall condition). There is also a very large number of other so-called 'balance-of-plant' heat exchangers; these include the maintenance coolers, moderator heat exchangers, shutdown coolers and a whole raft of smaller coolers - many of which are cooled directly by lake water with its potential for bio-fouling and 'BIC' (Biologically Induced Corrosion). This paper focuses primarily on the engineering assessment, inspection, repair and general refurbishment of the balance-of-plant heat exchangers. As will be discussed in the paper, the assessment of the

Nondestructive inspection of chemical warfare based on API-TOF

International Nuclear Information System (INIS)

Wang Xinhua; Zheng Pu; He Tie; An Li; Yang Jie; Fan Yu

2013-01-01

Background: Real-time, fast, accurate, nondestructive inspection (NDI) and quantitative analysis for chemical warfare are very imperative for chemical defense, anti-terror and nation security. Purpose: Associated Particles Technique (APT)/Neutron Time of Flight (TOF) has been developed for non-invasive inspection of sealed containers with chemical warfare agents. Methods: A prototype equipment for chemical warfare is consisted of an APT neutron generator with a 3×3 matrix of semiconductor detectors of associated alpha-particles, the shielding protection of neutron and gamma-ray, arrayed NaI(Tl)-based detectors of gamma-rays, fully-digital data acquisition electronics, data analysis, decision-making software, support platform and remote control system. Inelastic scattering gamma-ray pulse height spectra of sarin, VX, mustard gas and adamsite induced by 14-MeV neutron are measured. The energies of these gamma rays are used to identify the inelastic scattering elements, and the intensities of the peaks at these energies are used to reveal their concentrations. Results: The characteristic peaks of inelastic scattering gamma-ray pulse height spectra show that the prototype equipment can fast and accurately inspect chemical warfare. Conclusion: The equipment can be used to detect not only chemical warfare agents but also other hazardous materials, such as chemical/toxic/drug materials, if their chemical composition is in any way different from that of the surrounding materials. (authors)

Low energy microcolumn for large field view inspection

Energy Technology Data Exchange (ETDEWEB)

Kim, Young Chul [Department of Optometry, Eulji University, 212 Yangji-dong, Sujeong-gu, Seongnam-si, Gyeonggi-do 461-713 (Korea, Republic of); Ahn, Seung-Joon; Oh, Tae-Sik; Kim, Dae-Wook [Department of Nanoscience, Sun Moon University 100 Kalsan-ri, Tangjeong-myun, Asan-si, Chungnam 336-708 (Korea, Republic of); Kim, Ho-Seob, E-mail: hskim3@sunmoon.ac.kr [Department of Nanoscience, Sun Moon University 100 Kalsan-ri, Tangjeong-myun, Asan-si, Chungnam 336-708 (Korea, Republic of); Jang, Won Kweon [Division of Electronic, Computer and Communication Engineering, Hanseo University 360 DaeKook-ri, Haemi-myun, Seosan-si, Chungnam 356-706 (Korea, Republic of)

2011-12-15

Since the development of microcolumn system, it attracted much attention because multiple microcolumns can be assembled into arrayed form, which is expected to generate multiple electron beams and overcome the disadvantage of electron beam inspection equipments, low throughput . However, it is not easy to apply a microcolumn to the practical inspection or testing equipment since its scanning area is too small. Even if the arrayed operation using multiple microcolumns can overcome this limit, it requires complicated supporting systems and related technologies to operate a number of microcolumns simultaneously. Therefore, we tried to modify microcolumn design itself so that it can have a large field of view. In this work, two kinds of modified columns will be suggested and the preliminary results showing their performance of scanning large area will be discussed. -- Highlights: Black-Right-Pointing-Pointer Two types of microcolumn designs to achieve a large field of view are fabricated. Black-Right-Pointing-Pointer Field of view of a microcolumn increases linearly with the working distance. Black-Right-Pointing-Pointer New designed microcolumns can be developed as a low energy column system for large view inspections.

46 CFR 189.60-10 - Cargo Ship Safety Equipment Certificate.

Science.gov (United States)

2010-10-01

... 46 Shipping 7 2010-10-01 2010-10-01 false Cargo Ship Safety Equipment Certificate. 189.60-10... VESSELS INSPECTION AND CERTIFICATION Certificates Under International Convention for Safety of Life at Sea, 1974 § 189.60-10 Cargo Ship Safety Equipment Certificate. (a) All vessels on an international voyage...

46 CFR 159.007-3 - Production inspections and tests: Independent laboratory's procedures.

Science.gov (United States)

2010-10-01

...'s procedures. 159.007-3 Section 159.007-3 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) EQUIPMENT, CONSTRUCTION, AND MATERIALS: SPECIFICATIONS AND APPROVAL APPROVAL OF EQUIPMENT AND... meets the inspection and test procedures of the laboratory; and (3) Are accepted by the Commandant under...

Inspection of the Sizewll 'B' reactor coolant pump flywheels

International Nuclear Information System (INIS)

McNulty, A.L.; Cheshire, A.

1992-01-01

The Sizewell ''B'' safety case has categorised some primary circuit items as components for which failure is considered to be incredible. These Incredibility of Failure (IOF) components are particularly critical in their safety function, and specially stringent and all embracing provisions are made in their design, manufacture, inspection and operation. These provisions are such as to limit the probability of failure to levels which are so low that it does not have to be taken into account and no steps are necessary to control the consequences. The reactor coolant pump flywheel is considered to be an IOF component. Consequently there is a need for rigorous inspection during both manufacture and in service (ISI). The ISI requirement results in the need for an automated inspection. There is therefore a prerequisite to perform a Pre-Service Inspection (PSI) for baseline fingerprinting purposes. Furthermore there is a requirement that the inspection procedure, the inspection equipment and the operators are validated at the Inspection Validation Centre (IVC) of the AEA Technology laboratories at Risley. Development work is described. (author)

Automated x-ray inspection of composites at northrop aircraft

International Nuclear Information System (INIS)

Murphy, W.J. Jr.; Nutter, R.L.; Patricelli, F.

1985-01-01

The Northrop automated x-ray inspection system (AXIS) has evolved from a research and development program initiated in 1981 to reduce increasing inspection costs; and reduce inspection times to stay abreast with increasing F/A-18A production. The goal of the program was to develop an automated production system that would meet existing inspection requirements; automate handling and alignment; and replace film for the inspection of F/A-18A composite assemblies and laminates. Originally, the program was supported completely by Northrop internal finding. However in 1984 it became part of the Navy Industrial Modernization Incentive Program (IMIP) with joint funding. The program was selected by the Navy because of its great potential to reduce and stabilize costs associated with F/A-18A inspections. Currently the AXIS is in the last stage of development with final integration expected by the end of July 1985 and production implementation by the end of the year. This paper briefly describes the equipment, and operation of the AXIS. Slides will be presented at the conference which will further illustrate the system; including inspection results

Predictive maintenance and inspection through airborne ultrasound technology

Energy Technology Data Exchange (ETDEWEB)

Bandes, A [UE Systems, Inc., Elmsford, NY (United States)

1998-12-31

Airborne ultrasound can be considered an ideal integrating technology in that these instruments can stand alone to detect a variety of potential problems or they can be used to support vibration and infrared inspection programs. Usually portable, these instruments detect leaks in both pressurized gas systems or vacuum systems and related equipment such as tanks, pipes, heat exchangers, valves and steam traps. Additional applications include inspection of high voltage apparatus for corona, arcing and tracking. They are used to trend bearing failure as well as to detect conditions such as lack of lubrication and rubbing. A brief overview of the technology, its applications and suggested inspection techniques are explained. (orig.) 2 refs.

Predictive maintenance and inspection through airborne ultrasound technology

Energy Technology Data Exchange (ETDEWEB)

Bandes, A. [UE Systems, Inc., Elmsford, NY (United States)

1997-12-31

Airborne ultrasound can be considered an ideal integrating technology in that these instruments can stand alone to detect a variety of potential problems or they can be used to support vibration and infrared inspection programs. Usually portable, these instruments detect leaks in both pressurized gas systems or vacuum systems and related equipment such as tanks, pipes, heat exchangers, valves and steam traps. Additional applications include inspection of high voltage apparatus for corona, arcing and tracking. They are used to trend bearing failure as well as to detect conditions such as lack of lubrication and rubbing. A brief overview of the technology, its applications and suggested inspection techniques are explained. (orig.) 2 refs.

Making petroleum equipment safe, a priority

International Nuclear Information System (INIS)

1999-01-01

Changes to the 'Act respecting the use of petroleum products' have been announced effective May 1, 1999. The changes have been made to reduce problems which can be attributed to petroleum product leaks. The new regulations will make owners and users of petroleum equipment, including underground and above-ground storage equipment and commercial storage tanks, more accountable for the use of their own equipment. The emphasis in the new regulations is based upon the storage capacity of petroleum equipment and the risks associated with this equipment, rather than the on the activities of the owners concerned. Accordingly, the new regulations call for stricter requirements for high-risk equipment, a private equipment inspection plan, a two-year operating permit, replacing the current permits and certificates, a tariff structure based on the risks associated with the equipment, and deregulation of commercial activities involving petroleum products that require no equipment. Additionally, the amendments to the Act transfer responsibility for administration to the Regie du batiment and to the Ministere des Transports. Details of each of these changes are explained

Application of parallel processing for automatic inspection of printed circuits

International Nuclear Information System (INIS)

Lougheed, R.M.

1986-01-01

Automated visual inspection of printed electronic circuits is a challenging application for image processing systems. Detailed inspection requires high speed analysis of gray scale imagery along with high quality optics, lighting, and sensing equipment. A prototype system has been developed and demonstrated at the Environmental Research Institute of Michigan (ERIM) for inspection of multilayer thick-film circuits. The central problem of real-time image processing is solved by a special-purpose parallel processor which includes a new high-speed Cytocomputer. In this chapter the inspection process and the algorithms used are summarized, along with the functional requirements of the machine vision system. Next, the parallel processor is described in detail and then performance on this application is given

46 CFR 91.60-10 - Cargo Ship Safety Equipment Certificate.

Science.gov (United States)

2010-10-01

... 46 Shipping 4 2010-10-01 2010-10-01 false Cargo Ship Safety Equipment Certificate. 91.60-10... VESSELS INSPECTION AND CERTIFICATION Certificates Under International Convention for Safety of Life at Sea, 1974 § 91.60-10 Cargo Ship Safety Equipment Certificate. (a) All vessels on an international voyage are...

The API methodology for risk-based inspection (RBI) analysis for the petroleum and petrochemical industry

International Nuclear Information System (INIS)

Reynolds, J.T.

1998-01-01

Twenty-one petroleum and petrochemical companies are currently sponsoring a project within the American Petroleum Institute (API) to develop risk-based inspection (RBI) methodology for application in the refining and petrochemical industry. This paper describes that particular RBI methodology and provides a summary of the three levels of RBI analysis developed by the project. Also included is a review of the first pilot project to validate the methodology by applying RBI to several existing refining units. The failure for pressure equipment in a process unit can have several undesirable effects. For the purpose of RBI analysis, the API RBI program categorizes these effects into four basic risk outcomes: flammable events, toxic releases, major environmental damage, and business interruption losses. API RBI is a strategic process, both qualitative and quantitative, for understanding and reducing these risks associated with operating pressure equipment. This paper will show how API RBI assesses the potential consequences of a failure of the pressure boundary, as well as assessing the likelihood (probability) of failure. Risk-based inspection also prioritizes risk levels in a systematic manner so that the owner-user can then plan an inspection program that focuses more resources on the higher risk equipment; while possibly saving inspection resources that are not doing an effective job of reducing risk. At the same time, if consequence of failure is a significant driving force for high risk equipment items, plant management also has the option of applying consequence mitigation steps to minimize the impact of a hazardous release, should one occur. The target audience for this paper is engineers, inspectors, and managers who want to understand what API Risk-Based Inspection is all about, what are the benefits and limitations of RBI, and how inspection practices can be changed to reduce risks and/or save costs without impacting safety risk. (Author)

Inspection and repair in JRR-3 after the 2011 off the Pacific coast of Tohoku Earthquake

International Nuclear Information System (INIS)

Hosoya, Toshiaki; Nagadomi, Hideki; Torii, Yoshiya

2014-01-01

In the 2011 off the Pacific Coast of Tohoku Earthquake, seismic intensity of 6 lower was observed at Tokai Village. However, the maximum acceleration of ground motion that was observed in the JRR-3 reactor facilities had exceeded the maximum response acceleration at the time of design. Therefore, to confirm whether the predetermined performance of the facility equipment of the reactor facilities had been maintained after the earthquake, soundness confirmation inspection was carried out. In the inspection, the soundness of equipment and facilities was evaluated from the results of the equipment inspection and seismic impact assessment, and the repair work was applied when necessary. As a result, it was confirmed that after the earthquake, the equipment of JRR-3 reactor facilities maintained the predetermined performance, and was possible to resume operation. The following item are reported here: (1) overview of JRR-3, (2) conditions of JRR-3 reactor facilities while earthquake occurrence, (3) basic principle for soundness evaluation of facilities, (4) soundness confirmation of buildings and structures, (5) contents of repair, and (6) soundness verification and comprehensive evaluation of each facility and equipment. (A.O.)

Development of Remote Inspection Systems with the Java Applet

Energy Technology Data Exchange (ETDEWEB)

Choi, Yoo Rark; Lee, Jae Cheol; Kim, Jae Hee [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2005-07-01

The world wide web and java are powerful networking technologies on the internet. An applet is a program written in the java programming language that can be included in an HTML page, much in the same way as an image is included. When we use a Java technology-enabled browser to view a page that contains an applet, the applet code is transferred to a client's system and executed by the browser's Java Virtual Machine (JVM). We have developed two remote inspection systems for a reactor wall inspection and guide tube spilt pin inspection based on the java and traditional programming language. The java is used on a GUI(graphic user interface) and the traditional visual C++ programming language is used to control the inspection equipments.

Remote-Controlled Inspection Robot for Nuclear Facilities in Underwater Environment

International Nuclear Information System (INIS)

Yasuhiro Miwa; Syuichi Satoh; Naoya Hirose

2002-01-01

A remote-controlled inspection robot for nuclear facilities was developed. This is a underwater robot technology combined with inspection and flaw removal technologies. This report will describe the structure and performance of this robot. The inspection robot consists of two parts. The one is driving equipment, and the other is inspection and grinding units. It can swim in the tank, move around the tank wall, and stay on the inspection area. After that it starts inspection and flaw removal with a special grinding wheel. This technology had been developed to inspect some Radioactive Waste (RW) tanks in operating nuclear power plants. There are many RW tanks in these plants, which human workers can be hard to access because of a high level dose. This technology is too useful for inspection works of human-inaccessible areas. And also, in conventional inspection process, some worker go into the tank and set up scaffolding after full drainage and decontamination. It spends too much time for these preparations. If tank inspection and flaw removal can be performed in underwater, the outage period will be reduced. Remote-controlled process can be performed in underwater. This is the great advantage for plant owners. Since 1999 we have been applying this inspection robot to operating nuclear 11 facilities in Japan. (authors)

Discussion of in-service inspection planning for nuclear power plants

International Nuclear Information System (INIS)

Aoki, Takayuki; Takagi, Toshiyuki

2012-01-01

For creating an inspection plan for industrial plants like nuclear power plants, it is necessary to have a well-grounded basis. Therefore, this paper proposes a method for determining the following three elements of such a plan: the equipment to be inspected, the inspection method to be adopted, and the timing of its implementation using a scientific approach. The key idea is to analyze the components of the plan by employing the understanding of cancer detection and diagnosis in medical science and also to take an approach of creating a plan based on the characteristic features of the component and its aging degradation mode, the performance of the inspection method, and the relationship between the two. Taking all the above into account, the factors to be considered and the best way for inspecting the plants are presented in this paper. (author)

Equipment and special tool design for remote maintenance

International Nuclear Information System (INIS)

Northey, L.M.; Thomson, J.D.

1985-01-01

Maintenance tasks performed in locations with hostile environments and/or limited space accesses often require equipment that is operated remotely. This paper discusses considerations that should be addressed in the design of remote maintenance equipment. Some of the topics include proper material selection, interface identifications, operational feedback devices and cost limitations. These considerations add ''human engineering'' to the equipment design to assure protection of the tool and the operating personnel. Examples of remote maintenance and inspection systems that were developed by the Westinghouse Hanford Company and that utilize many of these design considerations are included

30 CFR 77.1901 - Preshift and onshift inspections; reports.

Science.gov (United States)

2010-07-01

... before and after blasting. (b) The surface area surrounding each slope and shaft shall be inspected by a... condition has been abated. (d) No work shall be performed in any slope or shaft, no drilling equipment shall...

Continuous improvement in manufacturing and inspection of fuel

International Nuclear Information System (INIS)

Domingon, A.; Ruiz, R.

2015-01-01

The manufacturing and inspection process of fuel assemblies in ENUSA is characterized by its robustness acquired over the last thirty years of experience in manufacturing. The reliability of these processes is based on a qualified processes and continuous improvement in the design and upgrading of equipment and optimization of software and manufacturing processes. Additionally, management and quality control systems have been improved in both software and measuring business objectives. this article emphasizes the improvements made over the past five years in management, production and inspection of fuel assemblies. (Author)

An on-line monitoring system for navigation equipment

Science.gov (United States)

Wang, Bo; Yang, Ping; Liu, Jing; Yang, Zhengbo; Liang, Fei

2017-10-01

Civil air navigation equipment is the most important infrastructure of Civil Aviation, which is closely related to flight safety. In addition to regular flight inspection, navigation equipment's patrol measuring, maintenance measuring, running measuring under special weather conditions are the important means of ensuring aviation flight safety. According to the safety maintenance requirements of Civil Aviation Air Traffic Control navigation equipment, this paper developed one on-line monitoring system with independent intellectual property rights for navigation equipment, the system breakthroughs the key technologies of measuring navigation equipment on-line including Instrument Landing System (ILS) and VHF Omni-directional Range (VOR), which also meets the requirements of navigation equipment ground measurement set by the ICAO DOC 8071, it provides technical means of the ground on-line measurement for navigation equipment, improves the safety of navigation equipment operation, and reduces the impact of measuring navigation equipment on airport operation.

Final results of double-shell tank 241-AZ-101 ultrasonic inspection

International Nuclear Information System (INIS)

JENSEN, C.E.

1999-01-01

This document presents the results and documentation of the nondestructive ultrasonic examination of tank 241-AZ-101. A tank inspection supplier was retained to provide and use an ultrasonic examination system (equipment, procedures, and inspectors) to scan a limited area of double-shell tank 241-AZ-101 primary tank wall and welds. The inspection found one reportable indication of thinning and no reportable pitting, corrosion, or cracking

Safety inspection guide, Mod III (a systematic approach to conducting a safety inspection)

International Nuclear Information System (INIS)

Davidson, J.E.

1977-06-01

This guide was developed as a comprehensive/systematic approach to the problem of performing a safety inspection. Five basic sections (categories) are considered in the guide: physical work place; machines/mechanical equipment; hazardous materials/processes/environments; energy sources; and management hazard . control factors. The basic concept is that one starts evaluating hazard potentials from the physical work place and continues considering other elements as they are added to the physical work place. This approach provides a better understanding of the interfaces of each section to the entire group. The guide is supported by an Area Safety Inspection Result form to record defects or conditions found, the evaluation (best estimate) of the urgency or priority for correcting deficiencies or areas of noncompliance, and the status of corrective action. Additionally, the guide serves as an educational tool in accident prevention for supervisors and employees

Classification and handling of non-conformance item of nuclear class equipment during manufacture phase

International Nuclear Information System (INIS)

Wang Ruiping

2001-01-01

Based on inspection experiences in years on nuclear class equipment manufacturing, the author discusses the classification and handling of non-conformance items occurred during equipment manufacturing, and certain technical considerations are presented

Assessment of pressurized nuclear equipment compliance - ASN guide no. 8, version of 04/09/2012

International Nuclear Information System (INIS)

2012-01-01

This document describes the modalities according to which the compliance assessment of pressurized nuclear equipment must be performed by inspecting organisations according to a decree of December 1999 and an order of December 2005. After an indication of reference documents and some technical definitions, this guide describes the equipment classification and the principles of intervention. These principles concern the assessment request and the various assessment tasks to be performed by the inspecting organisation

Decommissioning of Division of Military Application equipment at Hanford. Summary report

International Nuclear Information System (INIS)

Raile, M.N.

1977-06-01

This report describes the successful decommissioning of plutonium-contaminated equipment used for weapon component fabrication and inspection at the Hanford Plant. Special materials, techniques, and equipment were employed during the course of the decommissioning program. Most significant was the development and design of large, double-wall fiberglassed plywood boxes for long-term (20-years, minimum) retrievable storage of the contaminated equipment in underground transuranic waste trenches

Eddy current inspection on heat exchanger tubes - problems and limitations

International Nuclear Information System (INIS)

Ilham Mukriz; Zainal Abidin Mohamed; Hairul Hasmoni Khairul Anuar; Mohd Salleh; Mahmood Dollah

2005-01-01

This paper focus on problems associated to eddy current inspection of heat exchanger tubes. A brief review on heat exchanger design and operation is presented. Eddy current technique in identifying inhomogeneity in tested tubes is discussed, highlighting its limitation in distinguishing between real pit type defects and other mundane anomalies. The limitation of the eddy current probe and equipment pertinent to the inspection are identified and areas of improvement are discussed. (Author)

Development of automated equipment for reduction of personnel radiation exposure in nuclear power plants

International Nuclear Information System (INIS)

Ogushi, Akira; Fujii, Masaaki; Mizuno, Katsuhiro.

1976-01-01

Described are a mobile remote inspection system and an automatic analyzer for radioactive nuclides in reactor coolant now being developed as a means of reducing personnel radiation exposure in nuclear power plants. In the mobile remote inspection system ''TELEPAT'', a self-propelled vehicle equipped with a thermometer, accelerometer, microphone, ionization chamber, etc. is remote operated from the main control room to inspect the equipment in the reactor building. The automatic analyzer for radioactive nuclides in reactor coolant automates the series of operations ranging from sampling of reactor coolant to measurement of radioactivity and analyses of measured data, with a view to saving labor in radioactivity analysis work while reducing exposure of personnel to radiation. (auth.)

Inspection of Emergency Arrangements

International Nuclear Information System (INIS)

2013-01-01

NPPs. - Where RBs have an influence over land use around NPPs, they use the knowledge of their local or resident inspectors to inform decisions. - Inspectors check that appropriate action levels or criteria to identify an actual or radiological emergency are clearly defined and readily available to decision makers. - When observing emergency exercises inspectors check that: an appropriate and timely declaration is made, plant operators respond in accordance with the emergency plan and emergency instructions, and an appropriate level of response is initiated on and off-site. - RBs conduct follow-up inspections after real events, to ensure that the correct emergency response has been followed. - Inspectors verify that reliable data will be used to support the evaluation of environmental impact from a nuclear or radiological emergency, to the extent that this is within the jurisdiction of the RB. - Routine inspections and emergency exercise observations include a check that lines of communication are sufficiently resilient. - When observing emergency exercises inspectors, where practicable, check that timely, accurate and consistent information is provided to the public, in accordance with the off-site emergency plan. - RBs inspect the ability of the operator to give accurate medical and radiological information about casualties, to enable the correct treatment to be given. - Additional emergency equipment that is held in reserve off-site, provided to enhance resilience (post Fukushima), is included in the RB planned inspection and/or emergency exercise programme. - Inspectors check that licensee staff are adequately trained to connect and use additional equipment provided to enhance resilience. - Inspectors utilise the NPP operator's approved on-site emergency plan when inspecting on-site emergency arrangements. - RBs include human factors staff in emergency exercise evaluation teams to consider safety culture and human performance. - RBs consider the need for exercise

INETEC new system for inspection of PWR reactor pressure vessel head

International Nuclear Information System (INIS)

Nadinic, B.; Postruzin, Z.

2004-01-01

INETEC Institute for Nuclear Technology developed new equipment for inspection of PWR and VVER reactor pressure vessel head. The new advances in inspection technology are presented in this article, as the following: New advance manipulator for inspection of RPVH with high speed of inspection possibilities and total automated work; New sophisticated software for manipulator driving which includes 3D virtual presentation of manipulator movement and collision detection possibilities; New multi axis controller MAC-8; New end effector system for inspection of penetration tube and G weld; New eddy current and ultrasonic probes for inspection of G weld and penetration tube; New Eddy One Raster scan software for analysis of eddy current data with mant advanced features which allows easy and quick data analysis. Also the results of laboratory testing and laboratory qualification are presented on reactor pressure vessel head mock, as well as obtained speed of inspection and quality of collected data.(author)

Improvement and optimization for in-service inspection of M310 nuclear power station

International Nuclear Information System (INIS)

Wang Chen; Sun Haitao; Gao Chen; Deng Dong

2015-01-01

In-service inspection (ISI) is an important method to ensure the safety of the mechanical equipment in nuclear power stations. According to the in-service inspection experience feedback from the domestic nuclear power stations, the reasonableness of some provisions in the RSE-M code are discussed and the applications of risk-informed in-service inspection (RI-ISI) are introduced, and the advices for the optimization of the ISI of the domestic M310 nuclear power stations are proposed. (authors)

An overview of in-service inspection for nuclear power plants in Japan

International Nuclear Information System (INIS)

Takano, Eishiro

1996-01-01

In nuclear power stations, for maintaining the safety of machinery and equipment, it is stipulated to carry out periodic inspection. The contents of the periodic inspection and the inspections of important matters are explained. In-service inspection (ISI) is the nondestructive inspection for confirming the soundness of reactor pressure vessels, main pipings, valves and others. The stipulations on the scope and time of the periodic inspection and ISI, the course of introducing ISI into Japan, and the basic way of thinking on ISI are described. Pre-service inspection (PSI) is carried out for the purpose of collecting and recording the initial data for ISI. The range of the objects of nondestructive inspection and leak test and the range of the objects of leak test only are shown. As to nondestructive inspection, the parts to be inspected, the frequency of inspection and the methods of inspection, and the method of leak test are described. As the present state of inspection technology, the automatic ultrasonic flow detectors for reactor vessels, piping welded parts and reactor vessel stud bolts, and the eddy current flaw detector for steam generator tubes are explained. (K.I.)

46 CFR 107.231 - Inspection for certification.

Science.gov (United States)

2010-10-01

... effectively carry out abandonment and fire fighting procedures. Fire Fighting Equipment (h) Each hand portable... accordance with § 107.235(a). (i) Each fixed fire-extinguishing system is inspected, and serviced if required, in accordance with § 107.235(b). (j) Each fire main system meets the testing requirements in § 107...

16 CFR 1605.2 - Conduct and scope of inspections.

Science.gov (United States)

2010-01-01

... Section 1605.2 Commercial Practices CONSUMER PRODUCT SAFETY COMMISSION FLAMMABLE FABRICS ACT REGULATIONS INVESTIGATIONS, INSPECTIONS AND INQUIRIES PURSUANT TO THE FLAMMABLE FABRICS ACT Procedures for Investigations... any product, fabric, or related material and all pertinent equipment, materials, substances, products...

Present state of inspection robot technology in nuclear power facilities. Case of fast breeder reactors

International Nuclear Information System (INIS)

Ara, Kuniaki

1995-01-01

In the maintenance works in nuclear power facilities such as checkup, inspection and repair, for the main purpose of radiation protection, remote operation technology was introduced since relatively early stage, and at present, the robots that carry out the inspection works for confirming the soundness of main equipment have been developed and put to practical use. At the time of introducing these technologies, in addition to the research and development of robots proper, the coordination with the design of plant machinery and equipment facilities as the premise of introducing robots is an important requirement. In this report, the present state of the development of remote inspection technology for fast breeder reactors is introduced, and the matters to which attention is paid in the plant design for introducing robots are explained. First, fast breeder reactors are described. The needs of robotizing and adopting remote operation in nuclear power facilities are explained, using the examples of the inspection system for a reactor vessel and the inspection system for steam generator heat transfer tubes. (K.I.)

The Mechatronic System Design Of Ultrasonic Scanner For Inservice Inspection Of Research Reactor

Science.gov (United States)

Handono, Khairul; Kristedjo, K.; Awwaluddin, M.; Shobary, Ihsan

2018-02-01

The mechatronic system design of ultrasonic scanner for inservices inspection of Research Reactor has been conducted. The requirement designed must be reliable operated, safety to personnel and equipments, ease of maintenance and operation, protection of equipment mechanically, interchangeability of equipments and addition of the several model of probe immersion ultrasonic tranducer. In order to achieve the above goals and obtain the desired results, a mechatronic design based on mechanical and electronic practical experiences will be needed. In this paper consist of the mechanical design and the system mechanical movement using stepper motor control. The criteria and the methods of designs of mechanical and electronic equipments of the system have been discussed and investigated. A mechanical and instrumentation control system drawing and requirement of design will be presented as the outcome of the design. The designed of mechanical system is consequently simulated by solidwork software. The intention of the above research is to create solutions in different ways of inservice inspection of integrity of Reactor.

Pipelines inspection robots; Robos para inspecao de linhas de servico

Energy Technology Data Exchange (ETDEWEB)

Archila Diaz, John Faber; Dutra, Max Suell [Universidade Federal do Rio de Janeiro (UFRJ), RJ (Brazil). Coordenacao dos Programas de Pos-graduacao de Engenharia (COPPE). Lab. de Robotica

2008-07-01

One of the problems existing in the area of maintenance of systems for the transport of mass and / or energy is to examine the integrity of the lines of service in the basic infrastructure of cities and industries. For the development of maintenance, whether predictive, preventive or corrective is necessary to conduct the inspection of these lines. To carry out this task is necessary count on help of appropriate technological tools. The main tools for inspection of service lines come from the area of external inspection of pipelines and are also in development, the problem happens when we need to achieve internal or external failures in places of difficult access, and move the inspection equipment to places where it's going to fail. In these cases it is necessary to the use of mechatronic systems, more specifically robotic systems, which may be developed for inspection. This paper aims to present the main robotic systems used for inspection, especially for internal inspection of pipelines. These systems have been developed by the research groups in Brazil, Japan, and Belgium among others, giving up a classification of robots for inspection of pipelines and the main features necessary for its project. (author)

Pipelines inspection robots; Robos para inspecao de linhas de servico

Energy Technology Data Exchange (ETDEWEB)

Archila Diaz, John Faber; Dutra, Max Suell [Universidade Federal do Rio de Janeiro (UFRJ), RJ (Brazil). Coordenacao dos Programas de Pos-graduacao de Engenharia (COPPE). Lab. de Robotica

2008-07-01

One of the problems existing in the area of maintenance of systems for the transport of mass and / or energy is to examine the integrity of the lines of service in the basic infrastructure of cities and industries. For the development of maintenance, whether predictive, preventive or corrective is necessary to conduct the inspection of these lines. To carry out this task is necessary count on help of appropriate technological tools. The main tools for inspection of service lines come from the area of external inspection of pipelines and are also in development, the problem happens when we need to achieve internal or external failures in places of difficult access, and move the inspection equipment to places where it's going to fail. In these cases it is necessary to the use of mechatronic systems, more specifically robotic systems, which may be developed for inspection. This paper aims to present the main robotic systems used for inspection, especially for internal inspection of pipelines. These systems have been developed by the research groups in Brazil, Japan, and Belgium among others, giving up a classification of robots for inspection of pipelines and the main features necessary for its project. (author)

Final results of double-shell tank 241-AY-102 ultrasonic inspection

International Nuclear Information System (INIS)

JENSEN, C.E.

1999-01-01

This document presents the results and documentation of the nondestructive ultrasonic examination of tank 241-AY-102. A tank inspection supplier was retained to provide and use an ultrasonic examination system (equipment, procedures, and inspectors) to scan a limited area of double-shell tank 241-AY-102 primary tank wall and welds. The inspection found some indication of insignificant general and local wall thinning with no cracks detected

Final results of double-shell tank 241-AN-105 ultrasonic inspection

International Nuclear Information System (INIS)

JENSEN, C.E.

1999-01-01

This document presents the results and documentation of the nondestructive ultrasonic examination of tank 241-AN-105. A tank inspection supplier was retained to provide and use an ultrasonic examination system (equipment, procedures, and inspectors) to scan a limited area of double-shell tank 241-AN-105 primary tank wall primary knuckle, and secondary tank bottom. The inspection found some indication of general and local wall thinning with no cracks detected

Equipment for detach the fuel elements of the irradiated candu fuel bundle

International Nuclear Information System (INIS)

Cojocaru, V.; Dinuta, G.

2013-01-01

Monitoring the behaviour of the fuel bundles during their combustion provides useful information for the operation of the nuclear power plant as well as for the fuel manufacturer. Before placing it inside the reactor, the fuel bundle is inspected visually, dimensionally and, during combustion in the reactor, its radioactive behaviour is monitored. The purpose of the presented equipment is to allow the visual external inspection of the damaged fuel bundle in order to identify visible defects and to detach the fuel element by breaking the welded connection between the cap and grid. These devices are operated using the handler devices already existing in the hot cells Post-Irradiation Examination Laboratory (LEPI). This equipment has been used successfully in the LEPI laboratory at SCN Pitesti to inspect the damaged fuel from Cernavoda NPP, in March 2013. (authors)

MACS as a tool for international inspections

International Nuclear Information System (INIS)

Curtiss, J.A.; Indusi, J.P.

1995-01-01

General acceptance of the challenge provision in the Chemical Weapons Convention has the potential for influence in other arms control areas. While most applications of the challenge inspection may be straightforward, there may be instances where access to the site by inspectors may be problematic. The MACS system described in this paper was developed to respond to these situations. Inspection and verification may be difficult when a host is unwilling,for valid reasons, to permit physical access to a site. We proposed a system of remote sensors which may be used to demonstrate compliance with Chemical Weapons Convention (CWC) challenge inspections even ff the inspector is physically excluded from a sensitive site. The system is based upon alternative-means-of-access provisions of the CWC. The Defense Nuclear Agency (DNA) funded design and construction of a system prototype, designated as MACS for Managed Access by Controlled Sensing. Features of the MACS design allow growth of the prototype into a versatile device for international monitoring of production facilities and other sites. MACS consists of instrumentation and communication equipment allowing site personnel to conduct a facility tour and perform acceptable measurements, while physically excluding the inspector from the facility. MACS consists of a base station used by the inspector, and a mobile unit used within the facility and manipulated by the facility staff. The base station and the mobile unit are at sign ed by a communication system, currently realized as a fiber optic cable. The mobile unit is equipped with television cameras and remote-reading distance-measuring equipment (DME) for use in verifying locations and dimensions. Global Positioning System receivers on the mobile unit provide both precise location and dead reckoning, suitable for tracking the mobile unit's position while within a building when satellite signals are not available

Performance monitoring of safeguards equipment

International Nuclear Information System (INIS)

Sirisena, K.; Peltoranta, M.; Goussarov, V.; Vodrazka, P.

1999-01-01

SGTCS is responsible for monitoring and reporting the performance of the SG equipment. Performance monitoring (PM) has been implemented in most important safeguards equipment operating unattended in nuclear facilities. Inspectors acquire equipment performance data in facilities. After inspection, the data package is submitted to SGTCS for processing and analysis. The performance data is used for identification of systems or components, which should be changed in the field and for identification of modules which, should be diagnosed at HQ in order to determine the cause of failure. Moreover, the performance data is used for preventive maintenance and spares distribution planning, and to provide statistics for official reports and management decision making. An important part of the performance monitoring is reporting. Equipment performance reports contain information about equipment inventory, utilization, failure types, failure distribution, and reliability. Trends in performance are given in graphical form in cases, where past data is available. Reliability estimates such as expected times between failures are provided. The automated reporting tools are obtainable through EMIS database application. (author)

Supervision and inspection plans of plants activities

International Nuclear Information System (INIS)

Feijoo, J. P.

2009-01-01

Any idea of hierarchization between supervisor and supervised in inspection and supervision activities should necessarily be dismissed, and the independence of the supervisor when executing has tasks should be guaranteed. The inspection and supervision program enable the detection and resolution of materials and human problems alike. In addition, they are a solution to anticipate potential problems in the future, which results in a very significant reduction of industrial accidents and human errors, as well as better use and upkeep of equipment. With these programs we improve our management and our work, and without a doubt they help to strengthen the safety culture in Cofrentes Nuclear Power Plant. (Author)

Risk-based inspection in the context of nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Soares, Wellington A.; Vasconcelos, Vanderley de; Rabello, Emerson G., E-mail: soaresw@cdtn.br, E-mail: vasconv@cdtn.br, E-mail: egr@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

2015-07-01

Nuclear power plant owners have to consider several aspects like safety, availability, costs and radiation exposure during operation of nuclear power plants. They also need to demonstrate to regulatory bodies that risk assessment and inspection planning processes are being implemented in effective and appropriate manner. Risk-Based Inspection (RBI) is a methodology that, unlike time-based inspection, involves a quantitative assessment of both failure probability and consequence associated with each safety-related item. A correctly implemented RBI program classifies individual equipment by its risks and prioritizes inspection efforts based on this classification. While in traditional deterministic approach, the inspection frequencies are constant, in the RBI approach the inspection interval for each item depends on the risk level. Regularly, inspection intervals from RBI result in risk levels lower or equal than deterministic inspection intervals. According to the literature, RBI solutions improve integrity and reduce costs through a more effective inspection. Risk-Informed In-service Inspection (RI-ISI) is the equivalent term used in the nuclear area. Its use in nuclear power plants around world is briefly reviewed in this paper. Identification of practice methodologies for performing risk-based analyses presented in this paper can help both Brazilian nuclear power plant operator and regulatory body in evaluating the RI-ISI technique feasibility as a tool for optimizing inspections within nuclear plants. (author)

Risk-based inspection in the context of nuclear power plants

International Nuclear Information System (INIS)

Soares, Wellington A.; Vasconcelos, Vanderley de; Rabello, Emerson G.

2015-01-01

Nuclear power plant owners have to consider several aspects like safety, availability, costs and radiation exposure during operation of nuclear power plants. They also need to demonstrate to regulatory bodies that risk assessment and inspection planning processes are being implemented in effective and appropriate manner. Risk-Based Inspection (RBI) is a methodology that, unlike time-based inspection, involves a quantitative assessment of both failure probability and consequence associated with each safety-related item. A correctly implemented RBI program classifies individual equipment by its risks and prioritizes inspection efforts based on this classification. While in traditional deterministic approach, the inspection frequencies are constant, in the RBI approach the inspection interval for each item depends on the risk level. Regularly, inspection intervals from RBI result in risk levels lower or equal than deterministic inspection intervals. According to the literature, RBI solutions improve integrity and reduce costs through a more effective inspection. Risk-Informed In-service Inspection (RI-ISI) is the equivalent term used in the nuclear area. Its use in nuclear power plants around world is briefly reviewed in this paper. Identification of practice methodologies for performing risk-based analyses presented in this paper can help both Brazilian nuclear power plant operator and regulatory body in evaluating the RI-ISI technique feasibility as a tool for optimizing inspections within nuclear plants. (author)

Technical video documentation UN Security Council Resolution 687. 7. IAEA inspection in Iraq October 1991, IAEA inspection no. 8 Iraq November 1991

International Nuclear Information System (INIS)

1991-01-01

This video documents the 7th and 8th IAEA inspections to Iraq (A1 Tuwaitha, A1 Atheer, A1 Qa Qaa sites and A1 Hatteen High Explosive Test Site) and the destruction and removal of various equipment suitable for nuclear weapon development

Operational aspects of the Calder Hall and Chapelcross pressure vessel ultrasonic inspections

International Nuclear Information System (INIS)

Bithell, S.J.; Howard, S.R.

1993-01-01

As a consequence of the NII's assessment of the Calder Hall and Chapelcross Long Term Safety Review, BNFplc were required to demonstrate the integrity of the Reactor Pressure Vessels through a programme of volumetric seam weld inspection. Existing equipment proved to be inadequate and necessitated the design and manufacture of a remote power manipulator and ultrasonic scanning package. Calder Hall Operations Department and Sellafield Technical Department, working closely with contract staff, completed the first stage of this technically demanding task within 14 months of the project's initiation, resulting in the first deployment of ''REDIMAN'' in March 1991. The design of the new equipment, and the technical and operational difficulties which were overcome by the Inspection Team are outlined. (author)

Limits of applicability in NDT inspections. Practical examples

International Nuclear Information System (INIS)

Sodeikat, Christian; Lohse, Carsten

2016-01-01

Property owners, developers, architects, planners and in many cases courts require further information regarding the state of existing and under construction buildings. In order to avoid concerns on the building structure and to avoid nuisance by noise and dirt and ultimately save costs, structural inspection should be carried out as non-destructive. NDT methods, however, always have application limits that can be very different depending on the methods used and test equipment. However, not every inspection task, the implementation of which customer want, can be solved with NDT methods. The following article presents practical examples of application limits of different NDT methods. [de

MACS as a tool for international inspections

Energy Technology Data Exchange (ETDEWEB)

Curtiss, J.A.; Indusi, J.P.

1995-08-01

The MACS/ACRS (Managed Access by Controlled Sensing/Access by Controlled Remote Sensing) system is a collection of communication devices, video capability, and distance-measuring equipment which can effectively substitute for the physical presence of a challenge inspector within a facility. The MACS design allows growth of the prototype, developed in response to the Chemical Weapons Convention (CWC), into a versatile device for inspection of sensitive nuclear facilities under other international arrangements, for example the proposed Fissile Material Cutoff Convention. A MACS/ACRS-type system in a standard, international-recognized configuration could resolve sensitive information and safety concerns through providing a means of achieving the goals of an inspection while excluding the inspector. We believe the technology used to develop MACS for the Defense Nuclear Agency, followed by ACRS for the Department of Energy, is universally adaptable for minimally-intrusive managed-access international inspections of sensitive sites.

MACS as a tool for international inspections

International Nuclear Information System (INIS)

Curtiss, J.A.; Indusi, J.P.

1995-01-01

The MACS/ACRS (Managed Access by Controlled Sensing/Access by Controlled Remote Sensing) system is a collection of communication devices, video capability, and distance-measuring equipment which can effectively substitute for the physical presence of a challenge inspector within a facility. The MACS design allows growth of the prototype, developed in response to the Chemical Weapons Convention (CWC), into a versatile device for inspection of sensitive nuclear facilities under other international arrangements, for example the proposed Fissile Material Cutoff Convention. A MACS/ACRS-type system in a standard, international-recognized configuration could resolve sensitive information and safety concerns through providing a means of achieving the goals of an inspection while excluding the inspector. We believe the technology used to develop MACS for the Defense Nuclear Agency, followed by ACRS for the Department of Energy, is universally adaptable for minimally-intrusive managed-access international inspections of sensitive sites

RSE-M: In-Service Inspection Rules for Mechanical Components of PWR Nuclear Islands

International Nuclear Information System (INIS)

2016-01-01

The RSE-M code defines in-service inspection operations. It applies to pressure equipment used in PWR plants, as well as spare parts for such equipment. The RSE-M code does not apply to equipment made from materials other than metal. It is based on the RCC-M code for requirements relating to the design and fabrication of mechanical components. Use: The inspection rules specified in the RSE-M code describe the standard requirements of best practice within the French nuclear industry, based on its own feedback from operating several nuclear units and partly supplemented with requirements stipulated by French regulations. To date, the 58 units in France's nuclear infrastructure enforce the in-service inspection rules of the RSE-M code. Operation of 30 commissioned units in China's nuclear infrastructure, corresponding to the M310, CPR-1000 and CPR-600 reactors, is based on the RSE-M code (since 2007, use of AFCEN codes has been required by NNSA for Generation II+ reactors). Contents of the 2016 Edition: Volume I - Rules: Section A - General rules, Section B - Specific rules for class 1 components, Section C - Specific rules for class 2 or 3 components, Section D - Specific rules for components not assigned to any particular RSE-M class; Volume II - Appendices 1 to 8: Appendices 1.0 to 1.9: supporting appendices for the general requirements, Appendix 2.1: appendix associated with chap. 2000 Requalifications, Hydraulic Proof Tests and Hydraulic Tests, Appendices 4.1 to 4.4: appendices associated with chap. 4000 Examination techniques, Appendices 5.1 to 5.8 and RPP2: appendices associated with chap. 5000 Mechanical and Materials, Appendices 8.1 to 8.2: appendices associated with chap. 8000 Maintenance Operations; Volume III: Appendix 3.1 - Visit tables: main primary and secondary systems, EPR pre-service inspection program, Class 2 or 3 vessels; Appendix 3.2 - Inspection Plans For Non-Nuclear Pressure Equipment

46 CFR 109.301 - Operational readiness, maintenance, and inspection of lifesaving equipment.

Science.gov (United States)

2010-10-01

... and cleaning each fuel tank, and refilling it with fresh fuel. (2) Each davit, winch, fall and other...(e); (ii) Maintenance and repair instructions; (iii) A schedule of periodic maintenance; (iv) A... repair equipment. Spare parts and repair equipment must be provided for each lifesaving appliance and...

Advancement of safeguards inspection technology for CANDU nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Lee, Jae Sung; Park, W S; Cha, H R; Ham, Y S; Lee, Y G; Kim, K P; Hong, Y D

1999-04-01

The objectives of this project are to develop both inspection technology and safeguards instruments, related to CANDU safeguards inspection, through international cooperation, so that those outcomes are to be applied in field inspections of national safeguards. Furthermore, those could contribute to the improvement of verification correctness of IAEA inspections. Considering the level of national inspection technology, it looked not possible to perform national inspections without the joint use of containment and surveillance equipment conjunction with the IAEA. In this connection, basic studies for the successful implementation of national inspections was performed, optimal structure of safeguards inspection was attained, and advancement of safeguards inspection technology was forwarded. The successful implementation of this project contributed to both the improvement of inspection technology on CANDU reactors and the implementation of national inspection to be performed according to the legal framework. In addition, it would be an opportunity to improve the ability of negotiating in equal shares in relation to the IAEA on the occasion of discussing or negotiating the safeguards issues concerned. Now that the national safeguards technology for CANDU reactors was developed, the safeguards criteria, procedure and instruments as to the other item facilities and fabrication facilities should be developed for the perfection of national inspections. It would be desirable that the recommendations proposed and concreted in this study, so as to both cope with the strengthened international safeguards and detect the undeclared nuclear activities, could be applied to national safeguards scheme. (author)

Inspection of pressurised nuclear equipment by certified organizations

International Nuclear Information System (INIS)

Marez, Y.

2010-01-01

The A.Q.U.A.P. is a technical association created on the 17 october 1978 grouping control organisms that define methodologies in order to apply the same procedures among their customers. It writes cards to interpret the regulation for organisms, operators and manufacturers. The areas covered by the A.Q.U.A.P. works concern the conformity evaluation of new pressure vessels, qualification of qualification of welding procedures and permanent assemblies and the qualification of the personnel realizing these assemblies, the follow up of the equipment in service. (N.C.)

Status on system inspection and preventive maintenance of HANARO

International Nuclear Information System (INIS)

Kim, Young-Ki; Cho, Yeong-Garp; Kwag, Byung-Ho

1999-01-01

The HANARO is a 30 MW open pool type multi-purpose research reactor with forced light water coolant/moderator flows and heavy water annular reflector. The relatively small reactor core uses a low enriched fuel and is designed to maximize the power density, thus providing the required neutron flux for various research activities. It is mainly used for radioisotope production, nuclear material testing and neutron physics experiments. The initial criticality was achieved February 1995. Considering the importance of their functionality from the safety point of view, some components and equipment are categorized into a nuclear safety grade. There are three different inspection activities for the various reactor systems and components - a Surveillance Inspection(SI) for the safety grades and a Periodic Inspection (PI) for the non-safety grades and In-Service Inspection (ISI) for the ASME Sec.III components. All of the SIs are specified and required by the safety analysis report. The SI also differs from the PI in such a point that all kinds of activities for the SIs should be accompanied by an appropriate quality assurance, while for the PIs it is not necessarily mandatory. In addition, the inspection results for the SIs should go through an examination from regulatory body every two years and specific functions of the critical components or systems are demonstrated under the witness by the governmental inspector. The ISI is required and carried out as per international codes and standards as well as Korean atomic energy regulations. There are 54 SIs, 25 PIs and 4 ISIs for the HANARO. This paper concentrates on the managing strategy and its practices for the SIs and ISIs of the safety-related components, currently being done at HANARO. Most parts of the inspections fall into a group for the periodic performance testing and/or equipment calibration. Some mechanical inspections like a torque measurement are grouped into a preventive maintenance. Lastly the ASME Sec

Development of CANDU fuel in-bay inspection and dimensional measurement system

Energy Technology Data Exchange (ETDEWEB)

Jo, Chang Keun; Cho, Moon Sung; Suk, Ho Chun; Koo, Dae Seo; Park, Kwang June; Jun, Ji Su; Jung, Jong Yeob

2004-09-01

In this report, we describe a spent fuel inspection and dimensional measuring system for CANDU fuel bundles in atmosphere or water. The submissible camera with radiation resistance was used to inspect a spent fuel in water. The design criteria of the dimensional measuring system was set up {+-}0.01mm(10{mu}m) for measuring accuracy. The LVDT (Linear Variable Differential Transformer) was used as measuring sensor in this dimensional measuring system. An LVDT calibration equipment was developed in order to satisfy the required accuracy of the system. Also, aluminum master and CANDU Master with same dimension of fuel bundle was made to calibrate the mechanical error of the dimensional measuring system. The accuracy of the fuel inspection system was examined. The results show that the accuracy in dimensional measurement of fuel rod profile and bearing pad profile, diameter of fuel bundle, fuel rod length, and end plate profile using standard test equipment satisfies the design criteria, i.e., maximum measurement error of {+-}0.01mm(10{mu}m)

Methodology if inspections to carry out the nuclear outages model

International Nuclear Information System (INIS)

Aycart, J.; Mortenson, S.; Fourquet, J. M.

2005-01-01

Before the nuclear generation industry was deregulated in the United States, refueling and maintenance outages in nuclear power plants usually lasted orotund 100 days. After deregulation took effect, improved capability factors and performances became more important. As a result, it became essential to reduce the critical path time during the outage, which meant that activities that had typically been done in series had to be executed in parallel. The new outage model required the development of new tools and new processes, The 360-degree platform developed by GE Energy has made it possible to execute multiple activities in parallel. Various in-vessel visual inspection (IVVI) equipments can now simultaneously perform inspections on the pressurized reactor vessel (RPV) components. The larger number of inspection equipments in turn results in a larger volume of data, with the risk of increasing the time needed for examining them and postponing the end of the analysis phase, which is critical for the outage. To decrease data analysis times, the IVVI Digitalisation process has been development. With this process, the IVVI data are sent via a high-speed transmission line to a site outside the Plant called Center of Excellence (COE), where a team of Level III experts is in charge of analyzing them. The tools for the different product lines are being developed to interfere with each other as little as possible, thus minimizing the impact of the critical path on plant refueling activities. Methods are also being developed to increase the intervals between inspection. In accordance with the guidelines of the Boiling Water Reactor Vessel and Internals project (BWRVIP), the intervals between inspections are typically longer if ultrasound volumetric inspections are performed than if the scope is limited to IVVI. (Author)

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

International Nuclear Information System (INIS)

Spaang, Kjell; Staahl, Gunnar

2013-02-01

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

75 FR 76254 - Official Performance and Procedural Requirements for Grain Weighing Equipment and Related Grain...

Science.gov (United States)

2010-12-08

... DEPARTMENT OF AGRICULTURE Grain Inspection, Packers and Stockyards Administration 7 CFR Part 802 [Docket GIPSA-2010-FGIS-0012] RIN 0580-AB19 Official Performance and Procedural Requirements for Grain Weighing Equipment and Related Grain Handling Systems AGENCY: Grain Inspection, Packers and Stockyards...

Development of automatic ultrasonic testing equipment for reactor pressure vessel

Energy Technology Data Exchange (ETDEWEB)

Jang, Kee Ok; Park, Dae Yung; Park, Moon Hoh; Koo, Kil Mo; Park, Kwang Heui; Kang, Sang Sin; Bang, Heui Song; Noh, Heui Choong; Kong, Woon Sik [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1994-08-01

The selected weld areas of reactor pressure vessel and adjacent piping are examined by remote mechanized ultrasonic testing(MUT) equipment. Since the MUT equipment was purchased from Southwest Research Institute (SwRI) in April 1985, we have performed 15 inservice inspections and 5 preservice inspections. However, the reliability of examination was recently decreased rapidly as the problems which results from the old age of equipment and the frequent movement to plant site to site have occurred frequently. Therefore, the 3-axis control system hardware in occurring many problems among the equipments of mechanized ultrasonic testing (MUT) was designed and developed to cover the examination areas of nozzle-shell weld as specified in ASME Code Section XI and to improve the examination reliability. The new 3-axis control system hardware with the performance of this project was developed to be compatible with the old one and it was used as dual system or spare parts of the old system. Furthermore, the established technologies are expected to be applied to the similar control systems in nuclear power plant. 17 figs, 2 pix, 2 tabs, 10 refs. (Author).

Development of automatic ultrasonic testing equipment for reactor pressure vessel

International Nuclear Information System (INIS)

Jang, Kee Ok; Park, Dae Yung; Park, Moon Hoh; Koo, Kil Mo; Park, Kwang Heui; Kang, Sang Sin; Bang, Heui Song; Noh, Heui Choong; Kong, Woon Sik

1994-08-01

The selected weld areas of reactor pressure vessel and adjacent piping are examined by remote mechanized ultrasonic testing(MUT) equipment. Since the MUT equipment was purchased from Southwest Research Institute (SwRI) in April 1985, we have performed 15 inservice inspections and 5 preservice inspections. However, the reliability of examination was recently decreased rapidly as the problems which results from the old age of equipment and the frequent movement to plant site to site have occurred frequently. Therefore, the 3-axis control system hardware in occurring many problems among the equipments of mechanized ultrasonic testing (MUT) was designed and developed to cover the examination areas of nozzle-shell weld as specified in ASME Code Section XI and to improve the examination reliability. The new 3-axis control system hardware with the performance of this project was developed to be compatible with the old one and it was used as dual system or spare parts of the old system. Furthermore, the established technologies are expected to be applied to the similar control systems in nuclear power plant. 17 figs, 2 pix, 2 tabs, 10 refs. (Author)

Changes in security systems and manufacture equipment and inspection

International Nuclear Information System (INIS)

Paloma, J. J.; Moraga, J. L.

2015-01-01

From the beginning of its industrial activity 30 years ago, the Juzbado factory of Enusa Group has maintained a strong commitment to safety and technological innovation. As a result, we have development new equipment and constantly improving the existing ones, as well as the facilities of the factory in accordance with the internal procedures, with multidisciplinary design teams and review teams. (Author)

30 CFR 250.516 - Blowout preventer system tests, inspections, and maintenance.

Science.gov (United States)

2010-07-01

... seal in the wellhead or BOP stack assembly; (e) Postponing BOP tests. You may postpone a BOP test if... sea conditions permit. You may use television cameras to inspect this equipment. The District Manager...

Sub 20nm particle inspection on EUV mask blanks

NARCIS (Netherlands)

Bussink, P.G.W.; Volatier, J.B.; Walle, P. van der; Fritz, E.C.; Donck, J.C.J. van der

2016-01-01

The Rapid Nano is a particle inspection system developed by TNO for the qualification of EUV reticle handling equipment. The detection principle of this system is dark-field microscopy. The performance of the system has been improved via model-based design. Through our model of the scattering

Automated ultrasonic inspection of IGSCC in DOE production reactor process water piping

International Nuclear Information System (INIS)

Harrison, J.M.; Sprayberry, R.; Ehrhart, W.

1987-01-01

Inspection of nuclear power components has always presented difficulties to the nondestructive testing (NDT) industry from a time consumption and radiation exposure standpoint. Recent advances in computerized NDT equipment have improved the situation to some extent; however, the need for high reliability, precision, reproducibility, and clear permanent documentation are indispensable requirements that can only be met by automatic inspection and recording systems. The Savannah River Plant's inspection program of over 1000 IGSCC-susceptible welds is one of the most complete in the country and offers educational insight into ultrasonic examination technology of thin-wall stainless steel pipe welds

Conveying equipment for various inspection devices through remote control

International Nuclear Information System (INIS)

Kihara, Shizo; Ibe, Tomoyoshi.

1976-01-01

Purpose: To rapidly and accurately convey a flaw detector by means of remote control to a member to be inspected, which is not accessible by an operator, for example, such as a suitable desired wall surface within a reactor. Constitution: Guide tracks are fixedly mounted along the wall surface of the structure by support members. A TV camera mounted on a sliding truck catches an image reflected from a concave reflecting mirror within the flaw detector to obtain information by which a driving mechanism of the self-travelling truck and winch mechanisms of the self-travelling truck and sliding truck may be driven to move the flaw detector to the desired position. In this case, the automatic connecting mechanism is disconnected, and a cable is suitably expanded by a group of travelling trucks and an expansion adjusting mechanism. (Yoshino, Y.)

Recent development for inservice inspection of reactor pressure vessels

International Nuclear Information System (INIS)

Fischer, K.; Engl, G.; Rathgeb, W.; Heumueller, R.

1991-01-01

The German Nuclear Code (KTA-rules) requires a full scope inservice inspection (ISI) of reactor pressure vessels within a period of four years. This has a remarkable influence on plant operation and economy. Therefore, the development of advanced inspection equipment and techniques is directed not only to the enhancement of defect detectability and flaw sizing capabilities but also to reducing inspection times. A new manipulator system for PWR vessels together with fast data processing reduces the time for ISI of modern RPVs to 7 days. A new multichannel UT-system based on ALOK principle offers increased ultrasonic information with comfortable and rapid evaluation and presentation of results together with enhanced sizing capabilities. For specific inspection problems characterized by geometrical complexity the application of phased array probes in connection with UT-tomography provides improved ultrasonic information together with a streamlined manipulator principle and simplification of set up and tear down at the component which results in considerable reduction of radiation exposure. (orig.)

7 CFR 58.128 - Equipment and utensils.

Science.gov (United States)

2010-01-01

... cleaning and inspection. Any opening at the top of the tank or vat including the entrance of the shaft... equally noncorrosive metal it shall be properly tinned over the entire surface. Sanitary seal assemblies at the shaft ends of coil vats shall be of the removable type, except that existing equipment not...

29 CFR 1910.334 - Use of equipment.

Science.gov (United States)

2010-07-01

... remain connected once they are put in place and are not exposed to damage need not be visually inspected... until repairs and tests necessary to render the equipment safe have been made. (iii) When an attachment... grounding conductor. (ii) Attachment plugs and receptacles may not be connected or altered in a manner which...

Automatic ultrasonic pre-service, and in-service inspection of pressurized components of the primary circuit of nuclear power stations

International Nuclear Information System (INIS)

Muller, G.P.; Hallermeier, L.; Heinrich, D.; Grabendorfer, W.; Rebrmann, M.

1985-01-01

Ultrasonic pre-service and especially in-service inspection activities on the primary circuit of nuclear power stations form an essential part of the maintenance work that must be performed throughout the lifetime to ensure plant integrity. Consequently, the equipment required to carry out these inspections must be continuously improved in respect of reliability, safety, accuracy and ease of handling in order to minimize disturbances and repairs and reduce radiation exposure of the personnel. The authors' discussion of technique, equipment and performance of automated ultrasonic inspection is based on 15 years of experience in the testing of components of the primary circuit in nuclear power stations. To cover all inspection areas of the RPV of a PWR, four different manipulators are required, two for the closure head, one for the studs and one for the cylindrical shell and bottom closure. The use of the newly developed equipment, which naturally meets all the recommendations of the licensing authorities, allows for the automatic inspection of the components of primary circuit of nuclear power stations and the thus helps to substantially decrease the radiation exposure of the personnel. All the manipulators and their control consoles were designed and manufactured by M.A.N., Nuremberg while the ultrasonic electronic system was developed by Krautkramer, Cologne

Ultrasonic inspection method and system for detection of steeple cracking in turbine disk rims

International Nuclear Information System (INIS)

Birring, A.S.; Lamping, G.A.; Van der Veer, W.R.; Hanley, J.J.

1990-01-01

Steam turbine disks which operate under high cyclic stress in a moist environment can develop cracks in the disk-rim steeples. Detection of these cracks using nondestructive testing methods is necessary to assure safe operation and avoid unnecessary disk replacement. Both magnetic particle (MT) and ultrasonic testing (UT) can be used to inspect the steeples; however, UT can be used without removing the blades. A system for inspecting bladed steeples has been developed that can be applied on a range of disks including those in Westinghouse, General Electric, and Allis Chalmers turbines. The system performs an inspection as the turbine is rotated at slow speeds over turning rolls. This procedure greatly reduces inspection time because the inspection can be done without deblading the disk or resetting the inspection equipment for different rim segments

Development of a remote inspection robot for high pressure structures

Energy Technology Data Exchange (ETDEWEB)

Lee, Jae C.; Kim, Jae H.; Choi, Yu R.; Moon, Soon S

1999-10-01

The high pressure structures in industrial plants must be periodically inspected for ensure their safety. Currently, the examination of them is manually performed by human inspectors, and there are many restrictions to examine the large containers which enclose dangerous chemicals or radioactive materials. We developed a remotely operated robot to examine these structures using recent mobile robot and computer technologies. Our robot has two magnetic caterpillars that make the robot can adhere to the structures made of steel like materials. The robot moves to the position for examination, and scans that position using ultrasonic probes equipped on it's arm, and transmits the result to the inspector according to his/her commands. Without building any auxiliary structures the robot can inspect the places where manual inspection can't reach. Therefore the robot can make shortening the inspection time as well as preventing the inspector from an accident. (author)

Development of a remote inspection robot for high pressure structures

International Nuclear Information System (INIS)

Lee, Jae C.; Kim, Jae H.; Choi, Yu R.; Moon, Soon S.

1999-10-01

The high pressure structures in industrial plants must be periodically inspected for ensure their safety. Currently, the examination of them is manually performed by human inspectors, and there are many restrictions to examine the large containers which enclose dangerous chemicals or radioactive materials. We developed a remotely operated robot to examine these structures using recent mobile robot and computer technologies. Our robot has two magnetic caterpillars that make the robot can adhere to the structures made of steel like materials. The robot moves to the position for examination, and scans that position using ultrasonic probes equipped on it's arm, and transmits the result to the inspector according to his/her commands. Without building any auxiliary structures the robot can inspect the places where manual inspection can't reach. Therefore the robot can make shortening the inspection time as well as preventing the inspector from an accident. (author)

Underwater inspection training in intense radiation field

International Nuclear Information System (INIS)

Taniguchi, Ryoichi

2017-01-01

Osaka Prefecture University has a large dose cobalt 60 gamma ray source of about 2 PBq, and is engaged in technological training and human resource development. It is assumed that the decommissioning underwater operation of Fukushima Daiichi Nuclear Power Station would be the focus. The university aims at acquisition of the basic of underwater inspection work under radiation environment that is useful for the above purpose, radiation measurement under water, basic training in image measurement, and aims as well to evaluate the damage of imaging equipment due to radiation, and master practical knowledge for the use of inspection equipment under a large dose. In particular, it is valuable to train in the observation of Cherenkov light emitted from a large dose cobalt radiation source in water using a high sensitivity camera. The measurement of radiation dose distribution in water had difficulty in remote measurement due to water shielding effect. Although it took much time before, the method using high sensitivity camera is easy to sequentially perform two-dimensional measurement, and its utility value is large. Its effect on the dose distribution measurement of irregularly shaped sources is great. The contents of training includes the following: radiation source imaging in water, use of a laser rangefinder in water, dose distribution measurement in water and Cherenkov light measurement, judgment of equipment damage due to irradiation, weak radiation measurement, and measurement and decontamination of surface contamination. (A.O.)

Special servicing equipment for reactor pressurized vessel stud hole and stud accessories

International Nuclear Information System (INIS)

Li Jianglian

1999-01-01

The author briefly introduces the design and manufacture of nuclear island special servicing equipment of Nuclear Power Institute of China. Maintenance process of reactor pressurized vessel (RPV) stud hold and stud accessories the special servicing equipment include RPV flange dummy, closed-circuit television (CCTV) inspection equipment, RPV stud hole expandable comb, RPV stud hole polisher, RPV stud hold thread lubricating equipment, RPV stud hole thread miller and RPV stud hole camera. It is presented how eight kinds of special servicing equipment perform the maintenance process concerning their function, structure, and characteristics, their practical use on site is also introduced

Initial acceptance test experience with FFTF plant equipment

International Nuclear Information System (INIS)

Brown, R.K.; Coleman, K.A.; Mahaffey, M.K.; McCargar, C.G.; Young, M.W.

1978-09-01

The purpose of this paper is to examine the initial acceptance test experience of certain pieces of auxiliary equipment of the Fast Flux Test Facility (FFTF). The scope focuses on the DHX blowers and drive train, inert gas blowers, H and V containment isolation valves, and the Surveillance and In-service Inspection (SISI) transporter and trolley. For each type of equipment, the discussion includes a summary of the design and system function, installation history, preoperational acceptance testing procedures and results, and unusual events and resolutions

Experience with the WWER-440 MW reactor pressure vessel in-service inspections and evaluation of their results

International Nuclear Information System (INIS)

Brumovsky, M.; Kralovec, J.; Prepechal, J.; Sulc, J.

1989-01-01

The Power Machinery Plant of Skoda Works in Plzen carries out in-service inspections of WWER-440 MW reactor pressure vessels by means of remote controlled inspection equipment - the TRC reactor test system, and some other inspections devices. The results of the in-service inspections were evaluated by methods based on the fracture mechanics approach, the knowledge of stress and strain distribution, and the operating history of the pressure vessels. Examples of types of defects found and their analysis are shown. (author). 1 tab

The Management Advisory Committee of the Inspection Validation Centre - fifth report

International Nuclear Information System (INIS)

1988-07-01

The Management Advisory Committee of the Inspection Validation Centre (IVC/MAC) was set up by the Chairman of the UKAEA early in 1983 with terms of reference to review the policy, scope, procedure and operation of the Inspection Validation Centre, to supervise its operation and to advise and report to the UKAEA appropriately. The Inspection Validation Centre (IVC) has been established at the UKAEA Northern Research Laboratories, Risley for the purpose of validating the procedures, equipment and personnel proposed by the CEGB for use in the ultrasonic inspection at various stages of the fabrication, erection and operation of the CEGB's PWR reactor pressure vessel and such other components as are identified by the CEGB. This report, for 1987/8, states that the IVC has continued to make progress in the provision of the validation services as specified. (author)

Inspection systems for valves monitoring at EDF

International Nuclear Information System (INIS)

Germain, J.L.; Granal, L.; Provost, D.; Touillez, M.

1997-01-01

Electricite de France (EDF) makes increasing use of valve inspection systems to guarantee safety in its pressurized water reactor plants, improve plant availability and facilitate condition-based maintenance. A portable system known as SAMIR has been developed for inspection of motor-operated valves, and is now used on EDF's 900-MW sites. For its 1300-MW units, EDF has chosen a more complete system which enables measuring thrust on the valve stem during a maneuver, using a sensor mounted on the yoke. To detect internal vale leaks, an on-site assessment has demonstrated the economic benefits of acoustic emission techniques. EDF has equipped its sites with analog leak detection systems which may soon be replaced by a digital model now being developed. (authors)

Integration of process-oriented control with systematic inspection in FRAMATOME-FBFC fuel manufacturing

International Nuclear Information System (INIS)

Kopff, G.

2000-01-01

The classical approach to quality control is essentially based on final inspection of the product conducted through a qualified process. The main drawback of this approach lies in the separation and , therefore, in the low feedback between manufacturing and quality control, leading to a very static quality system. As a remedy, the modern approach to quality management focuses on the need for continuous improvement through process-oriented quality control. In the classical approach, high reliability of nuclear fuel and high quality level of the main characteristics are assumed to be attained, at the manufacturing step, through 100% inspection of the product, generally with automated inspection equipment. Such a 100% final inspection is not appropriate to obtain a homogeneous product with minimum variability, and cannot be a substitute for the SPC tools (Statistical Process Control) which are rightly designed with this aim. On the other hand, SPC methods, which detect process changes and are used to keep the process u nder control , leading to the optimal distribution of the quality characteristics, do not protect against non systematic or local disturbances, at low frequency. Only systematic control is capable of detecting local quality troubles. In fact, both approaches, SPC and systematic inspection, are complementary , because they are remedies for distinct causes of process and product changes. The term 'statistical' in the expression 'SPC' refers less to the sampling techniques than to the control of global distribution parameters of product or process variables (generally location and dispersion parameters). The successive integration levels of process control methods with systematic inspection are described and illustrated by examples from FRAMATOME-FBFC fuel manufacturing, from the simple control chart for checking the performance stability of automated inspection equipment to the global process control system including systematic inspection. This kind of

Storage options for Long Length Contaminated Equipment (LLCE) items

International Nuclear Information System (INIS)

Hodgson, R.D.

1994-11-01

A review of the Washington state requirements for the storage of long equipment items removed from tanks indicate that if the contaminated materials on the long equipment items are analyzed and determined to be DW, and not EHW, the containers can be stored on an uncovered, RCRA approved, storage pad. Long equipment items contaminated with reportable levels of EHW, or suspected of being contaminated with EHW, must be protected from the elements by means of a building or other protective covering that otherwise allows adequate inspection of the containers. Storage of the long equipment item containers on an uncovered storage pad is recommended and will reduce construction costs for new storage by an estimated 60 percent when compared to construction costs for enclosed storage

Overview of the use and radiological protection of body scanner equipment in Brazil

International Nuclear Information System (INIS)

Souza, D.A.P.; Nascimento, C.S.; Silva, F.C.A. da

2017-01-01

After security incidents in recent years, there is a growing need for security at airports, ports and prisons. In the fight against terrorism, smuggling and illegal entry of material, X-rays are used for non-invasive inspection of people. Traditionally, surveillance has been done exclusively on people by metal detection techniques or by intimate search. But in today's globalized world, and given concern for international security, governments are considering introducing a new series of technologies at airports and prisons, which reveal what an individual can carry under their clothes when traveling or entering visitation in prisons. Body inspection equipment, also called body scanners or 'body scanner', which can detect metallic and non-metallic objects hidden in a person's body, such as weapons, drugs, precious stones, cell phones, etc. This work shows the types of body inspection equipment, the radiation doses involved, and the radiation protection aspects that are critical to maintaining the safety of all users

Proceedings of the European Symposium on Pressure Equipment - ESOPE 2004

International Nuclear Information System (INIS)

2004-01-01

The symposium on Pressure Equipment Technology, organised every three years by the AFIAP (Association Francaise des Ingenieurs en Appareils a Pression), for the second time is organised at the European level. It is the 'European Symposium on Pressure Equipment, ESOPE 2004'. This symposium is placed under the patronage of the Minister of Industry. The central theme of ESOPE 2001 has been the European Directives for Fixed Equipment (PED) and for Transportable Equipment (TPED). ESOPE 2004 will be a state on the application of these Directives after 3 years of use. The first plenary session will made the comparison of some National codes with EN13445 standard and of the evolution of the Asme code. But the principal theme of the second plenary session and the panel, where European experts will answer to your questions, will be on 'Pressure equipment life management'. It therefore seems important to incorporate this subject into the agenda of this symposium in order to allow widespread dialogue between the industrial members concerned. Our association, AFIAP, has the advantage of regrouping all the industrial partners concerned, from the end user and the administrative body responsible for equipment safety, to the pressure equipment fabricator and his materials suppliers, also including those bodies responsible for design, inspection and certification. To improve availability of equipment and reduce production costs the most efficient way is the development of technology. It is essential to improve competitiveness of European companies. Research is necessary, but the results must be available to everyone, including small and medium-sized industries. ESOPE 2004 has 3 technical sessions in parallel, which will be followed, by many fruitful exchanges of experience: - design/materials - fabrication/welding/inspection - fitness for service. You will find on a CD-Rom all the contributions which have been presented. (authors)

7 CFR 61.33 - Equipment of sampler; contents of certificate.

Science.gov (United States)

2010-01-01

... 7 Agriculture 3 2010-01-01 2010-01-01 false Equipment of sampler; contents of certificate. 61.33 Section 61.33 Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (Standards, Inspections, Marketing Practices), DEPARTMENT OF AGRICULTURE (CONTINUED) REGULATIONS...

New developments for optimization of automatic inspections in nuclear power plants

International Nuclear Information System (INIS)

Bollini, G.J.; Gonzalez, B.

1989-01-01

One of the most important factors to be taken into acount with respect to remote control mechanized inspection tasks carried out during refueling outages in nuclear power plants, which include components and systems as varied as the reactor vessel, nozzles, piping, vessel head closure bolts, turbine discs, etc., is the unification of systems used to control the inspection systems themselves. Likewise, the implementation in these systems of specific functions simplifying operational sequences and confirming correct execution of work implies a set of criteria that must be taken into account if the reliability of the tasks carried out is to be increased. The system presented in this paper, SIROCCO (Sistema Robotizado de Control) has been designed taking into consideration the above mentioned criteria, with two clear obectives in mind: a reduction in inspection times and in the dose received by the participating technical personnel, and an increase in the reliability of the electronic equipment used. In February and March of this year, during shutdown of a BMR-type nuclear power plant, several SIROCCO control units were usids in mechanized inspection systems of various kinds, applicable to components such as those mentioned above, with forecasts regarding the reduction of inspection times being met. The main reasons for this reduction were the familiarity of the operators with this single control system, the unification of replacement parts for equipment maintenance and the availability of interchangeable units. This philosophy of unification of electronic systems also includes data acquisition and the transmission of information between different areas, which require the unification of control systems already commented and accomplished. This course of action is currently under development at Tecnatom. (author). 4 figs

Advances based on digital technology named TEDDY+ for inspection of eddy current

International Nuclear Information System (INIS)

Barcenilla, V.; Hernandez, J.; Ribes, B.

2007-01-01

As a result of the recent developing line of eddy current data acquisition system a new product based on digital technology named TEDDY+, comes to the market. With only 4 kg of weight constitutes a great advance with regards to other equipment's available in the market. These advances, have enabled, among others, to increase considerably the signal to noise (S/N) ratio, avoid typical saturation problems in the eddy current signal, increase the inspection speed, eliminate the reference probe, detect the air/tube signal in real time, and the possibility to integrate the tester inside a push puller thanks to its reduced size and to have integrated as part of the ET equipment the mechanical systems control board. Two product lines have been developed, one oriented to any market and application (nuclear market, industrial and aeronautical, chemical and petrochemical, etc) and other specially dedicated to the massive inspection of tubes, named TEDDY+SP (Suitcase Pusher). Both lines are prepared to use eddy current arrays which clearly constitute the future of the eddy current inspection systems. The new TEDDY+ line of products presented in this paper constitutes one of the most powerful and reliable existing in the market. These improvements and novelties place the new ET inspection system from Tecnatom as one of the most powerful and reliable in the market. (Author)

Ultrasonic phased arrays for nondestructive inspection of forgings

International Nuclear Information System (INIS)

Wuestenberg, H.; Rotter, B.; Klanke, H.P.; Harbecke, D.

1993-01-01

Ultrasonic examinations on large forgings like rotor shafts for turbines or components for nuclear reactors are carried out at various manufacturing stages and during in-service inspections. During the manufacture, most of the inspections are carried out manually. Special in-service conditions, such as those at nuclear pressure vessels, have resulted in the development of mechanized scanning equipment. Ultrasonic probes have improved, and well-adapted sound fields and pulse shapes and based on special imaging procedures for the representation of the reportable reflectors have been applied. Since the geometry of many forgings requires the use of a multitude of angles for the inspections in-service and during manufacture, phased-array probes can be used successfully. The main advantages of the phased-array concept, e.g. the generation of a multitude of angles with the typical increase of redundancy in detection and quantitative evaluation and the possibility to produce pictures of defect situations, will be described in this contribution

Underwater inspection and maintenance programs within nuclear and non-nuclear related operating systems

International Nuclear Information System (INIS)

Vallance, C.; Goulet, B.; Black, S.

2008-01-01

The increasing age of the nuclear and non-nuclear power generating facilities requires extended inspection, repair and maintenance (IRM) activities to prolong the operation of these facilities past their original design life. Commercial divers are often utilized to perform critical work at nuclear power plants, fuel reprocessing plants, waste storage facilities, and research institutions. These various tasks include inspection, welding, mechanical modifications and repairs, coating applications, and work associated with plant decommissioning. Programs may take place in areas such as the reactor vessel, equipment pool, spent fuel pool, and suppression chamber using manned intervention and remotely operated vehicles. Some of these tasks can also be conducted using remotely operated vehicles (ROV's). Although specialist robots are not uncommon to the nuclear industry, the use of free-swimming vehicle's and remote systems for the inspection of underwater assets has increased due to improvements of the supporting technologies and information requirements needed to extend the life of these facilities. This paper will provide an overview of the procedures and equipment necessary to perform unique work tasks using manned and unmanned techniques. (author)

Device for inspecting the inside of a nuclear reactor

International Nuclear Information System (INIS)

Kurata, Masuo.

1985-01-01

Purpose: To apply illumination concentrically to a particular place and enable rapid and accurate inspection for the detailed portions by making such that the viewing direction of a television camera disposed in water and the direction of illumination of a submerged illumination tool can be varied optionally by remote control. Constitution: In the conventional inspection equipments for the inside of the reactor, a submerged illumination tool has merely been suspended by a cable and it has been difficult to effectively control the relative position with the television camera disposed in water. In this invention, the television camera disposed in water and a submerged illumination tool are rotatably disposed by way of a clamp to an inspection device main body. Then, the clamp can be rotated by the remote control and, further, the inspection device is suspended by way of a rope from a winding device disposed above the pressure vessel. In such a constitution, the submerged illumination tool can be adjusted to an optimal position to the television camera disposed in water. (Kamimura, M.)

A development methodology for a remote inspection system with JAVA and socket

International Nuclear Information System (INIS)

Choi, Yoo Rark; Lee, Jae Cheol; Kim, Jae Hee

2004-01-01

We have developed RISYS (Reactor Inspection System) which inspects reactor vessel welds by an underwater mobile robot. The system consists of a main control computer and an inspection robot which is controlled by the main control computer. Since the environments of the inspection tasks in a nuclear plant, like in other industrial fields, is very poor, serious accidents often happen. Therefore the necessity for remote inspection and control system has increased more and more. We have carried out the research for a remote inspection model for RISYS, and have adopted the world wide web, java, and socket technologies for it. Client interface to access the main control computer that controls the inspection equipment is essential for the development of a remote inspection system. It has been developed with a traditional programming language, for example, Visual C++, Visual Basic and X-Window. However, it is too expensive to vend and maintain the version of a interface program because of the different computer O/S. Nevertheless web and java technologies come to the fore to solve the problems but the java interpreting typed language could incur a performance problem in operating the remote inspection system. We suggest a methodology for developing a remote inspection system with java, a traditional programming language, and a socket programming that solves the java performance problem in this paper

3. report of the Management Advisory Committee of the Inspection Validation Centre

International Nuclear Information System (INIS)

1986-07-01

The Inspection Validation Centre (IVC) has been established at the UKAEA Risley Nuclear Power Development Laboratories for the purpose of validating procedures, equipment and personnel proposed by the CEGB for use in the ultrasonic inspection at different stages of the fabrication, erection and operation of the CEGB's proposed PWR pressure vessel and such other components as are identified by the CEGB. Technical progress since May 1985 is reported. The number of operators receiving certificates for detection and sizing of flaws is given. (author)

46 CFR 159.005-11 - Approval inspection or test report: Contents.

Science.gov (United States)

2010-10-01

... 46 Shipping 6 2010-10-01 2010-10-01 false Approval inspection or test report: Contents. 159.005-11 Section 159.005-11 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) EQUIPMENT... representation is also punishable as a crime under 18 U.S.C. 1001. ...

Methodology for the inspection of items important to safety

International Nuclear Information System (INIS)

Ishack, G.

1981-11-01

A description is given of the inspection methods adopted by the Canadian Atomic Energy Control Board. From the outset of the industry in Canada, resident officers have been assigned to nuclear power stations. These inspectors have unlimited access to equipment, documents and personnel at the station. They work closely with Head Office specialists, provincial authorities, and private consultants

Reduced program of inspection by induced currents for condenser of Embalse nuclear power plant

International Nuclear Information System (INIS)

Obrutsky, L.; Mendonca, H.

1986-01-01

In this work it's presented a reduced inspection in service program by the technique of induced currents to the turbine condenser of Embalse's Power Plant (Cordoba). The authors based its elaboration on the results obtained in the exam of a small number of tubes and on experience obtained through four inspections in the condensers of Atucha I Power Plant, through mathematical models of oxygen and ammoniac distribution in both Power Plants, and its experimental verification in the case of Atucha I. This program improves the quality of inspection thereby reducing time, equipment and personnel employed. (C.M.) [pt

The use of NPAR results in plant inspection activities

International Nuclear Information System (INIS)

Gunther, W.; Taylor, J.

1990-01-01

The US Nuclear Regulatory Commission's (NRC's) Nuclear Plant Aging Research (NPAR) Program is a hardware oriented research program which has produced a large data base of equipment and system operating, maintenance, and testing information. Equipment and systems which have a propensity for age related degradation are identified, and methods for detecting and mitigating aging effects have been evaluated. As plants age, it becomes increasingly important that NRC inspectors be cognizant of plant aging phenomena. This paper describes the NPAR information which can enhance inspection activities, and provides a mechanism for making pertinent research available to the inspectors

Field Operations and Enforcement Manual for Air Pollution Control. Volume II: Control Technology and General Source Inspection.

Science.gov (United States)

Weisburd, Melvin I.

The Field Operations and Enforcement Manual for Air Pollution Control, Volume II, explains in detail the following: technology of source control, modification of operations, particulate control equipment, sulfur dioxide removal systems for power plants, and control equipment for gases and vapors; inspection procedures for general sources, fuel…

Development of remote handling tools and equipment

International Nuclear Information System (INIS)

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

1997-01-01

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

A review of digital radiography technology for valve inspection

International Nuclear Information System (INIS)

Stoev, K.; Guerout, F.M.; Horn, D.

2008-01-01

There are thousands of valves in a nuclear power plant (NPP) used for control, safety and checks in various plant systems, so there is a well-identified need for fast and reliable inspection and diagnostics of valves. Digital radiography can provide considerable improvements to the inspection and testing procedures for valves in comparison to classical film radiography. These improvements can lead to significant financial advantages by providing real-time inspection results, significantly reduced inspection and decision-making time, and reduced operational cost. Digital image processing, including digital image enhancement, digital archiving, and digital communication of the images and the results, is also a considerable advantage over classical film radiography technology. Another advantage of digital radiography technology is the improved safety and the reduced environmental impact due to reduced exposure/test times, use of smaller exclusion zones, elimination of chemical processing, and absence of disposable materials. This paper reviews the existing technology and evaluates the potential of digital radiography for inspection and diagnostics of valves. Station needs and requirements are assessed, and the safety, environmental and economical constraints of digital radiography techniques estimated. The advantages and disadvantages of different digital radiography equipment are compared, and their limitations and characteristics studied. (author)

ASME section XI - design and access requirements for in-service inspection

International Nuclear Information System (INIS)

Davis, D.D.

1982-01-01

The Owner of a nuclear power plant has the regulatory commitment to perform Section XI in-service inspection throughout the service life of a plant. In anticipation of what will be needed to perform adequately the required examinations and tests, sub-article IWA-1500 of Section XI not only requires that sufficient access be provided to accommodate equipment and inspection personnel but also requires that other provisions be considered such as: component surface preparations, material selections, shielding, removal and storage of hardware, handling equipment, and provisions for repairs and replacements. It is, therefore, the owner's and the architect engineer's responsibility to ensure that proper design and access provisions are incorporated to enable the owner to meet his commitments. Since the architect engineer usually has the prime responsibility for the implementation of design criteria, the owner must ensure that these provisions be considered in each phase of design and construction. The benefits of this can result in shorter outages, more meaningful examinations and tests and less radiation exposure of inspection personnel. This paper will address in detail those topics that affect design and access provisions which need to be considered during the design and construction of a nuclear power plant. (author)

The portable GIS applied to geotechnical inspections; O GIS portatil para inspecoes geotecnicas

Energy Technology Data Exchange (ETDEWEB)

Rabaco, Lis M.; Lins, Alexandre F. [PETROBRAS S.A., Rio de Janeiro, RJ (Brazil); Costa, Rogerio M.; Freitas, Carlos F. [CONCREMAT, Rio de Janeiro, RJ (Brazil)

2005-07-01

The purpose of this paper is to implement an interface using tool to pack the GIS application to carry out a field inspection. The solution was implemented on pocket equipment using a simplified map and database integrated with the GIS Corporative. The main objective is to avoid paper work in field inspections. The emphases are on geotechnical inspections in order to assist the recuperation of information about points with geotechnical risk. There are interfaces with external device as GPS for insertion of points of risk. A set of tools are developed for bidirectional synchronization among the Corporative GIS and the pocket devices. The project focused geotechnical inspections on field, in order to synchronize automatically the information collected with the pocket GIS application with a Web server, packing all information from field operation to managers. (author)

Promoting transparency: The Korean national inspection experience

International Nuclear Information System (INIS)

Kim, B.K.

1999-01-01

The Republic of Korea started the LAMA full-scope safeguards inspection with the TRIGA research reactor in 1976 when the nuclear industry was at its infancy. Over two decades of rapid economic growth was propelled by stable supply of electricity, substantially from nuclear energy. Today nearly half of the nations electricity comes from sixteen operating nuclear power plants (12 LWRs + 4 OLRs). Total number of facilities under IAEA inspection reaches 30 where the Agency conducts about 400 PDIs annually. Within the last decade, nuclear transparency in Korea has transformed into the international norm primarily from the needs of rapidly expanding domestic nuclear program. In addition, possibility of North/South mutual inspection helped initiate the national inspection regime in addition to the IAEA inspection. The Technology Center for Nuclear Control was established at KAERI in 1994 in order to maintain the nation's nuclear verification expertise in support of the Korean government. National inspections have been carried out simultaneously with the IAEA inspection since 1997 with trial facilities, and all domestic facilities are being inspected from this year. Necessary legal framework and working procedures were developed and field-tried for LWRs, OLRs, fuel fabrication plants and research reactor facilities. Although the inspection equipment and technology along with the safeguards criteria are quite similar to those of the Agency, it is essential to maintain the independent conclusion capabilities between IAEA and the national authority. Substantial improvements in the IAEA safeguards inspection goal attainments since 1997 are credited to the increasing safeguards awareness among operators and SSAC. Further work is necessary to develop the evaluation criteria based on the field inspection results to meet the national inspection goals. The Korean Government signed the Additional Protocol with IAEA on June, 1999 after much deliberation since it involves facilities

Application of the risk based inspection in chemical and nuclear installations: a critical evaluation

International Nuclear Information System (INIS)

Sousa, Anna Leticia Barbosa de

2004-01-01

Risk-based Inspection (RBI) has arisen as an opportunity for the industry to give a specific treatment to items as equipment integrity, failures consequences and the level of risk of each piece of equipment in the inspection programs definitions. Risk-based inspection programs are replacing the traditional ones based on prescriptive requirements, for both the oil and nuclear industries. The aim of this thesis is to demonstrate how the nuclear industry has gotten over several difficulties in implementing risk-based programs considering that its safety design and regulations have traditionally been based on deterministic and prescriptive criteria and requirements. During the development of the work, the study has shown how the absence of a rigid regulation favored the dissemination of RBI diffusion in the oil industry, mainly in the USA, where such industries do not face those difficulties found by the European plants, as long as it is well known that in Europe there are complex interrelations among documents from different countries with diversity of regulation procedures. (author)

Catalog of physical protection equipment. Book 1: Volume I. Barriers and structural components

International Nuclear Information System (INIS)

Haberman, W.

1977-06-01

A catalog of commercially available physical protection equipment has been prepared for use by the U.S. Nuclear Regulatory Commission (NRC). Included is information on barrier structures and equipment, interior and exterior intrusion detection sensors, entry (access) control devices, surveillance and alarm assessment equipment, contraband detection sensors, automated response equipment, general purpose displays and general purpose communications, with one volume devoted to each of these eight areas. For each item of equipment the information included consists of performance, physical, cost and supply/logistics data. The entire catalog is contained in three notebooks for ease in its use by licensing and inspection staff at NRC

Catalog of physical protection equipment. Book 3: Volume VII. General purpose display components

International Nuclear Information System (INIS)

1977-06-01

A catalog of commercially available physical protection equipment has been prepared under MITRE contract AT(49-24)-0376 for use by the U. S. Nuclear Regulatory Commission (NRC). Included is information on barrier structures and equipment, interior and exterior intrusion detection sensors, entry (access) control devices, surveillance and alarm assessment equipment, contraband detection sensors, automated response equipment, general purpose displays and general purpose communications, with one volume devoted to each of these eight areas. For each item of equipment the information included consists of performance, physical, cost and supply/logistics data. The entire catalog is contained in three notebooks for ease in its use by licensing and inspection staff at NRC

Qualification of the Improved rotating probe process for steam generator tubes inspection

International Nuclear Information System (INIS)

Caston, D.

2002-01-01

In 1997, EDF called for bids to Eddy Current (EC) probes manufacturers to supply rotating probes in order to improve the inspection of the Roll Transition Zone of Steam Generator tubes. Several probes met EDF requirements, and after full assessment, EDF chose one between several EC rotating probe prototypes. For the state of its technical study, EDF chose CEGELEC NDTs services among French ISI SG NDT providers, to inspect a limited number of tubes on two French NPP in 2000 with this prototype. Improved Rotating Probe process technical requirements were provided by EDF with the SG contract specifications in June 2000. They dictate technique performances level and acquisition rate of this new process using two techniques at the same time: - STL classic technique applied for detection and sizing of axial cracks; - STT technique, applied for detection and Sizing of circumferential cracks and wear. It has to be used, instead of classic STL process, without increasing inspection duration and SG occupancy. In competition for the qualification, CEGELEC NDT decided to design a new probe with its providers, including the two EC sensors and meeting EDF's requirements. Two another new equipment, designed in CEGELEC NDT laboratories, have been integrated into Improved Rotating Probe Process: - 'STL Lift', new rotating probe push-puller for Roll Transition Zone inspection; - 'ANASTL', on-line STL and STT data quality check, on-line data processing and analysis software. Without talking about performances of the technique and results obtained on site, this paper presents the new equipment, the different phases of the qualification conducted according to RSE-M rules, the first field experiences in August 2001 and the feedback experience of following site inspections. (author)

Risk informed In-service Inspection

International Nuclear Information System (INIS)

Corak, Z.

2003-01-01

Safety of nuclear power plants is one of the most important conditions for their acceptance. Safety is being acheived by numerous methods and techniques in phase of design, manufacturing and maintenance of the nuclear power plants. In-service Inspection (ISI) has a significant role in avoidances of failure in components of nuclear power plants just the same as in assurance of their integrity. Non-destructive examinations are performed periodically in accordance with 10 CFR 50 50.55a and ASME Boiler and Pressure Vessel Code section XI which is referenced by 10 CFR 50.55a. Nondestructive examinations provide information about a current condition of equipment at nuclear power plants and about any damage, defect or degradation mechanism. A lot of effort is often spent in situations in which the probability of failure and their effects on safety have a very low impact. Practical experience shows that failures can often occur at locations where the inspection has never been performed. Costs and expenses of in-service inspections are very high. Therefore, the accent has to be on locations with significant risk to safety. Many years of nuclear power plants' operation and maintenance have resulted in a more broad knowledge of degradation mechanism and the most susceptible locations and huge databases of different nuclear power plants' components. U.S. Nuclear Regulatory Commission (NRC) and the nuclear industry have recognized that probabilistic risk assessment (PRA) has developed and changed to be more useful in improvement of traditional engineering approaches in nuclear power plants regulation. After the publication of its policy statement on the use of PRA in nuclear regulatory activities, the Commission ordered the NRC staff to develop a regulatory framework that incorporated risk insights. The American Society of Mechanical Engineers (ASME) initiated Code Case N-560, N-577, and N-578 that address the importance of categorization and inspection of piping using risk

Poolside fuel assembly inspection campaigns performed at Kernkraftwerk Leibstadt during summer 1997

International Nuclear Information System (INIS)

Zwicky, H.U.; Wiktor, C.G.; Schrire, D.

1998-01-01

. Planning and data evaluation done in close co-operation between fuel supplier and plant, and a well trained, highly motivated inspection team, supported by experienced operators of the fuel handling equipment, applying well proven equipment, are the prerequisites for a successful inspection campaign. (author)

Advanced Visualization Software System for Nuclear Power Plant Inspection

International Nuclear Information System (INIS)

Kukic, I.; Jambresic, D.; Reskovic, S.

2006-01-01

Visualization techniques have been widely used in industrial environment for enhancing process control. Traditional techniques of visualization are based on control panels with switches and lights, and 2D graphic representations of processes. However, modern visualization systems enable significant new opportunities in creating 3D virtual environments. These opportunities arise from the availability of high end graphics capabilities in low cost personal computers. In this paper we describe implementation of process visualization software, developed by INETEC. This software is used to visualize testing equipment, components being tested and the overall power plant inspection process. It improves security of the process due to its real-time visualization and collision detection capabilities, and therefore greatly enhances the inspection process. (author)

Licensee contractor and vendor inspection status report. Quarterly report, April 1982-June 1982

International Nuclear Information System (INIS)

1982-07-01

Firms designing nuclear steam supply systems, architect engineering firms doing design work on nuclear power plants, and certain selected vendors are currently inspected on a regular basis by the NRC. NRC inspectors, during periodic inspections, ascertain through direct observation of selected activities (including review of processes and selected hardware, discussions with employees and selected record review) whether a licensee or contractor is satisfactorily implementing a quality assurance program. If nonconformances with QA commitments are found, the inspected organization is requested to take appropriate corrective action and to institute preventive measures to preclude recurrence. In addition to the QA program inspections, NRC also conducts reactive inspections of the licensee's contractors and vendors. These are special, limited scope inspections to verify that organizations supplying safety-related equipment or services to licensed facilities are exercising appropriate corrective/preventive measures when defects or conditions which could adversely affect the safe operation of such facilities are identified and that these organizations are complying with the NRC requirements which govern the evaluation and reporting of such conditions

Inspection activities of other strategic points (OSPs) at Rokkasho Reprocessing Plant

International Nuclear Information System (INIS)

Kaifuki, Yukinobu; Ebata, Takashi; Nakano, Sadayuki; Fujimaki, Kazunori

2008-01-01

At Rokkasho Reprocessing Plant (RRP), Active Test (AT) using actual spent fuels for the final confirmation of the equipment and the system has been performed since March 31, 2006 toward the commercial operation. The safeguards inspection during AT is required in the same manner as commercial operation condition because plutonium is handled. In RRP automated verification systems are established by using unattended verification systems including a number of process monitoring systems along with main plutonium handling process from the spent fuel storage until the MOX product storages. Even under the modernized safeguards, inspection activities at Other Strategic Points (OSPs) are required to confirm plant status in accordance with requirements of the IAEA safeguards criteria. This paper presents procedures and inspection activities at OSPs which has been implemented in RRP since start of AT. (author)

15. Internal symposium on recent progress of nondestructive inspection and monitoring technologies for nuclear power plants

International Nuclear Information System (INIS)

1994-01-01

At the symposium, lectures were given on the recent development of the nondestructive inspection technology for nuclear power plants, the trend regarding the nondestructive inspection in foreign countries (Japan-Germany atomic energy seminar), the present state and subjects of the monitoring technology in BWR plants, the present state and subjects of the monitoring technology in PWR plants, and the present state and the subjects for hereafter of the defect evaluation method in the equipment of light water reactors. The data on the ultrasonic flaw detection in aluminum alloy welded joints were obtained. The German inspection technology is similar to that in Japan and other countries. The research on the plant synthetic monitoring and diagnosis system is reported. The monitoring systems for abnormal state in operation, troubles and the secular change of equipment are reported. The evaluation of the flaws in nuclear piping is reported. The summaries of the lectures are collected in this book. (K.I.)

Light transmission and air used for inspection of glovebox gloves

International Nuclear Information System (INIS)

Castro, Julio M.; Steckle, Warren P. Jr.; Macdonald, John M.

2002-01-01

Various materials used for manufacturing the glovebox gloves are translucent material such as hypalon, rubbers, and neoprene. This means that visible light can be transmitted through the inside of the material. Performing this test can help to increase visualization of the integrity of the glove. Certain flaws such as pockmarks, foreign material, pinholes, and scratches could be detected with increased accuracy. An analysis was conducted of the glovebox gloves obscure polymer material using a inspection light table. The fixture is equipped with a central light supply and small air pump to inflate the glove and test for leak and stability. A glove is affixed to the fixture for 360-degree inspection. Certain inspection processes can be performed: (1) Inspection for pockmarks and thin areas within the gloves; (2) Observation of foreign material within the polymer matrix; and (3) Measurements could be taken for gloves thickness using light measurements. This process could help reduce eyestrain when examining gloves and making a judgment call on the size of material thickness in some critical areas. Critical areas are fingertips and crotch of fingers.

The use of NPAR [Nuclear Plant Aging Research] results in plant inspection activities

International Nuclear Information System (INIS)

Gunther, W.; Taylor, J.

1989-01-01

The Nuclear Plant Aging Research (NPAR) Program is a hardware oriented research program which has produced a large data base of equipment and system operating, maintenance, and testing information. A review of the NRC Inspection Program and discussions with NRC inspection personnel have revealed several areas where NPAR research results would be valuable to the inspector. This paper describes the NPAR information which can enhance inspection activities, and provides alternatives for making these pertinent research results available to the inspectors. The NRC Inspection Program emphasis is on evaluating the performance of licensees by focusing on requirements and standards associated with administrative, managerial, engineering, and operational aspects of licensee activities. The Program recognizes that licensees may satisfy NRC requirements differently, and therefore expresses inspection guidance in the form of performance objectives and evaluation criteria. for the resident and regional inspectors, procedures have been written covering various subject areas, such as operations, maintenance, and surveillance. Some of these procedures contain guidance related to aging degradation. The types of information generated by NPAR which were found to be relevant to inspection needs include the following: functional indicators; failure modes, causes, effects; stresses which cause degradation; maintenance recommendations; inspection prioritization. 3 refs

Activities with regard to research and development of technics for SNR 300 reactor vessel in-service inspection procedures

International Nuclear Information System (INIS)

Hoeller, K.; Kirchner, G.; Menck, J.

1980-01-01

During the development of SNR 300 in-service inspection equipment, several branches were tested by experiment. In this report special steps for testing of manipulation systems and additional engineering equipment for control systems, such as coupling fluid circuit or camera cooling system are considered more in detail

MINAC, portable high energy radiographic inspection system

International Nuclear Information System (INIS)

Lapides, M.E.; Schonberg, R.

1985-01-01

MINAC, a portable, high energy radiographic source (1) was recognized as a desired inspection device for nuclear generation plants during EPRI-sponsored studies of the late 1970s and rapidly transitioned from proof-of-principle (1978-1980) to field-proven hardware (1981-present date). The equipment has completed its second generation of configuration development (SHRINKAC), that has recently been used in the field for detection of pipe cracks. Important auxiliaries for image data processing and real-time, thick section radiography have been demonstrated in both laboratory and field situations. Finally, a 6 MeV accelerator alternate is in bench test. These significant developments have, and are expected to continue to upgrade the utility of radiographic inspection in power plant practice. This paper describes the development and experience with this modular system during the last three years

Visual beam tube inspection at the TRIGA reactor Vienna

International Nuclear Information System (INIS)

Boeck, H.; Musilek, A.; Villa, M.

2006-01-01

Of the four TRIGA beam tubes two have been visually inspected in 1985. Prior to the inspection the reactor was shut down for 3 weeks. The fuel elements around the beam tubes were removed. Stainless steel dummy elements were inserted in the fuel positions to shield the core radiation. The active part of the Fast Rabbit Tube was removed into the beam tube loading device and transferred to an interim storage: Front dose rate was ∼ 50 mSv/h. Generally the beam tube was very clean, after the last inspection about 30 years ago. A1 cm cut was observed at the beam tube front end. A rigid endoscope was used to check the beam tube's inner surface using a 90 degree deflection objective and photo- and video equipment. The direct dose rate in front of the beam tube was about 30 mSv/h. The beam tube was vacuum cleaned. A corroded shielding tank containing boric acid has leaked. A wooden collimator partially disintegrating due to extreme temperature was removed from beam tube D. Documentation of the inspection for visible defects is produced for later comparison

Inquiry about the uses of special equipment (CT equipment, angiography systems, mammography devices, screens)

International Nuclear Information System (INIS)

Schwager, P.; Stieve, F.E.

1986-01-01

There are at least 1100 special devices in medical establishment in Bavaria which require special inspection and surveillance with regard to quality of equipment and radiation protection. In addition, there are at least 53 tomographs available for operation, and at least 120 installed X-ray screens. These devices need special approval testing and quality control services as they contribute a very significant amount of the medically indicated radiation exposure of the population. Appropriate measures are explained that can be applied in order to reduce the medical radiation exposure to an optimum. (orig.) [de

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.)

INFIBRA: machine vision inspection of acrylic fiber production

Science.gov (United States)

Davies, Roger; Correia, Bento A. B.; Contreiras, Jose; Carvalho, Fernando D.

1998-10-01

This paper describes the implementation of INFIBRA, a machine vision system for the inspection of acrylic fiber production lines. The system was developed by INETI under a contract from Fisipe, Fibras Sinteticas de Portugal, S.A. At Fisipe there are ten production lines in continuous operation, each approximately 40 m in length. A team of operators used to perform periodic manual visual inspection of each line in conditions of high ambient temperature and humidity. It is not surprising that failures in the manual inspection process occurred with some frequency, with consequences that ranged from reduced fiber quality to production stoppages. The INFIBRA system architecture is a specialization of a generic, modular machine vision architecture based on a network of Personal Computers (PCs), each equipped with a low cost frame grabber. Each production line has a dedicated PC that performs automatic inspection, using specially designed metrology algorithms, via four video cameras located at key positions on the line. The cameras are mounted inside custom-built, hermetically sealed water-cooled housings to protect them from the unfriendly environment. The ten PCs, one for each production line, communicate with a central PC via a standard Ethernet connection. The operator controls all aspects of the inspection process, from configuration through to handling alarms, via a simple graphical interface on the central PC. At any time the operator can also view on the central PC's screen the live image from any one of the 40 cameras employed by the system.

UAV Low Altitude Photogrammetry for Power Line Inspection

Directory of Open Access Journals (Sweden)

Yong Zhang

2017-01-01

Full Text Available When the distance between an obstacle and a power line is less than the discharge distance, a discharge arc can be generated, resulting in the interruption of power supplies. Therefore, regular safety inspections are necessary to ensure the safe operation of power grids. Tall vegetation and buildings are the key factors threatening the safe operation of extra high voltage transmission lines within a power line corridor. Manual or laser intensity direction and ranging (LiDAR based inspections are time consuming and expensive. To make safety inspections more efficient and flexible, a low-altitude unmanned aerial vehicle (UAV remote-sensing platform, equipped with an optical digital camera, was used to inspect power line corridors. We propose a semi-patch matching algorithm based on epipolar constraints, using both the correlation coefficient (CC and the shape of its curve to extract three dimensional (3D point clouds for a power line corridor. We use a stereo image pair from inter-strip to improve power line measurement accuracy by transforming the power line direction to an approximately perpendicular to epipolar line. The distance between the power lines and the 3D point cloud is taken as a criterion for locating obstacles within the power line corridor automatically. Experimental results show that our proposed method is a reliable, cost effective, and applicable way for practical power line inspection and can locate obstacles within the power line corridor with accuracy better than ±0.5 m.

Development of FBR visual inspection technique in sodium

International Nuclear Information System (INIS)

Suzuki, T.; Nagai, S.; Shioyama, T.; Sato, M.; Karasawa, H.; Maruyama, F.; Ota, S.; Hida, T.; Kai, M.

1995-01-01

Because the reactor vessel of Fast Breeder Reactor is filled with opaque liquid sodium, it is expected to develop an acoustic visual inspection technique in sodium. The acoustic 3 dimensional image processing technique and the elemental parts of the visual inspection equipment in sodium have been developed at the first stage of the in-sodium visual inspection technique development. The cross correlation processing has been applied to improve the S/N ratio in the acoustic echo that are deteriorated by wetting in sodium and the low sensitivity that are also deteriorated by rather smaller diameter to integrate the high density multiple acoustic sensors. The improvement of S/N ratio has been realized by the cross correlation between acoustic echo data that is reflected from the objects and M-series continuous wave that is transmitted from the acoustic transducer. The high speed parallel processing circuits, in which DSPs (Digital Signal Processors) are included, have been developed to realize high speed processing by employing (the circuits connected to) each of sensors in parallel. Synthetic Aperture Focussing Technique (SAFT) has been applied to the acoustic 3-dimensional image processing. The amounts of ellipsoids must be drawn into the 3-dimensional memory to compose the 3-dimensional image by SAFT. Then, a high performance work-station has been employed to deal with enormous data to compose the acoustic 3 dimensional image. Motors and cables, which can be operated under the condition of high-temperature and high-radiation environment, have been developed as the parts of the manipulator which will be used for visual inspection equipment in sodium. A prototype drive mechanism consists of the manipulator with three joints and a scanner with an arrayed acoustic sensors which a sweeps in fan-shape mechanically. The manipulatory type prototype drive mechanism and the signal processing device have been developed and tested, and the acoustic 3-dimensional image of pyramid

46 CFR 199.45 - Tests and inspections of lifesaving equipment and arrangements.

Science.gov (United States)

2010-10-01

... such as lifebuoys, lifejackets, immersion suits, work vests, lifefloats, buoyant apparatus, and..., immersion suits, work vests, lifefloats, buoyant apparatus, and associated equipment; (4) The proper...

Guide for the evaluation of physical protection equipment. Book 2: Volumes IV--VIII

International Nuclear Information System (INIS)

Haberman, W.

1977-06-01

A guide for evaluating the performance of commercially available physical protection equipment has been prepared for use by U.S. NRC. Separate evaluation procedures are provided for each generic type of equipment contained in the companion document, Catalog of Physical Protection Equipment (NUREG-0274). Among the equipment parameters evaluated are sensitivity, area/volume of coverage, false/nuisance alarm rate, resistance to countermeasures, environmental requirements, installation parameters and maintenance. Four evaluation techniques are employed (inspections, analyses, demonstrations and tests); standard test equipment (both commercially available as well as developmental) to be used in the evaluation is listed. The following categories of equipment are covered: surveillance and alarm assessment components, contraband detection components, automated response components, general purpose display components, and general purpose communication components

Seismic verification of nuclear plant equipment anchorage

International Nuclear Information System (INIS)

Lepiece, M.; Van Vyve, J.

1991-01-01

More than 60% of the electrical power of Belgium is generated by seven PWR nuclear power plants. For three of them, the electro-mechanical equipment had to be reassessed after ten years of operation, because the seismic requirements were upgraded from 0.1 g to 0.17 g free field ground acceleration. The seismic requalification of the active equipment was a critical problem as the classical methods were too conservative. The approach based on the use of the past experience on the seismic behavior of nonnuclear equipment, chosen and developed by the SQUG, had to be transposed to the Belgian N.P.P. The decision of the accept-ability of equipment relies heavily on the aseismatic capacity of anchorage. The Electrical Power Research Institute (EPRI) developed the procedure and guideline for the demonstration of the aseismatic adequacy of equipment anchorage in a cost-effective and consistent manner, to support the decision by Seismic Review Team. The field inspection procedure to identify the type of fasteners and detect their possible defects and the verification procedure developed to calculate the aseismatic capacity of equipment anchorage on the strength of fasteners, the aseismatic capacity of anchorage and the comparison of the capacity with the demand are reported. (K.I.)

Guide for the evaluation of physical protection equipment. Book 1: Volumes I--III

International Nuclear Information System (INIS)

Haberman, W.

1977-06-01

A guide for evaluating the performance of commercially available physical protection equipment has been prepared in partial fulfillment of Task 2 of MITRE contract AT(49-24)-0376 for use by the U.S. Nuclear Regulatory Commission (NRC). Separate evaluation procedures are provided for each generic type of equipment contained in the companion document, Catalog of Physical Protection Equipment. Among the equipment parameters evaluated, as appropriate, are sensitivity, area/volume of coverage, false/nuisance alarm rate, resistance to countermeasures, environmental requirements, installation parameters and maintenance. Four evaluation techniques are employed (inspections, analyses, demonstrations and tests); standard test equipment (both commercially available as well as developmental) to be used in the evaluation are listed

9 CFR 381.201 - Means of conveyance and equipment used in handling poultry products offered for entry to be...

Science.gov (United States)

2010-01-01

... INSPECTION AND CERTIFICATION POULTRY PRODUCTS INSPECTION REGULATIONS Imported Poultry Products § 381.201... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Means of conveyance and equipment used in handling poultry products offered for entry to be maintained in sanitary condition. 381.201...

EPERC: The European Pressure Equipment Research Council

International Nuclear Information System (INIS)

Darlaston, J.; McAllister, S.

1998-01-01

The European Pressure Equipment Research Council (EPERC) is a European Network of industries, research laboratories, inspection bodies and governmental institutions set up to foster co-operative research for the greater benefit of the European industry. The concept of a European Research Council originated at the PVRC meeting in Cannes in 1989 and since this time volunteers from the industry, research laboratories and of the European Commission Joint Research Centre, Petten have worked together to create a Statute for EPERC. In the context of the pressure equipment industry, the creation of EPERC is extremely pertinent, since in the near future, a Council directive on pressure equipment will replace the existing national regulations. In parallel to this, work is in progress for the elaboration of European Standards. It is useful to recall that ''Harmonised Standards'' will be the privileged means of complying with the Essential Safety Requirements of the directive. (author)

Development of automatic Ultrasonic testing equipment for reactor pressure vessel

International Nuclear Information System (INIS)

Kim, Kor R.; Kim, Jae H.; Lee, Jae C.

1996-06-01

The selected weld areas of a reactor pressure vessel and adjacent piping are examined by the remote mechanized ultrasonic testing (MUT) equipment. Since the MUT equipment was purchased from southwest Research Institute (SwRI) in April 1985, 15 inservice inspections and 5 preservice inspections are performed with this MUT equipment. However due to the old age of the equipment and frequent movements to plant sites, the reliability of examination was recently decreased rapidly and it is very difficult to keep spare parts. In order to resolve these problems and to meet the strong request from plant sites, we intend to develop a new 3-axis control system including hardware and software. With this control system, we expect more efficient and reliable examination of the nozzle to shell weld areas, which is specified in ASME Code Section XI. The new 3-axis control system hardware and software were designed and development of our own control system, the advanced technologies of computer control mechanism were established and examination reliability of the nozzle to shell weld area was improved. With the development of our 3-axis control system for PaR ISI-2 computer control system, the reliability of nozzle to shell weld area examination has been improved. The established technologies from the development and detailed analysis of existing control system, are expected to be applied to the similar control systems in nuclear power plants. (author). 12 refs., 4 tabs., 33 figs

Development of automatic Ultrasonic testing equipment for reactor pressure vessel

Energy Technology Data Exchange (ETDEWEB)

Kim, Kor R.; Kim, Jae H.; Lee, Jae C.

1996-06-01

The selected weld areas of a reactor pressure vessel and adjacent piping are examined by the remote mechanized ultrasonic testing (MUT) equipment. Since the MUT equipment was purchased from southwest Research Institute (SwRI) in April 1985, 15 inservice inspections and 5 preservice inspections are performed with this MUT equipment. However due to the old age of the equipment and frequent movements to plant sites, the reliability of examination was recently decreased rapidly and it is very difficult to keep spare parts. In order to resolve these problems and to meet the strong request from plant sites, we intend to develop a new 3-axis control system including hardware and software. With this control system, we expect more efficient and reliable examination of the nozzle to shell weld areas, which is specified in ASME Code Section XI. The new 3-axis control system hardware and software were designed and development of our own control system, the advanced technologies of computer control mechanism were established and examination reliability of the nozzle to shell weld area was improved. With the development of our 3-axis control system for PaR ISI-2 computer control system, the reliability of nozzle to shell weld area examination has been improved. The established technologies from the development and detailed analysis of existing control system, are expected to be applied to the similar control systems in nuclear power plants. (author). 12 refs., 4 tabs., 33 figs.

Concrete pedestals for high-performance semiconductor production equipment

Science.gov (United States)

Vogen, Wayne; Franklin, Craig L.; Morneault, Joseph

1999-09-01

Concrete pedestals have many vibration and stiffness characteristics that make them a superior choice for sensitive semiconductor production equipment including scanners, scanning electron microscopes, focused ion beam millers and optical inspection equipment. Among the advantages of concrete pedestals are high inherent damping, monolithic construction that eliminates low stiffness joints common in steep pedestals, ability to reuse and ease of installation. Steel pedestals that have plates attached to the top of the frame are easily excited by acoustic excitation, especially in the range from 50 Hertz to 400 Hertz. Concrete pedestals do not suffer from this phenomenon because of the high mass and damping of the top surface.

Inspecting Sizewell B Class 1 and IoF components

International Nuclear Information System (INIS)

McNulty, T.

1990-01-01

Class 1 and ''incredibility of failure'' (IoF) pre-service inspections for Sizewell B cover steam generator and pressurizer welds and nozzles, welds on the emergency boration system, accumulators and reactor coolant loop, and the whole of the Class 1 piping. The contractor for this work has recently been selected. The scope of the work and the techniques and equipment to be used are outlined. (author)

7 CFR 54.1014 - Accessibility of equipment and utensils; access to establishments.

Science.gov (United States)

2010-01-01

...) AGRICULTURAL MARKETING SERVICE (Standards, Inspections, Marketing Practices), DEPARTMENT OF AGRICULTURE (CONTINUED) REGULATIONS AND STANDARDS UNDER THE AGRICULTURAL MARKETING ACT OF 1946 AND THE EGG PRODUCTS..., Processing, and Packaging of Livestock and Poultry Products § 54.1014 Accessibility of equipment and utensils...

Recommendations for managing equipment aging in nuclear power plants

International Nuclear Information System (INIS)

Gunther, W.E.; Subudhi, M.; Aggarwal, S.K.

1992-01-01

Research conducted under the auspices of the US NRC's Nuclear Plant Aging Research (NPAR) Program has resulted in a large database of component and system operating, maintenance, and testing information. This database has been used to determine the susceptibility to aging of selected components, and the potential for equipment aging to impact plant safety and availability. it has also identified methods for detecting and mitigating component and system aging. This paper describes the research recommendations on electrical components which could be applied to maintenance, testing, and inspection activities to detect and mitigate the effects of aging prior to equipment failures

Safety requirements and feedback of commonly used material handling equipment

International Nuclear Information System (INIS)

Pathak, M.K.

2009-01-01

Different types of cranes, hoists, chain pulley blocks are the most commonly used material handling equipment in industry along with attachments like chains, wire rope slings, d-shackles, etc. These equipment are used at work for transferring loads from one place to another and attachments are used for anchoring, fixing or supporting the load. Selection of the correct equipment, identification of the equipment planning of material handling operation, examination/testing of the equipment, education and training of the persons engaged in operation of the material handling equipment can reduce the risks to safety of people in workplace. Different safety systems like boom angle indicator, overload tripping device, limit switches, etc. should be available in the cranes for their safe use. Safety requirement for safe operation of material handling equipment with emphasis on different cranes and attachments particularly wire rope slings and chain slings have been brought out in this paper. An attempt has also been made to bring out common nature of deficiencies observed during regulatory inspection carried out by AERB. (author)

Development of support system for maintenance and administration of reprocessing plant equipment

International Nuclear Information System (INIS)

Iwasaki, Syogo; Taniguchi, Takayuki; Shiraishi, Yoshihiko; Isaka, Kazuo

1998-01-01

Each year, maintenance work is carried out for about 10,000 pieces of equipment, including mechanical devices, electric equipment and instruments, at the Tokai Reprocessing Plant. Ninety percent of such maintenance work is preventive maintenance. In order to manage the information about the maintenance work, a computer support system was developed between 1985 and 1992. Twenty-seven thousand pieces of equipment and 180,000 maintenance histories have already been registered in the system. The system has been used for planning inspections and replacement of equipment as well as checking their maintenance histories. Actual usage of the system has shown that some auxiliary functions need to be added. The system will therefore be improved and extended. (author)

Automated in-core image generation from video to aid visual inspection of nuclear power plant cores

Energy Technology Data Exchange (ETDEWEB)

Murray, Paul, E-mail: paul.murray@strath.ac.uk [Department of Electronic and Electrical Engineering, University of Strathclyde, Technology and Innovation Centre, 99 George Street, Glasgow, G1 1RD (United Kingdom); West, Graeme; Marshall, Stephen; McArthur, Stephen [Dept. Electronic and Electrical Engineering, University of Strathclyde, Royal College Building, 204 George Street, Glasgow G1 1XW (United Kingdom)

2016-04-15

Highlights: • A method is presented which improves visual inspection of reactor cores. • Significant time savings are made to activities on the critical outage path. • New information is extracted from existing data sources without additional overhead. • Examples from industrial case studies across the UK fleet of AGR stations. - Abstract: Inspection and monitoring of key components of nuclear power plant reactors is an essential activity for understanding the current health of the power plant and ensuring that they continue to remain safe to operate. As the power plants age, and the components degrade from their initial start-of-life conditions, the requirement for more and more detailed inspection and monitoring information increases. Deployment of new monitoring and inspection equipment on existing operational plant is complex and expensive, as the effect of introducing new sensing and imaging equipment to the existing operational functions needs to be fully understood. Where existing sources of data can be leveraged, the need for new equipment development and installation can be offset by the development of advanced data processing techniques. This paper introduces a novel technique for creating full 360° panoramic images of the inside surface of fuel channels from in-core inspection footage. Through the development of this technique, a number of technical challenges associated with the constraints of using existing equipment have been addressed. These include: the inability to calibrate the camera specifically for image stitching; dealing with additional data not relevant to the panorama construction; dealing with noisy images; and generalising the approach to work with two different capture devices deployed at seven different Advanced Gas Cooled Reactor nuclear power plants. The resulting data processing system is currently under formal assessment with a view to replacing the existing manual assembly of in-core defect montages. Deployment of the

Safeguards techniques and equipment. 2003 ed

International Nuclear Information System (INIS)

2003-01-01

The 1990s saw significant non-proliferation related developments in the world, resulting in a new period of safeguards development. Over several years an assessment was made of how to strengthen the effectiveness and improve the efficiency of IAEA safeguards. In May 1997 this culminated in the adoption by the IAEA Board of Governors of a Protocol Additional to Safeguards Agreements which significantly broadens the role of IAEA safeguards. As a consequence, the IAEA safeguards system entered a new era. In 1997 the IAEA began to publish a new series of booklets on safeguards, called the International Nuclear Verification Series (NVS). The objective of these booklets was to help in explaining IAEA safeguards, especially the new developments in safeguards, particularly for facility operators and government officers involved with these topics. The current booklet, which is a revision and update of IAEA/NVS/1, is intended to give a full and balanced description of the techniques and equipment used for both nuclear material accountancy and containment and surveillance measures, and for the new safeguards measure of environmental sampling. A completely new section on data security has been added to describe the specific features that are included in installed equipment systems in order to ensure the authenticity and confidentiality of information. As new verification measures continue to be developed the material in this booklet will be periodically reviewed and updated versions issued. The basic verification measure used by the IAEA is nuclear material accountancy. In applying nuclear material accountancy, IAEA safeguards inspectors make independent measurements to verify quantitatively the amount of nuclear material presented in the State's accounts. For this purpose, inspectors count items (e.g. fuel assemblies, bundles or rods, or containers of powdered compounds of uranium or plutonium) and measure attributes of these items during their inspections using non

A computerised automatic pellet inspection unit for FBTR fuel

International Nuclear Information System (INIS)

Ramakumar, M.S.; Mahule, K.N.; Ghosh, J.K.; Venkatesh, D.

1984-01-01

Physical inspection and certification of nuclear reactor fuel element components is an activity demanding utmost imagination and skill in devising accurate measuring systems. There is also need for remote handling, automation, rapid processing and inspection data print out when dealing with reactor fuel material. This report deals with an automatic computerised fuel pellet inspection system that has been developed in Radiometallurgy Division, B.A.R.C. to carry out dimensional and weight measurements on fuel pellets for the Fast Breeder Test Reactor (FBTR) at Kalpakkam near Madras. The system consists of several subsystems each developed especially for a specific purpose and as such items are not available off the shelf from manufacturers in India. If a general approach is adopted towards the report, there are many innovations and ideas that can be used in the automatic inspection of a variety of products in industry. As the system is fairly involved the report does not attempt to deal with detailed description of the equipment. The function of the system is to accept a certain quantity of fuel pellets in a bowl feeder, separate the pellets rejected owing to their exceeding dimensional and weight limits and form columns of accepted pellets. Dimensional and weight limits can be set as required and all inspection data are presented in a printed format. The system processes pellets at the rate of 15 per minute. The entire system can be run by operators with no special skills. The unit is currently in use for the inspection of mixed carbide fuel pellets for FBTR. (author)

Risk based inspection experience from the European chemical- and petrochemical industries

International Nuclear Information System (INIS)

Kristensen, Hans; Jeppesen, Leif; Larsen, Bjarne; Kim, Na Yon

2001-01-01

As an inspection vendor with 60 years of experience and with more than 25 years of experience as manufacturer of the Automated Ultrasonic NDT systems, the P-scan systems, FORCE Institute is continuously analysing the market for NDT. This is done to assure that both the equipment product line and the service mix provided by FORCE Institute are meeting the requirements from the industry today and in the future. The concept of Risk Based Inspection Programmes were adopted early by the offshore industry and has in the recent years been adopted by many other industries as a reliable and cost efficient way of maintaining a production facility. A Risk/Reliability Based Inspection Programme is a 'living organism' that constantly needs information if it shall be of any value and NDT information is only one type of information that is required. The NDT information required is normally related to corrosion/base material information and weld integrity information. NDT as an integrated part of a plants maintenance system is, in Europe, currently influenced by the following tendencies which all are related to 'Risk Based Inspection': · Increased use of Base-Line Inspections · Reduction in the use of repeated inspections(qualitative- instead of quantitative Inspections). · Inspection results are fed directly into the plant maintenance system. · Fitness-for-Purpose acceptance criteria instead of conventional acceptance criteria. As repeatability and accuracy is a key issue for the data, automated ultrasonic inspection is increasingly used as an alternative to manual ultrasonic inspection, but due to the physical size of most automated ultrasonic inspection systems the gain in productivity has not been as significant as the gain in repeatability and accuracy. In this paper some of FORCE Institute's practical experiences with examinations carried out in connection with Risk Based Inspection is used to illustrate the above described tendencies. Not only examples using automated

Eddy current inspection of stationary blade rings

International Nuclear Information System (INIS)

Krzywosz, K.J.; Hastings, S.N.

1994-01-01

Stationary turbine blade rings in a US power plant have experienced chloride-induced cracking. Failure analysis determined two types of cracking mechanisms: corrosion fatigue cracking confined to the leading edge of the outer shroud; and stress corrosion cracking present all over the blade surface. Fluorescent dye penetrant is typically used to detect and size cracks. However, it requires cleaning the blade rings by sandblasting to obtain reliable inspection results. Sand blasting in turn requires sealing the lower half of the turbine housing to prevent sand from contaminating the rest of the power plant components. Furthermore, both the penetrant examination and the removal of the sand are time consuming and costly. An alternative NDE technique is desirable which requires no pre-cleaning of the blade and a quick go/no-go inspection with the capability of estimating the crack length. This paper presents an innovative eddy current technique which meets the desired objectives by incorporating the use of specially designed contoured scanners equipped with an array of pancake coils. A set of eddy current pancake coils housed in three different scanners is used to manually scan and inspect the convex side of the stationary blade rings. The pancake coils are operated in a transmit/receive mode using two separate eddy current instruments. This paper presents the inspection concept, including scanner and probe designs, and test results from the various stages of multiple blade rings

Periodical in-service inspection as part of individual program of quality assurance of steam generators and pressurizers of WWER 440 nuclear power plant

International Nuclear Information System (INIS)

Kawalec, M.

1982-01-01

The manufacturers of equipment for nuclear power plants in the Czechoslovak Socialist Republic are obligated to process so-called individual programs of quality assurance in order to secure the quality of selected equipment in nuclear power. These programmes should include the evaluation of the design of the individual equipments with regard to the implementation of in-service inspection. The main problems are discussed related to the processing of the program of quality assurance for the steam generator and pressurizer. To solve these problems it is necessary that the general project designer should make a classification of the components according to safety categories and that the manufacturers should determine the weak points of the design on the basis of an analysis of the design of individual component nodes. On the basis of such an analysis it is then necessary to evaluate the existing design of the scale of in-service inspections and to decide whether or not new inspection methods should be added. (Z.M.)

Remote handling equipment design for the HEDL fuel supply program

International Nuclear Information System (INIS)

Metcalf, I.L.

1984-09-01

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

Validation of Sizewell ''B'' ultrasonic inspections -- Messages for performance demonstration

International Nuclear Information System (INIS)

Conroy, P.J.; Leyland, K.S.; Waites, C.

1994-01-01

At the time that the decisions leading to the construction of the Sizewell ''B'' plant were being made, public concern over the potential hazards of nuclear power was increasing. This concern was heightened by the accident at USA's Three Mile Island plant. The result of this and public pressure was that an extensive public inquiry was held in addition to the UK's normal licensing process. Part of the evidence to the inquiry supporting the safety case relied upon the ability of ultrasonic inspections to demonstrate that the Reactor Pressure Vessel (RPV) and other key components were free from defects that could threaten structural integrity. Evidence from a variety of trials designed to investigate the performance capability of ultrasonic inspection revealed that although ultrasonic inspection had the potential to satisfy this requirement its performance in practice was heavily dependent upon the details of application. It was therefore generally recognized that some form of inspection validation was required to provide assurance that the equipment, procedures and operators to be employed were adequate for purpose. The concept of inspection validation was therefore included in the safety case for the licensing of Sizewell ''B''. The UK validation trials covering the ultrasonic inspections of the Sizewell ''B'' PWR Reactor Pressure Vessel are now nearing completion. This paper summarizes the results of the RPV validations and considers some of the implications for ASME 11 Appendix 8 the US code covering performance demonstration

Inspection planning

International Nuclear Information System (INIS)

Korosec, D.; Levstek, M.F.

2001-01-01

Slovenian Nuclear Safety Administration (SNSA) division of nuclear and radiological safety inspection has developed systematic approach to their inspections. To be efficient in their efforts regarding regular and other types of inspections, in past years, the inspection plan has been developed. It is yearly based and organized on a such systematic way, that all areas of nuclear safety important activities of the licensee are covered. The inspection plan assures appropriate preparation for conducting the inspections, allows the overview of the progress regarding the areas to be covered during the year. Depending on the licensee activities and nature of facility (nuclear power plant, research reactor, radioactive waste storage, others), the plan has different levels of intensity of inspections and also their frequency. One of the basic approaches of the plan is to cover all nuclear and radiological important activities on such way, that all regulatory requests are fulfilled. In addition, the inspection plan is a good tool to improve inspection effectiveness based on previous experience and allows to have the oversight of the current status of fulfillment of planned inspections. Future improvement of the plan is necessary in the light of newest achievements on this field in the nuclear world, that means, new types of inspections are planned and will be incorporated into plan in next year.(author)

Availability and cost functions for periodically inspected preventively maintained units

International Nuclear Information System (INIS)

Vaurio, J.K.

1999-01-01

Unavailability and cost rate functions are developed for components whose failures can occur randomly but they are detected only by periodic testing or inspections. If a failure occurs between consecutive inspections, the unit remains failed until the next inspection. Components are renewed by preventive maintenance periodically, or by repair or replacement after a failure, whichever occurs first (age-replacement). The model takes into account finite repair and maintenance durations as well as costs due to testing, repair, maintenance and lost production or accidents. For normally operating units the time-related penalty is loss of production. For standby safety equipment it is the expected cost of an accident that can happen when the component is down due to a dormant failure, repair or maintenance. The objective of maintenance optimization is to minimize the total cost rate by proper selection of two intervals, one for inspections and one for replacements. General conditions and techniques are developed for solving optimal test and maintenance intervals, with and without constraints on the production loss or accident rate. Insights are gained into how the optimal intervals depend on various cost parameters and reliability characteristics

Long-term preventive maintenance of instrumentation control equipment for PWR plants

International Nuclear Information System (INIS)

Sugitani, S.; Nanba, M.

2006-01-01

Since the PWR plants in Japan have been operated more than 30 years, main instrumentation control equipment of analog systems has been renewed to digital control systems. Renewal works had to be done in short period within periodical inspection term and for several facilities. The Mitsubishi LTD group had been provided with these market needs by its digital control system (MELTAC-NplusR 3) applicable to main instrumentation control equipment for primary and secondary systems and had already finished the renewal for practical plants. (T. Tanaka)

Research on the Application of Risk-based Inspection for the Boiler System in Power Plant

Science.gov (United States)

Li, Henan

2017-12-01

Power plant boiler is one of the three main equipment of coal-fired power plants, is very tall to the requirement of the safe and stable operation, in a significant role in the whole system of thermal power generation, a risk-based inspection is a kind of pursuit of security and economy of unified system management idea and method, can effectively evaluate equipment risk and reduce the operational cost.

LESSONS LEARNED IN TESTING OF SAFEGUARDS EQUIPMENT

International Nuclear Information System (INIS)

Pepper, S.; Farnitano, M.; Carelli, J.; Hazeltine, J.; Bailey, D.

2001-01-01

The International Atomic Energy Agency's (IAEA) Department of Safeguards uses complex instrumentation for the application of safeguards at nuclear facilities around the world. Often, this equipment is developed through cooperation with member state support programs because the Agency's requirements are unique and are not met by commercially available equipment. Before approving an instrument or system for routine inspection use, the IAEA subjects it to a series of tests designed to evaluate its reliability. In 2000, the IAEA began to observe operational failures in digital surveillance systems. In response to the observed failures, the IAEA worked with the equipment designer and manufacturer to determine the cause of failure. An action plan was developed to correct the performance issues and further test the systems to make sure that additional operational issues would not surface later. This paper addresses the steps taken to address operation issues related to digital image surveillance systems and the lessons learned during this process

Methodology For Reduction Of Sampling On The Visual Inspection Of Developed And Etched Wafers

Science.gov (United States)

van de Ven, Jamie S.; Khorasani, Fred

1989-07-01

There is a lot of inspection in the manufacturing of semiconductor devices. Generally, the more important a manufacturing step, the higher is the level of inspection. In some cases 100% of the wafers are inspected after certain steps. Inspection is a non-value added and expensive activity. It requires an army of "inspectors," often times expensive equipment and becomes a "bottle neck" when the level of inspection is high. Although inspection helps identify quality problems, it hurts productivity. The new management, quality and productivity philosophies recommend against over inspection. [Point #3 in Dr. Deming's 14 Points for Management (1)] 100% inspection is quite unnecessary . Often the nature of a process allows us to reduce inspection drastically and still maintain a high level of confidence in quality. In section 2, we discuss such situations and show that some elementary probability theory allows us to determine sample sizes and measure the chances of catching a bad "lot" and accepting a good lot. In section 3, we provide an example and application of the theory, and make a few comments on money and time saved because of this work. Finally, in section 4, we draw some conclusions about the new quality and productivity philosophies and how applied statisticians and engineers should study every situation individually and avoid blindly using methods and tables given in books.

Prediction of Maintenance Period of Equipment Through Risk Assessment of Thermal Power Plants

Energy Technology Data Exchange (ETDEWEB)

Song, Gee Wook; Kim, Bum Shin; Choi, Woo Song; Park, Myung Soo [KEPCO Research Institute, Daejeon (Korea, Republic of)

2013-10-15

Risk-based inspection (RBI) is a well-known method that is used to optimize inspection activities based on risk analysis in order to identify the high-risk components of major facilities such as power plants. RBI, when implemented and maintained properly, improves plant reliability and safety while reducing unplanned outages and repair costs. Risk is given by the product of the probability of failure (Pof) and the consequence of failure (COF). A semi-quantitative method is generally used for risk assessment. Semi-quantitative risk assessment complements the low accuracy of qualitative risk assessment and the high expense and long calculation time of quantitative risk assessment. The first step of RB I is to identify important failure modes and causes in the equipment. Once these are defined, the Pof and COF can be assessed for each failure. During Pof and COF assessment, an effective inspection method and range can be easily found. In this paper, the calculation of the Pof is improved for accurate risk assessment. A modified semi-quantitative risk assessment was carried out for boiler facilities of thermal power plants, and the next maintenance schedules for the equipment were decided.

Prediction of Maintenance Period of Equipment Through Risk Assessment of Thermal Power Plants

International Nuclear Information System (INIS)

Song, Gee Wook; Kim, Bum Shin; Choi, Woo Song; Park, Myung Soo

2013-01-01

Risk-based inspection (RBI) is a well-known method that is used to optimize inspection activities based on risk analysis in order to identify the high-risk components of major facilities such as power plants. RBI, when implemented and maintained properly, improves plant reliability and safety while reducing unplanned outages and repair costs. Risk is given by the product of the probability of failure (Pof) and the consequence of failure (COF). A semi-quantitative method is generally used for risk assessment. Semi-quantitative risk assessment complements the low accuracy of qualitative risk assessment and the high expense and long calculation time of quantitative risk assessment. The first step of RB I is to identify important failure modes and causes in the equipment. Once these are defined, the Pof and COF can be assessed for each failure. During Pof and COF assessment, an effective inspection method and range can be easily found. In this paper, the calculation of the Pof is improved for accurate risk assessment. A modified semi-quantitative risk assessment was carried out for boiler facilities of thermal power plants, and the next maintenance schedules for the equipment were decided

Corrosion Assessment by Using Risk-Based Inspection Method for Petrochemical Plant - Practical Experience

International Nuclear Information System (INIS)

Choi, Song Chun; Song, Ki Hun

2009-01-01

Corrosion assessment has a number of uses but the use considered here is as a precursor to Risk-Based Inspection (RBI) planning. Systematic methods consisting of technical modules of RBI program were used to assess the effect of specific corrosion mechanism on the probability of failure in equipment of petrochemical plants. Especially in part of the damage and corrosion assessment, screening step involved evaluating the combinations of process conditions and construction materials for each equipment item in order to determine which damage mechanisms are potentially active. For general internal corrosion, either API 510 or API 570 was applied as the damage rate in the calculation to determine the remaining life and inspection frequency. In some cases, a measured rate of corrosion may not be available. The technical modules of RBI program employ default values for corrosion, typically derived from published data or from experience with similar processes, for use until inspection results are available. This paper describes the case study of corrosion and damage assessment by using RBI methodology in petrochemical plant. Specifically, this paper reports the methodology and the results of its application to the petrochemical units using the KGS-RBI TM program, developed by the Korea Gas Safety Corporation to suit Korean situation in conformity with API 581 Codes

Evaluation of robotic inspection systems at nuclear power plants

International Nuclear Information System (INIS)

White, J.R.; Eversole, R.E.; Farnstrom, K.A.; Harvey, H.W.; Martin, H.L.

1984-03-01

This report presents and demonstrates a cost-effective approach for robotics application (CARA) to surveillance and inspection work in existing nuclear power plants. The CARA was developed by the Remote Technology Corporation to systematically determine the specific surveillance/inspection tasks, worker hazards, and access or equipment placement restraints in each of the many individual rooms or areas at a power plant. Guidelines for designing inspection robotics are included and are based upon the modular arrangement of commercially-available sensors and other components. Techniques for maximizing the cost effectiveness of robotics are emphasized in the report including: selection of low-cost robotic components, minimal installation work in plant areas, portable systems for common use in different areas, and standardized robotic modules. Factors considered as benefits are reduced radiation exposure, lower man-hours, shorter power outage, less waste material, and improved worker safety concerns. A partial demonstration of the CARA methodology to the Sequoyah (PWR) and Browns Ferry (BWR) Plants is provided in the report along with specific examples of robotic installations in high potential areas

Laser Safety Inspection Criteria

International Nuclear Information System (INIS)

Barat, K.

2005-01-01

A responsibility of the Laser Safety Officer (LSO) is to perform laser audits. The American National Standard Z136.1 Safe Use of Lasers references this requirement through several sections. One such reference is Section 1.3.2.8, Safety Features Audits, ''The LSO shall ensure that the safety features of the laser installation facilities and laser equipment are audited periodically to assure proper operation''. The composition, frequency and rigor of that inspection/audit rests in the hands of the LSO. A common practice for institutions is to develop laser audit checklists or survey forms It is common for audit findings from one inspector or inspection to the next to vary even when reviewing the same material. How often has one heard a comment, ''well this area has been inspected several times over the years and no one ever said this or that was a problem before''. A great number of audit items, and therefore findings, are subjective because they are based on the experience and interest of the auditor to particular items on the checklist. Beam block usage, to one set of eyes might be completely adequate, while to another, inadequate. In order to provide consistency, the Laser Safety Office of the National Ignition Facility Directorate has established criteria for a number of items found on the typical laser safety audit form. The criteria are distributed to laser users. It serves two broad purposes; first, it gives the user an expectation of what will be reviewed by an auditor. Second, it is an opportunity to explain audit items to the laser user and thus the reasons for some of these items, such as labelling of beam blocks

IAEA preparations for the year 2000 compliance of safeguards equipment systems

International Nuclear Information System (INIS)

Aparo, M.; Barnes, B.; Lewis, W.; Hsiung, Sue

1999-01-01

The Department of Safeguards, IAEA, has used equipment systems for acquiring relevant data to support safeguards evaluation and verification activities. Typically an equipment system consists of EPROM (embedded system), a connecting personal computer with instrument software for data acquisition, and may include data evaluation software. Complementing the equipment systems is a collection of general evaluation software systems (application software) which support the analysis of the acquired data. In preparing for the year 2000 compliance of all safeguards systems, SGTS (Safeguards Division of Technical Services) in IAEA, must ascertain the equipment systems and the evaluation software authorised for inspection use can properly operate through the passage of year 2000. We present the year 2000 challenge for these systems, the approach we use to tackle the problem, and the status of our year 2000 project. (author)

The construction of solid waste form test and inspection facility

International Nuclear Information System (INIS)

Park, Hun Hwee; Lee, Kang Moo; Jung, In Ha; Kim, Sung Hwan; Yoo, Jeong Woo; Lee, Jong Youl; Bae, Sang Min

1988-01-01

The solid waste form test and inspection facility is a facility to test and inspect the characteristics of waste forms, such as homogenity, mechanical structure, thermal behaviour, water resistance and leachability. Such kinds of characteristics in waste forms are required to meet a certain conditions for long-term storage or for final disposal of wastes. The facility will be used to evaluate safety for the disposal of wastes by test and inspection. At this moment, the efforts to search the most effective management of the radioactive wastes generated from power plants and radioisotope user are being executed by the people related to this field. Therefore, the facility becomes more significant tool because of its guidance of sucessfully converting wastes into forms to give a credit to the safety of waste disposal for managing the radioactive wastes. In addition the overall technical standards for inspecting of waste forms such as the standardized equipment and processes in the facility will be estabilished in the begining of 1990's when the project of waste management will be on the stream. Some of the items of the project have been standardized for the purpose of localization. In future, this facility will be utilized not only for the inspection of waste forms but also for the periodic decontamination apparatus by remote operation techniques. (Author)

Experience in the manufacture of nuclear equipment in India

International Nuclear Information System (INIS)

Challappa, S.; Murthy, G.S.K.; Mehta, S.K.; Kakodkar, A.; Natarajan, A.

1977-01-01

Department of Atomic Energy with its programme for achieving self-sufficiency was involved in engineering, manufacture, inspection, performance testing and quality surveillance of major precision and critical equipment such as reactor vessels, shields, fuelling machines, coolant channel components etc. etc. high pressure equipment for Heavy Water Plants, specialized components for Fuel Complex, major equipment for Cyclotron Project and various research projects. These had to be manufactured at various shops in the country depending upon the availability of machines. The relative importance of various important parameters associated with the manufacture of this equipment were assessed in a separate R and D programme. This has helped in re-designing in some areas to suit the manufacture under Indian conditions. Assessment of any marginal variations that take place during manufacture was also possible because of the availability of data of this kind. Critical components and equipment are tested for their performance under simulated conditions before shipments. B.A.R.C. has contributed immensely in achieving the self-sufficiency and also for designs for future plants

49 CFR Appendix C to Part 180 - Eddy Current Examination With Visual Inspection for DOT 3AL Cylinders Manufactured of Aluminum...

Science.gov (United States)

2010-10-01

... 49 Transportation 2 2010-10-01 2010-10-01 false Eddy Current Examination With Visual Inspection... PACKAGINGS Pt. 180, App. C Appendix C to Part 180—Eddy Current Examination With Visual Inspection for DOT 3AL... procedure applicable to the test equipment it uses to perform eddy current examinations. 2. Visual...

Quantitative Inspection of Remanence of Broken Wire Rope Based on Compressed Sensing.

Science.gov (United States)

Zhang, Juwei; Tan, Xiaojiang

2016-08-25

Most traditional strong magnetic inspection equipment has disadvantages such as big excitation devices, high weight, low detection precision, and inconvenient operation. This paper presents the design of a giant magneto-resistance (GMR) sensor array collection system. The remanence signal is collected to acquire two-dimensional magnetic flux leakage (MFL) data on the surface of wire ropes. Through the use of compressed sensing wavelet filtering (CSWF), the image expression of wire ropes MFL on the surface was obtained. Then this was taken as the input of the designed back propagation (BP) neural network to extract three kinds of MFL image geometry features and seven invariant moments of defect images. Good results were obtained. The experimental results show that nondestructive inspection through the use of remanence has higher accuracy and reliability compared with traditional inspection devices, along with smaller volume, lighter weight and higher precision.

Advanced inspection technology for non intrusive inspection (NII) program

International Nuclear Information System (INIS)

Zamir Mohamed Daud

2003-01-01

In the current economic environment, plants and facilities are under pressure to introduced cost saving as well as profit maximising measures. Among the many changes in the way things are run is a move towards Risk Based Inspection (RBI), with an emphasis on longer operating periods between shutdowns as well as to utilise components to their maximum capability. Underpinning and RBI program requires good data from an effective online inspections program, which would not require the shutdown of critical components. One methodology of online inspection is known as Non Intrusive Inspection (NII), an inspection philosophy with the objective of replacing internal inspection of a vessel by doing Non Destructive Testing (NDT) and inspections externally. To this end, a variety of advanced NDT techniques are needed to provide accurate online measurements. (Author)

Field size and centring for conventional X-ray equipment

International Nuclear Information System (INIS)

Klimpel, H.; Kreienfeld, H.; Overbeck, R.

1989-01-01

Since 1973, all X-ray equipment for medical applications in the Federal Republic of Germany has had to be examined according to the requirements of the German ''Rontgenverordnung'' before it is used on patients and after each essential modification of design or construction. These examinations are carried out by inspectors appointed by the authorities, e.g. TUV. The field size adjustment and the centring of the radiation beam in relation to the image reception area is checked, along with other tests. To increase quality assurance in X-ray diagnosis, since the mid-1980s X-ray equipment has also been subject to in-service inspections to an increasing extent. (author)

Medical equipment in government health facilities: missed opportunities.

Science.gov (United States)

Pardeshi, Geeta S

2005-01-01

The availability and optimal utilization of medical equipment is important for improving the quality of health services. Significant investments are made for the purchase, maintenance and repair of medical equipment. Inadequate management of these equipment will result in financial losses and deprive the public of the intended benefits. This analysis is based on the conceptual framework drawn from the WHO recommended- lifecycle of medical equipment. (1) To identify the problems in different stages of the life cycle. (2) To assess its financial implications and effect on service delivery. Analysis of secondary data from the latest Comptroller and Auditor General (CAG) Reports for the states in India. The study variables were category of equipment, financial implications and problems in the stages of life cycle. Calculation of proportions. A total of forty instances mentioning problems in the first phase of the life cycle of medical equipment were noted in 12 state reports. The equipment from the radiology department (15), equipment in the wards (5), laboratory (3) and operation theatres (4) were the ones most frequently implicated. In a majority of cases the financial implications amounted to twenty-five lakhs. The financial implications were in the form of extra expenditure, unfruitful expenditure or locking of funds. In 25 cases the equipment could not be put to use because of non-availability of trained staff and inadequate infrastructural support. Careful procurement, incoming inspection, successful installation and synchronization of qualified trained staff and infrastructural support will ensure timely onset of use of the equipment.

Inspections in veterinary medicine 2005; Veterinaerinspektioner 2005

Energy Technology Data Exchange (ETDEWEB)

Joensson, Helene

2006-11-15

In Sweden 300 veterinary clinics have a license for x-ray diagnostics. Six of them also have a license for nuclear medicine. During 2005 eight clinics were inspected and the results show that the radiation protection in veterinary medicine can be improved. No clinic fulfilled the regulations of categorization of workplaces and workers (SSI FS 1998:3). Half of the clinics had no Swedish manual to the x-ray equipment and just as many had not performed the annual function check. Obviously, there is a need for more information to staff in veterinary medicine.

A guide to radiation protection in the use of X-ray optics equipment

International Nuclear Information System (INIS)

Bines, W.P.

1986-01-01

A booklet has been produced by a Working Group convened by the Health and Safety Executive to provide practical guidance for all who might be involved in work with X-ray optics equipment, such as designers, manufacturers, users, maintenance workers, inspectors, radiation protection advisers and supervisors. The particular radiation protection aspects described include those in connection with enclosure design and inspection, inter locks, tube shields, shutters and cover plates, administrative controls, monitoring and repair and maintenance of equipment. (UK)

LHC train control system for autonomous inspections and measurements

OpenAIRE

Di Castro, Mario; Baiguera Tambutti, Maria Laura; Gilardoni, Simone; Losito, Roberto; Lunghi, Giacomo; Masi, Alessandro

2018-01-01

Intelligent robotic systems are becoming essential for inspection and measurements in harsh environments, such as the European Organization for Nuclear Research (CERN) accelerators complex. Aiming at increasing safety and machine availability, robots can help to perform repetitive or dangerous tasks, reducing the risk for the personnel as the exposure to radiation. The Large Hadron Collider (LHC) tunnel at CERN has been equipped with fail-safe trains on monorail able to perform autonomously d...

Application of risk-based methods for inspection of nuclear power plant components

International Nuclear Information System (INIS)

Balkey, K.R.

1992-01-01

In-service inspections (ISIs) can play a significant role in minimizing equipment and structural failures. All aspects of inspections, i.e., objectives, method, timing, and the acceptance criteria for detected flaws can affect the probability of component failure. Where ISI programs exist, they are primarily based on prior experience and engineering judgment. At best, some include an implicit consideration of risk (probability of failure multiplied by consequence). Since late 1988, a multidisciplined American Society of Mechanical Engineers (ASME) Research Task Force on Risk-Based Inspection Guidelines has been addressing the general question of how to formally incorporate risk considerations into plans and requirements for the ISI of components and structural systems. The task force and steering committee that guided the project have concluded that appropriate analytical methods exist for evaluating and quantifying risks associated with pressure boundary and structural failures. With the support of about a dozen industry and government organizations, the research group has recommended a general methodology for establishing a risk-based inspection program that could be applied to any nuclear system or structural system

Inspection experience with RA-3 spent nuclear fuel assemblies at CNEA's central storage facility

International Nuclear Information System (INIS)

Novara, Oscar; LaFuente, Jose; Large, Steve; Andes, Trent; Messick, Charles

2000-01-01

Aluminum-based spent nuclear fuel from Argentina's RA-3 research reactor is to be shipped to the Savannah River Site near Aiken, South Carolina, USA. The spent nuclear fuel contains highly enriched uranium of U.S. origin and is being returned under the US Department of Energy's Foreign Research Reactor/Domestic Research Reactor (FRR/DRR) Receipt Program. An intensive inspection of 207 stored fuel assemblies was conducted to assess shipping cask containment limitations and assembly handling considerations. The inspection was performed with video equipment designed for remote operation, high portability, easy setup and usage. Fuel assemblies were raised from their vertical storage tubes, inspected by remote video, and then returned to their original storage tube or transferred to an alternate location. The inspections were made with three simultaneous video systems, each with dedicated viewing, digital recording, and tele-operated control from a shielded location. All 207 fuel assemblies were safely and successfully inspected in fifteen working days. Total dose to personnel was about one-half of anticipated dose. (author)

Subaquatic, pressure vessels and LPG storage spheres internal inspection; Inspecao interna de esfera utilizando mergulho como acesso

Energy Technology Data Exchange (ETDEWEB)

Filgueira Filho, Rafael; Monteiro, Ayres [PETROBRAS, Rio de Janeiro, RJ (Brazil)

2005-07-01

Minimizing shut-down costs is a widespread target in the oil and gas industry. The use of new inspection techniques is one of the ways for that. This work presents a new procedure for internal inspections in pressure vessels by the non destructive testing - NDT, ACFM, using industrial diving techniques. As a pioneer experience, this method was applied in the inspection of the internal parts of the LPG sphere tank 5101 at PETROBRAS Transporte S.A. - TRANSPETRO, in Jequie's Terminal, in the state of Bahia, in december, 2003. This new method allows the reduction of indirect costs related to operational unavailability of the equipment, by the reduction of the shut-down time in approximately 50%, when compared to the demanded shut down time, when using scaffolds for accessing the internal parts. Despite of direct costs are still higher with the new methodology, this paper demonstrates the economical feasibility of this new method, based on the savings obtained with the fastest return of the equipment to operation. (author)

Calculation of frequency of optimal inspection in non-notice inspection game

International Nuclear Information System (INIS)

Kumakura, Shinichi; Gotoh, Yoshiki; Kikuchi, Masahiro

2011-01-01

We consider a non-notice inspection game between an inspection party, who verifies absence of diversion of nuclear materials and misuse of nuclear facility, and a facility operator, who tries them in a nuclear facility. In the game, the payoff for each player, inspection party and facility operator, is composed of various elements (parameters) such as facility type, a type of nuclear material, number of inspection and others. Their payoffs consist of profits and costs (minus profit). Because of random nature by non-notice inspection, its deterrence effect and inspection number could have the potential to affect their payoffs. In this paper, their payoffs taking into consideration of the inspection environment above are represented as a function of inspection number. Then, the optimal number is calculated from a condition on their payoffs for number of inspection. Comparable statics analysis is performed in order to observe the change of inspection number which is equilibrium point by changing these parameters including deterrence effect, because the number derived depends on each parameter within the inspection environment. Based on the analysis results, necessary conditions to reduce the inspection number keeping inspection effect are pointed out. (author)

Eddy current and ultrasonic fuel channel inspection at Karachi Nuclear Power Plant

International Nuclear Information System (INIS)

Mayo, W.R.; Alam, M.M.

1997-01-01

In November of 1993 and in-service inspection was performed on eight fuel channels in the Karachi Nuclear Power Plant (KANUPP) reactor. The workscope included ultrasonic and eddy current volumetric examinations, and eddy current measurement of pressure-to calandria tube gap. This paper briefly discusses the planning strategy of the ultrasonic and eddy current examinations, and describes the equipment developed to meet the requirements, followed by details of the actual channel inspection campaign. The presented nondestructive examinations assisted in determining fitness for service of KANUPP reactor channels in general, and confirmed that the problems associated with channel G12 were not generic in nature. (author)

POTENTIAL OF UAV-BASED LASER SCANNER AND MULTISPECTRAL CAMERA DATA IN BUILDING INSPECTION

Directory of Open Access Journals (Sweden)

D. Mader

2016-06-01

Full Text Available Conventional building inspection of bridges, dams or large constructions in general is rather time consuming and often cost expensive due to traffic closures and the need of special heavy vehicles such as under-bridge inspection units or other large lifting platforms. In consideration that, an unmanned aerial vehicle (UAV will be more reliable and efficient as well as less expensive and simpler to operate. The utilisation of UAVs as an assisting tool in building inspections is obviously. Furthermore, light-weight special sensors such as infrared and thermal cameras as well as laser scanner are available and predestined for usage on unmanned aircraft systems. Such a flexible low-cost system is realized in the ADFEX project with the goal of time-efficient object exploration, monitoring and damage detection. For this purpose, a fleet of UAVs, equipped with several sensors for navigation, obstacle avoidance and 3D object-data acquisition, has been developed and constructed. This contribution deals with the potential of UAV-based data in building inspection. Therefore, an overview of the ADFEX project, sensor specifications and requirements of building inspections in general are given. On the basis of results achieved in practical studies, the applicability and potential of the UAV system in building inspection will be presented and discussed.

The Management Advisory Committee of the Inspection Validation Centre seventh report

International Nuclear Information System (INIS)

1990-07-01

The Management Advisory Committee of the Inspection Validation Centre (IVC/MAC) was set up to review the policy, scope, procedure and operation of the Inspection Validation Centre (IVC), to supervise its operation and to advise and report to the United Kingdom Atomic Energy Authority (UKAEA) appropriately. The IVC was established at the UKAEA Risley Laboratory, to validate the procedures, personnel and equipment proposed by Nuclear Electric for use in the ultrasonic inspection at various stages of the fabrication, erection and operation of the Sizewell 'B' Pressurized Water Reactor (PWR) reactor pressure vessel (RPV) and such other components as are identified by the utility. It is operated by the UKAEA to work as an independent organisation under contract to Nuclear Electric, and results are reported to Nuclear Electric together with the conclusions of the Centre in relation to the validation of individual techniques. At the meetings of the IVC/MAC, the progress on the manufacture of the pressure vessel is also outlined by the PWR Project Director. The vessel has now undergone the final stress relief and post-hydro inspection and is due to be delivered to the Sizewell site before the end of 1990. (author)

Proceedings of the workshop for exchange of technology for CWC inspections

Energy Technology Data Exchange (ETDEWEB)

McGuire, R.R.

1993-04-01

With the signing of the Chemical Weapons Convention (CWC), the work of the Preparatory Commission in defining the modalities of on-site verification inspections will begin early in 1993. One of the methods for increasing the effectiveness of inspections is the collection of samples for chemical analysis. The CWC allows for this analysis to be performed either at the site of the inspection or in a dedicated off-site laboratory. The decision as to where samples are to be analyzed in any specific instance may involve a consideration of the threat, real or perceived, to the compromise of legitimate sensitive host-party information. The ability to perform efficient chemical analysis at the inspection site, where samples remain in joint (host-inspector) custody and the analytical procedures can be observed by the host, can alleviate much of the concern over possible loss of confidential information in both government and industry. This workshop was designed to encourage the exchange of information among participants with experience in the use of analytical equipment for on-site sample collection and analysis. Individual projects are processed separately for the databases.

Qualification of a digital radiographic equipment for thin weld inspection

International Nuclear Information System (INIS)

Boulanger, G.; Furlan, J.

1988-04-01

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

Quantitative Inspection of Remanence of Broken Wire Rope Based on Compressed Sensing

Science.gov (United States)

Zhang, Juwei; Tan, Xiaojiang

2016-01-01

Most traditional strong magnetic inspection equipment has disadvantages such as big excitation devices, high weight, low detection precision, and inconvenient operation. This paper presents the design of a giant magneto-resistance (GMR) sensor array collection system. The remanence signal is collected to acquire two-dimensional magnetic flux leakage (MFL) data on the surface of wire ropes. Through the use of compressed sensing wavelet filtering (CSWF), the image expression of wire ropes MFL on the surface was obtained. Then this was taken as the input of the designed back propagation (BP) neural network to extract three kinds of MFL image geometry features and seven invariant moments of defect images. Good results were obtained. The experimental results show that nondestructive inspection through the use of remanence has higher accuracy and reliability compared with traditional inspection devices, along with smaller volume, lighter weight and higher precision. PMID:27571077

Quantitative Inspection of Remanence of Broken Wire Rope Based on Compressed Sensing

Directory of Open Access Journals (Sweden)

Juwei Zhang

2016-08-01

Full Text Available Most traditional strong magnetic inspection equipment has disadvantages such as big excitation devices, high weight, low detection precision, and inconvenient operation. This paper presents the design of a giant magneto-resistance (GMR sensor array collection system. The remanence signal is collected to acquire two-dimensional magnetic flux leakage (MFL data on the surface of wire ropes. Through the use of compressed sensing wavelet filtering (CSWF, the image expression of wire ropes MFL on the surface was obtained. Then this was taken as the input of the designed back propagation (BP neural network to extract three kinds of MFL image geometry features and seven invariant moments of defect images. Good results were obtained. The experimental results show that nondestructive inspection through the use of remanence has higher accuracy and reliability compared with traditional inspection devices, along with smaller volume, lighter weight and higher precision.

10 CFR 34.31 - Inspection and maintenance of radiographic exposure devices, transport and storage containers...

Science.gov (United States)

2010-01-01

.... 34.31 Section 34.31 Energy NUCLEAR REGULATORY COMMISSION LICENSES FOR INDUSTRIAL RADIOGRAPHY AND RADIATION SAFETY REQUIREMENTS FOR INDUSTRIAL RADIOGRAPHIC OPERATIONS Equipment § 34.31 Inspection and... maintenance program must include procedures to assure that Type B packages are shipped and maintained in...

Ultrasonic inspection of nodular cast iron

International Nuclear Information System (INIS)

Hersh, S.; Zhang, Yingda

1990-01-01

On the basis of experimental results collected from several nodular cast iron (NCI) specimens, Amdata, Inc., has developed a tentative procedure for performing ultrasonic testing (UT) preservice inspection of NCI casks and qualifying personnel and equipment. The authors anticipate that this procedure will be a component in a comprehensive program to certify that casks are free from critical flaws prior to their introduction into service, with testing being performed on a production line basis by UT inspection personnel. The tentative procedure was applied to inspection of NCI block SGR-483-001 manufactured by Siempelkamp Giesserei GmbH and Co. of West Germany. This block is 59 by 39.5 by 13.8 inches and weighs 5.2 tons. Several indications were detected with the I/98, in accordance with the tentative procedure, and they were analyzed using two-dimensional synthetic aperture technique (Line-SAFT). When compared with conventional sizing methods that may confound the effects of beam spread with flaw size, Line-SAFT significantly improved sizing accuracy. SAFT is an electronic simulation of a lens and has the property of reducing the effect of beam spread on the resultant indication sizes. Although a higher-precision 3-D SAFT option was also available, it would necessitate data transfer to a separate VAX computer and lengthy calculations. As an alternative, Line-SAFT, a faster but less precise 2-D simplification, was implemented on the I/98 data acquisition system

Report of Radioisotope Inspection Technical Committee

International Nuclear Information System (INIS)

Otani, H.

1980-01-01

For the purpose of unifying the method of performance test for the routine management of the performance of RI equipments, the check-up of performance at the time of purchasing the equipments or research works, the Committee has continued the investigation on the method of performance test on RI equipments. Now, the definite plans have been decided regarding the method of performance test on radioisotope monitoring instruments and the measuring instruments for RI samples, therefore they are reported hereinafter. As for the radioisotope monitoring instruments, Curie meter, area monitor, water monitor, gas monitor and hand, foot and cloth monitor were taken up, and the items of inspection, the purposes, the testing methods, the expression of measured results and their evaluation were discussed. The accuracy of measurement of absolute radio-activity is important in Curie meter, the stability of continuous monitoring is important in general monitors, and the limit of measurement is important in the hand, foot and cloth monitor. As for the measuring instruments for radioactive materials, the efficiency of counting, linearity and stability were taken up as the items of performance test, and other matters to which attention should be paid were added. These were described, dividing into well type scintillation counter and liquid scintillation counter. (Kako, I.)

Strategy of Risk-Informed Inspection for Secondary Systems in NPPs

International Nuclear Information System (INIS)

Kim, So Young; Heo, Gyun Young

2012-01-01

Recently, unexpected accidents such as large-scale blackout have been occurred due to increasing demand of electricity. The unplanned trips have great influence over the economics although they rarely affect the safety of system. Because the cost for inspection and maintenance is limited, it is beneficial not only economically to take follow-up action in a timely manner to prevent plant trip but also in safety by protecting against the risk which is occurred from trip. In nuclear power plants (NPPs), the importance about risk-informed service such as inspection, maintenance and replacement is becoming on the rise. Risk-informed techniques such as in-service test, in-service inspection, design guide change and etc. are already used in nuclear field but these techniques are applied focusing on primary system for safety-related regulatory issues. It is needed to consider the optimization of inspection informed risk for entire plant including secondary system which is not applied enough. The study about risk-based inspection for boilers in thermal power field is in progress actively, but not for turbine cycle, which is similar with nuclear industry. Today, the most of inspections or tests for turbine cycle are time-based maintenance, being performed on time. It is required to perform condition-based maintenance by evaluating risk analyzing both of probability and consequence simultaneously about damage mechanisms that can be predicted by equipment or devices configuring the secondary system. Probability of failure (POF) is analyzed in terms of materials' ageing mechanisms, but consequence of failure (COF) should be evaluated in terms of thermohydraulic condition then it is needed to check power loss and period of maintenance. This paper is going to propose the idea to quantify the consequence of failure using the fault tree and simulation for secondary system, and propose quantitative risk-informed inspection by these approaches

Manual on quality assurance for installation and commissioning of instrumentation, control and electrical equipment in nuclear power plants

International Nuclear Information System (INIS)

1989-01-01

The present Manual on Quality Assurance (QA) for Installation and Commissioning of Instrumentation, Control and Electrical (ICE) Equipment of Nuclear Power Plants contains supporting material and illustrative examples for implementing basic requirements of the quality assurance programme in procurement, receiving, installation and commissioning of this equipment. The Manual on Quality Assurance for Installation and Commissioning of ICE Equipment is designed to supplement and be consistent with the Guidebook as well as with the IAEA Code and Safety Guides on Quality Assurance. It is intended for the use of managerial staff and QA personnel of nuclear power plant owners or the organizations respectively responsible for the legal, technical, administrative and financial aspects of a nuclear power plant. The information provided in the Manual will also be useful to the inspection staff of the regulatory organization in the planning and performance of regulatory inspections at nuclear power plants

Articulated inspection arm for ITER, a demonstration in the Tore Supra tokamak

Energy Technology Data Exchange (ETDEWEB)

Cordier, J.J.; Gargiulo, L.; Grisolia, C.; Samaille, F. [Association Euratom-CEA Cadarache, 13 - Saint-Paul-lez-Durance (France). Dept. de Recherches sur la Fusion Controlee; Friconneau, J.P.; Perrot, Y. [CEA Fontenay-aux-Roses, LIST Robotics and Interactive Systems Unit, 92 (France); Palmer, J.D. [Max-Planck-Institut fuer Plasmaphysik Boltzmannstr.2, Garching (Germany)

2003-07-01

The aim of this program is to demonstrate for ITER the feasibility of an in-vessel remote handling inspection using a long reach, limited payload carrier (1 to 10 kg) for penetration of the ITER chamber through the openings. This device is dedicated to close inspection of the Plasma Facing Components (PFC). An articulated demonstrator called articulated inspection arm (AIA) has been manufactured. A feasibility study of a full AIA operation in Tore Supra was performed, taking into account ITER reference requirements. A scale one demonstration of the AIA under ITER relevant condition is feasible on Tore Supra and would give significant improvement in research results for ITER remote Handling equipment. The test of the AIA demonstrator behaviour is foreseen in 2005 in real Tokamak conditions. The paper presents the full robot concept, the results of the first test campaign, the AIA new design and its integration on Tore Supra. Several potential uses of the AIA for the in vessel components inspection are being studied such as PFC visual inspection, water loop leak testing, laser ablation for wall detritiation and carbon dust and flakes removal are foreseen as utilities to be placed at the AIA head. These various systems are described in the paper.

Articulated inspection arm for ITER, a demonstration in the Tore Supra tokamak

International Nuclear Information System (INIS)

Cordier, J.J.; Gargiulo, L.; Grisolia, C.; Samaille, F.; Palmer, J.D.

2003-01-01

The aim of this program is to demonstrate for ITER the feasibility of an in-vessel remote handling inspection using a long reach, limited payload carrier (1 to 10 kg) for penetration of the ITER chamber through the openings. This device is dedicated to close inspection of the Plasma Facing Components (PFC). An articulated demonstrator called articulated inspection arm (AIA) has been manufactured. A feasibility study of a full AIA operation in Tore Supra was performed, taking into account ITER reference requirements. A scale one demonstration of the AIA under ITER relevant condition is feasible on Tore Supra and would give significant improvement in research results for ITER remote Handling equipment. The test of the AIA demonstrator behaviour is foreseen in 2005 in real Tokamak conditions. The paper presents the full robot concept, the results of the first test campaign, the AIA new design and its integration on Tore Supra. Several potential uses of the AIA for the in vessel components inspection are being studied such as PFC visual inspection, water loop leak testing, laser ablation for wall detritiation and carbon dust and flakes removal are foreseen as utilities to be placed at the AIA head. These various systems are described in the paper

Pathology Residents Comprise Inspection Team for a CAP Self-Inspection

Directory of Open Access Journals (Sweden)

Stacy G. Beal MD

2017-03-01

Full Text Available We report our experience at the University of Florida in which residents and fellows served as the inspection team for a College of American Pathologists (CAP self-inspection. We aimed to determine whether the CAP self-inspection could serve as a learning opportunity for pathology residents and fellows. To prepare for the inspection, we provided a series of 4 lunchtime seminars covering numerous laboratory management topics relating to inspections and laboratory quality. Preparation for the inspection began approximately 4 months prior to the date of the inspection. The intent was to simulate a CAP peer inspection, with the exception that the date was announced. The associate residency program director served as the team leader. All residents and fellows completed inspector training provided by CAP, and the team leader completed the team leader training. A 20 question pre- and posttest was administered; additionally, an anonymous survey was given after the inspection. The residents’ and fellows’ posttest scores were an average of 15% higher than on the pretest ( P < .01. The surveys as well as subjective comments were overwhelmingly positive. In conclusion, the resident’s and fellow’s experience as an inspector during a CAP self-inspection was a useful tool to learn accreditation and laboratory management.

Licensing of non intrusive inspection equipment s for load and passengers vehicles that use X rays with energies up to 9 MeV. Mexican experience; Licenciamiento de equipos de inspeccion no intrusiva para vehiculos de carga y pasajeros que utilizan rayos X con energias de hasta 9 megaelectronvolts. Experiencia Mexicana

Energy Technology Data Exchange (ETDEWEB)

Munoz M, G. A.; Jimenez C, I., E-mail: armando.munoz@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Jose Ma. Barragan 779, Col. Narvarte, 03020 Mexico D. F. (Mexico)

2013-10-15

In the last years and like part of the extensive program of national security, in Mexico have been introduced a great quantity of non intrusive inspection equipment s for load and passengers vehicles that use X rays up to 9 MeV. Due to the great variety of equipment s, the Comision Nacional de Seguridad Nuclear y Salvaguardias (Mexican regulator organ) has established specific guidelines for their licensing and use supervision. In this work the adopted guidelines are exposed in the technical and administrative evaluation for the later licensing of these equipment s. Relative particular questions to the site of these equipment s and the impact in the public opinion that their use can generate are discussed. (author)

Technical diagnostics - equipment monitoring for increasing safety and availability of nuclear power plants

International Nuclear Information System (INIS)

Sturm, A.; Foerster, R.

1977-01-01

Utilization of technical diagnostics in equipment monitoring of nuclear power plants for ensuring nuclear safety, economic availability, and for decision making on necessary maintenance is reviewed. Technical diagnostics is subdivided into inspection and early detection of malfunctions. Moreover, combination of technical diagnostics and equipment monitoring, integration of technical diagnostics into maintenance strategy, and problems of introducing early detection of malfunctions into maintenance management of nuclear power plants are also discussed. In addition, a compilation of measuring techniques used in technical diagnostics has been made. The international state of the art of equipment monitoring in PWR nuclear power plants is illustrated by description of the sound and vibration measuring techniques. (author)

PAT portable appliance testing : in-service inspection and testing of electrical equipment

CERN Document Server

Scaddan, Brian

2015-01-01

The Electricity at Work Regulations 1989 requires any electrical system to be constructed, maintained and used in such a manner as to prevent danger. This means that inspection and testing of systems, including portable appliances, is needed in order to determine if maintenance is required. This book explains in clear language what needs to be done and includes expert advice on legislation as well as actual testing. The book contains an appendix providing the electrical fundamentals needed by non-specialists and also has sample questions (with answers) for the C&G 2377 exam. It is also an ideal revision guide for the non-specialist, such as maintenance staff and caretakers who carry out these tasks part-time, alongside their many other duties.

The development of a remote gauging and inspection capability for fuel channels in Candu reactors

International Nuclear Information System (INIS)

Dolbey, M.P.; Kupcis, O.A.

1979-01-01

Equipment under development for the inspection and gauging of pressure tubes in CANDU (Canadian Deuterium Uranium) type reactors is described. A brief overview of the mechanical scanning system is presented followed by a detailed description of the measurement and data processing systems for the gauging of diameter and wall thickness, volumetric inspection of the tube wall and gauging of the annular gap between the pressure tube and the calandria tube. Experience of testing ultrasonic transducers in very high (10 6 Roentgens/hour)(R/h) radiation fields is reviewed. (author)

Engineering Work Plan for the Development of Phased Startup Initiative (PSI) Phases 3 and 4 Test Equipment

International Nuclear Information System (INIS)

PITNER, A.L.

2000-01-01

A number of tools and equipment pieces are required to facilitate planned test operations during Phases 3 and 4 of the Phased Startup Initiative (PSI). These items will be used in assessing residual canister sludge quantities on cleaned fuel assemblies, sorting coarse and fine scrap fuel pieces, assessing the size distribution of scrap pieces, loading scrap into a canister, and measuring the depth of the accumulated scrap in a canister. This work plan supercedes those previously issued for development of several of these test items. These items will be considered prototype equipment until testing has confirmed their suitability for use in K West Basin. The process described in AP-EN-6-032 will be used to qualify the equipment for facility use. These items are considered non-OCRWM for PSI Phase 3 applications. The safety classification of this equipment is General Service, with Quality Level 0 (for PSI Phase 3). Quality Control inspections shall be performed to verify basic dimensions and overall configurations of fabricated components, and any special quality control verifications specified in this work plan (Section 3.1.5). These inspections shall serve to approve the test equipment for use in K West Basin (Acceptance Tag). This equipment is for information gathering only during PSI Phases 3 and 4 activities, and will be discarded at the completion of PSI. For equipment needed to support actual production throughput, development/fabrication/testing activities would be more rigorously controlled

Comparing PD results with visual inspection

International Nuclear Information System (INIS)

Rossi, A.; Stone, G.C.

2005-01-01

ENEL is the main generation utility in Italy, with more than 200 hydro units and 120 turbine generators, totaling 39,000 MW of capacity. To help identify the maintenance needs of the stator windings in these units, ENEL has been gradually equipping the generators with partial discharge (PD) sensors that facilitate an on-line measurement of the PD. The paper describes results from several machines that have PD. In all cases, the high PD was confirmed by visual inspections. Although PD usually found the units with severe insulation problems, it was not always possible to determine the causes of the deterioration from the PD pattern. (author)

ASTRID In Service Inspection and Repair: Review of R&D program and associated results

International Nuclear Information System (INIS)

Baqué, François; Jadot, Françoise; Bourdais, Florian le; Sibilo, Julien; Augem, Jean-Michel; Gastaldi, Olivier

2013-01-01

In Service Inspection & Repair (ISI&R): → range of provisions enabling to verify that the equipments state is in compliance with design criteria; → other range of provisions allowing to characterize an abnormal situation (failure, operation mistake) and to perform necessary actions to reach again an achievable plant configuration

Multifrequency eddy-current inspection of seam weld in steel sheath

Energy Technology Data Exchange (ETDEWEB)

Smith, J.H.; Dodd, C.V.; Chitwood, L.D.

1985-04-01

Multifrequency eddy-current techniques were used to perform a continuous on-line inspection of the seam weld in the steel jacket for a superconducting cable. The inspection was required to detect both surface and internal weld flaws in the presence of a large, highly conductive central conductor. Raw eddy-current data were recorded on magnetic tape, and test properties such as discontinuity size and weld penetration were determined by mathematically fitting these data to coefficients developed with representative standards. A sophisticated computer-controlled scanning technique was applied, and a unique scanning device was developed to provide full coverage of the weld and heat-affected zone. The techniques used to develop this multifrequency eddy-current examination are described in this report along with the test equipment, test procedures, and computer programs.

Multifrequency eddy-current inspection of seam weld in steel sheath

International Nuclear Information System (INIS)

Smith, J.H.; Dodd, C.V.; Chitwood, L.D.

1985-04-01

Multifrequency eddy-current techniques were used to perform a continuous on-line inspection of the seam weld in the steel jacket for a superconducting cable. The inspection was required to detect both surface and internal weld flaws in the presence of a large, highly conductive central conductor. Raw eddy-current data were recorded on magnetic tape, and test properties such as discontinuity size and weld penetration were determined by mathematically fitting these data to coefficients developed with representative standards. A sophisticated computer-controlled scanning technique was applied, and a unique scanning device was developed to provide full coverage of the weld and heat-affected zone. The techniques used to develop this multifrequency eddy-current examination are described in this report along with the test equipment, test procedures, and computer programs

Detection of organic residues on poultry processing equipment surfaces by LED-induced fluorescence imaging

Science.gov (United States)

Organic residues on equipment surfaces in poultry processing plants can generate cross- contamination and increase the risk of unsafe food for consumers. This research was aimed to investigate the potential of LED-induced fluorescence imaging technique for rapid inspection of stainless steel proces...

Ultrasonic inspection

International Nuclear Information System (INIS)

Satittada, Gannaga

1984-01-01

Ultrasonic inspection is one of the most widely used methods for nondestructive inspection. The beam of high-frequency sound wave, ultrasonic wave, is introduced into the material. It travels through the material with some attendant loss of energy and can be reflected at interfaces. The reflected beam is detected and analyzed. Ultrasonic inspection is used to detect flaws in metal parts as well as in welded, brazed and bonded joints during research work and developing production and service. It is also used to detect and locate porosity, pipe, and flakes. In addition, it can be used for the measurement of metal thickness. Ultrasonic inspection is therefore used for quality control and material inspection in all major industries

SmartInspect: Smart Contract Inspection Technical Report

OpenAIRE

Bragagnolo , Santiago; Rocha , Henrique ,; Denker , Marcus; Ducasse , Stéphane

2017-01-01

Smart contracts are embedded procedures stored with the data they act upon. Debugging deployed Smart Contracts is a difficult task since once deployed, the code cannot be reexecuted and inspecting a simple attribute is not easily possible because data is encoded. In this technical report, we present SmartInspect to address the lack of inspectability of a deployed contract. Our solution analyses the contract state by using decompilation techniques and a mirror-based architecture to represent t...

Radiological protection requirements applicable to non-invasive inspection of charges with ionizing radiation

International Nuclear Information System (INIS)

Crespo, S.C.; Palmieri, J.A.S.; Silva, F.C.A. da

2017-01-01

The US twin towers attack in 2001 raised concerns about terrorism, illicit trafficking of materials and the possible use of a 'dirty bomb' (DDR), affecting the control of entry and exit of products. Thus, the use of ionizing radiation scanning systems of containers at ports and borders was started to investigate possible entries of illegal material. Brazil, adhering to this concern and due to the holding of major events such as RIO + 20, World Cup, Olympics, etc., increased safety in the movement of goods using non-invasive inspection. Linear electron accelerators, which produce high energy X-rays in the range of 1.5 to 9 MeV, are used to inspect the containers. Since in Brazil there is no specific technical regulation for the operation of non-invasive inspection equipment with X-rays and linear accelerators, ten main technical requirements are presented. It is essential that a technical regulation is drawn up by placing the system of non-invasive inspection of cargo with ionizing radiation in the international radiation protection standard

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.

78 FR 73997 - Airworthiness Directives; Various Aircraft Equipped with Wing Lift Struts

Science.gov (United States)

2013-12-10

...-0023; Directorate Identifier 96-CE-072-AD; Amendment 39-17688; AD 99-01-05 R1] RIN 2120-AA64... Administration (FAA), DOT. ACTION: Final rule. SUMMARY: We are revising Airworthiness Directive (AD) 99-01-05 for certain aircraft equipped with wing lift struts. AD 99-01-05 required repetitively inspecting the wing...

46 CFR 31.40-10 - Cargo Ship Safety Equipment Certificate-T/ALL.

Science.gov (United States)

2010-10-01

... 46 Shipping 1 2010-10-01 2010-10-01 false Cargo Ship Safety Equipment Certificate-T/ALL. 31.40-10 Section 31.40-10 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY TANK VESSELS INSPECTION AND CERTIFICATION Certificates Under International Convention for Safety of Life at Sea, 1974 § 31.40-10 Cargo Ship...

Development of a sludge lancing equipment and FOSAR technology

International Nuclear Information System (INIS)

Jeong, W. T.; Choi, Y. S.; Son, S. Y.; Hong, S. Y.

2003-01-01

A program for developing steam generator lancing equipment was started in 1999 on the request of the Chemistry Division of KHNP of Kori NPP No.1. Based on the program, KALANS r -I lancing system was developed firstly in Korea. Lancing equipments for Ulchin NPP No.2(KSNP) and Youngkwang NPP No.1 have been being developed since 2001. A project for developing FOSAR(Foreign Object Search and Retrieval) equipment has been being developed since 2001. The FOSAR equipment is going to automate the search and retrieval operation which has been manual, thus minimizes radiation exposure and improves the performance of inspection work. Besides, a research to evaluate the feasibility of an ultrasonic cleaning method is also under consideration. A project to develop an Upper Bundle Hydraulic Cleaning (UBHC) system was started on May 2003. In this paper, a steam generator lancing system for Kori NPP No.1 is presented. A research activities for developing FOSAR(Foreign Object Search and Retrieval) system, UBHC(Upper Bundle Hydraulic Cleaning) system, and ultrasonic cleaning system are also presented briefly

Radiographic inspection. Film replacement with digital detector arrays in aerospace applications

International Nuclear Information System (INIS)

Schulte, Frank; Bavendiek, Klaus

2016-01-01

The new Digital Radiographic Inspection method replace more and more the conventional Film technique. For DDA (Digital Detector Array) systems it is currently necessary to use automated or semi-automated systems. For CR (Computer Radiography) Systems the conventional Film Systems may be used. For this CR technique operators can use same X-Ray Units (Bunker) and same X-Ray equipment. But on CR technique we have basically the same settings like the Film-based technique. More or less same exposure times and for aerospace application long scanning times for the CR foils. In fact there is no big benefit in capacity or in economical view. Regarding this issue we thought about the option to use a DDA System instead of a Film or CR System to use the current Film Equipment (Bunker, Generator, Tube.) and replace this 1:1 by a manual system. In this time only small detectors with fine pixel pitch was available on the market. With this type of DDA's is was absolutely uneconomical to inspect parts in serial inspection. Therefore a new generation of DDA's were developed, which is able to replace Film or CR System 1:1 with adequate economical properties for specific applications. The new PerkinElmer XRD 1611 Panel has a size of 40 x 40 cm and a pixel pitch of 100 μm. The baseline for the new DDA Panel was the most used X-Ray Film in size 30 x 40 cm. The Pixel Pitch and requirements for Bad Pixel based on the requirements for spatial resolution of the applicable ASTM standards and different customer specifications for castings. With this new DDA System is it possible to inspect small and medium castings in very short time with excellent image quality. The System is able to process images under 1 minute include averaging. Images will be transferred by a specific software tool to an offline reading station where certified Level 2 operator can inspect the images. Images will be archived as 16bit DICONDE File. All relevant images information are included in DICONDE File

RPII Inspection and Licensing Activities and Annual Inspection Programme for 2011

International Nuclear Information System (INIS)

2010-07-01

The objective of this report is to provide an overview of inspection activities of the Radiological Protection Institute of Ireland, to examine the evolution in licensee numbers and to outline the rationale in developing annual inspection programmes. All inspection activities are now carried out within the framework of a quality management system including: inspection planning, the training of inspectors, the conduct of inspections as well as inspection follow up and review. The report also provides an overview of the main features of the quality system

RPII Inspection and Licensing Activities and Annual Inspection Programme for 2013

International Nuclear Information System (INIS)

2013-04-01

The objective of this report is to provide an overview of inspection activities of the Radiological Protection Institute of Ireland RPII, to examine the evolution in licensee numbers and to outline the rationale in developing annual inspection programmes. All inspection activities are now carried out within the framework of a quality management system including inspection planning, the training of inspectors, the conduct of inspections as well as post inspection follow up and review. This report also provides an overview of the main features of the quality system

Vibrodynamical tests of RP equipment with application of imitation area of WWER-1000 reactor

International Nuclear Information System (INIS)

Khajretdinov, V.U.; Tarkhanov, V.V.; Rodionova, I.N.

2015-01-01

Performance of preoperational tests and measurements with application of imitation area of the reactor is a distinctive characteristic of putting into operation of NPP Units with WWER-1000/1200. The imitation area consists of 163 full-scale FA models, where fuel matrixes made of nuclear-fissionable material, are replaced by leaden simulators. Vibrodynamic tests involve inspection of hydrodynamic disturbances in the primary circuit (dynamic impact on the inspected elements), characteristics of vibration response of the main equipment stress-deformed state of bearing structure, and also parameters of moving and geometry of the inspected objects (boundary conditions at process simulation). Preoperational tests and measurements on the simulated area of WWER-1000/1200 are obligatory and performed at every unit of NPP of this type [ru

SAFIRE - a robotic inspection system for CANDU feeders

Energy Technology Data Exchange (ETDEWEB)

Buckingham, R. [OC Robotics, Bristol (United Kingdom)

2011-07-01

The condition of primary circuit feeder pipes in CANDU reactors is relevant to the commercial viability and plant life. One known wear mechanism is external fretting between feeder pipes and adjacent services or support structures, particularly within the Upper Feeder Cabinet (UFC). Fretting leads to wall thinning which must not exceed certain agreed limits. Chafe shields have been added to protect the feeder pipes. Regular inspections are required of the chafe shields, feeder pipes and other structures that may cause feeder damage. Historically, the dose received by inspectors conducting this work has been significant. For this reason Ontario Power Generation has invested in a remotely operated robot system to conduct visual inspections within the UFC. This system, called SAFIRE for 'Snake-Arm Feeder Inspection Robot Equipment' has been deployed at Pickering during 2010 and 2011 and has been used to inspect areas that are extremely difficult to inspect with existing manual techniques. The 2011 scope of work included inspection of a total of 660 feeder pipes in three UFC quadrants, in two reactors. The full scope was completed over a one-month period in Autumn 2011 in which SAFIRE was used during 23, twelve hour shifts. This included two periods each of 72 hours of continuous operation using multiple teams of operators. SAFIRE is remote controlled delivery system for multiple cameras to record still images and video. The main system elements include a snake-arm robot mounted on a mobile vehicle. It can be controlled from up to 500m away using a fibre/copper connection. The snake-arm is 2.2m long, 25mm wide and has 18 degrees of freedom. It is designed to snake between the rows of feeder pipes to inspect feeder/hanger interfaces, both above and below the feeder cabinet catwalks. Future upgrades offer the potential to add additional tools to increase functionality. This paper describes the SAFIRE development process from inception to operational experience

SAFIRE - a robotic inspection system for CANDU feeders

International Nuclear Information System (INIS)

Buckingham, R.

2011-01-01

The condition of primary circuit feeder pipes in CANDU reactors is relevant to the commercial viability and plant life. One known wear mechanism is external fretting between feeder pipes and adjacent services or support structures, particularly within the Upper Feeder Cabinet (UFC). Fretting leads to wall thinning which must not exceed certain agreed limits. Chafe shields have been added to protect the feeder pipes. Regular inspections are required of the chafe shields, feeder pipes and other structures that may cause feeder damage. Historically, the dose received by inspectors conducting this work has been significant. For this reason Ontario Power Generation has invested in a remotely operated robot system to conduct visual inspections within the UFC. This system, called SAFIRE for 'Snake-Arm Feeder Inspection Robot Equipment' has been deployed at Pickering during 2010 and 2011 and has been used to inspect areas that are extremely difficult to inspect with existing manual techniques. The 2011 scope of work included inspection of a total of 660 feeder pipes in three UFC quadrants, in two reactors. The full scope was completed over a one-month period in Autumn 2011 in which SAFIRE was used during 23, twelve hour shifts. This included two periods each of 72 hours of continuous operation using multiple teams of operators. SAFIRE is remote controlled delivery system for multiple cameras to record still images and video. The main system elements include a snake-arm robot mounted on a mobile vehicle. It can be controlled from up to 500m away using a fibre/copper connection. The snake-arm is 2.2m long, 25mm wide and has 18 degrees of freedom. It is designed to snake between the rows of feeder pipes to inspect feeder/hanger interfaces, both above and below the feeder cabinet catwalks. Future upgrades offer the potential to add additional tools to increase functionality. This paper describes the SAFIRE development process from inception to operational experience gained

Inspection vehicle

International Nuclear Information System (INIS)

Takahashi, Masaki; Omote, Tatsuyuki; Yoneya, Yutaka; Tanaka, Keiji; Waki, Tetsuro; Yoshida, Tomiji; Kido, Tsuyoshi.

1993-01-01

An inspection vehicle comprises a small-sized battery directly connected with a power motor or a direct power source from trolly lines and a switching circuit operated by external signals. The switch judges advance or retreat by two kinds of signals and the inspection vehicle is recovered by self-running. In order to recover the abnormally stopped inspection vehicle to the targeted place, the inspection vehicle is made in a free-running state by using a clutch mechanism and is pushed by an other vehicle. (T.M.)

Pre-service inspection and in-service inspection in Japan

International Nuclear Information System (INIS)

Uebayashi, T.; Miyake, Y.

1985-01-01

To ensure the safety of nuclear power plant, pre-service inspection/in-service inspection (PSI/ISI) has an important role, and informations obtained from various inspections during plant shut-down period are contributing to establish effective preventive maintenance activities for plant facilities. It might be said that the high level of availability of Japanese light-water nuclear power plants in these two or three years has been achieved by those efforts. In case of Japan, inspections to be carried out during scheduled plant shut-down period are not limited to code requirements but include many other inspections which are mostly reflected from troubles experienced in both domestic and overseas plants. Usually, those additional inspections are performed by Ministry of Trade and Industries' (MITI's) regulator and/or tentative requirement and considered as ISI in broad meaning. To achieve high availability of plant, it is essential to avoid unscheduled shut-down and to shorten inspection period. The developments of new technology to perform effective ISI for operating plants are continued, but on the other hand it is also very important to pay a great consideration to inspectability of the plants at the stage of plant engineering. With the leadership of MITI, improvement and standardization of light-water nuclear power plant has been proceeded and newly constructed plants have great advantage from the point of view on ISI

NDT method in determining the rate of corrosion applicable to risk based inspection

International Nuclear Information System (INIS)

Mohamed Hairul Hasmoni; Mohamad Pauzi Ismail; Ab Razak Hamzah

2004-01-01

Corrosion is a major problem in oil and gas industries, refineries and chemical process plants as the equipment is often exposed to corrosive environments or elevated temperature. Important equipment need to operate safely and reliably to avoid injuries to personnel and the public, and to prevent loss time and cost incurred due to loss of production and shutdown. The paper assess the approach in evaluating the technique of non-destructive testing (NDT) using Ultrasonic Testing (UT) in determining the rate of corrosion and remaining life of equipment applicable to Risk Based Inspection (RBI). Methods in determining the corrosion rate are presented using analytical method. Examples and data from MINT chiller water pipeline are presented to illustrate the application of these methods. (Author)

APPLICATION OF EQUIPMENT FOR AUTOMATIC CONTROL OF PLANAR STRUCTURES IN MANUFACTURING MASTER MASKS OF INTEGRATED CIRCUITS ON PHOTO-MASKS

Directory of Open Access Journals (Sweden)

S. M. Avakov

2007-01-01

Full Text Available Following the concept of defect-free manufacturing of master masks of IC on photo-masks, two Belarusian sets of optomechanical equipment for 0,3 5 p and 90 nanometers are presented in the paper. Each of the sets comprises:   • Multi-channel laser pattern generator; • Automatic mask defect inspection system; • Laser-based mask defect repair system.The paper contains description of automatic mask defect inspection process during photo-mask manufacturing and respective basic technological operations of the processes.Advantages of a complex approach to the development of a set of opto-mechanical equipment for defect-free manufacturing of photo-masks have been analyzed in the paper. 

46 CFR 159.007-7 - Application for acceptance for production inspections and tests: Coast Guard action.

Science.gov (United States)

2010-10-01

... and tests: Coast Guard action. 159.007-7 Section 159.007-7 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) EQUIPMENT, CONSTRUCTION, AND MATERIALS: SPECIFICATIONS AND APPROVAL APPROVAL....007-7 Application for acceptance for production inspections and tests: Coast Guard action. (a) From...

Prediction degradation trend of nuclear equipment based on GM (1, 1)-Markov chain

International Nuclear Information System (INIS)

Zhang Liming; Zhao Xinwen; Cai Qi; Wu Guangjiang

2010-01-01

The degradation trend prediction results are important references for nuclear equipment in-service inspection and maintenance plan. But it is difficult to predict the nuclear equipment degradation trend accurately by the traditional statistical probability due to the small samples, lack of degradation data and the wavy degradation locus. Therefore, a method of equipment degradation trend prediction based on GM (1, l)-Markov chain was proposed in this paper. The method which makes use of the advantages of both GM (1, 1) method and Markov chain could improve the prediction precision of nuclear equipment degradation trend. The paper collected degradation data as samples and accurately predicted the degradation trend of canned motor pump. Compared with the prediction results by GM (1, 1) method, the prediction precision by GM (1, l)-Markov chain is more accurate. (authors)

Regulations No. 59 of 20 February 1978 on X-ray skin therapy equipment up to 50 kV

International Nuclear Information System (INIS)

1978-01-01

These regulations lay down the provisions to be complied with for the protection of medical staff and patients when using X-ray equipment for skin therapy. The operators of such equipment must comply with the technical guidelines contained in the regulations and provision is made for annual inspections to ensure that the devices meet the necessary safety standards. (NEA) [fr

RBI - Risk Based Inspection: new technologies and methods applied to inspections of FPSO (Floating Production, Storage and Offloading Vessel) hull; IBR - Inspecao Baseada em Risco: novas tecnologias e metodos aplicados as inspecoes de casco de FPSOs

Energy Technology Data Exchange (ETDEWEB)

Farias, Bruno de; Figueiredo, Eduardo; Luiz, Marcio [PETROBRAS S.A., Rio de Janeiro, RJ (Brazil); Meurer, Gustavo; Duarte, Romulo; Oliveira, Thais; Krzonkalla, Viviane [ABS Consulting, Rio de Janeiro, RJ (Brazil)

2008-07-01

With the aging of the FPSO's, which are fundamental to the operation Offshore, better techniques and technologies must be applied to assess more accurately the actual efficiency and structural conditions of producing unit. With the emergence of new engineering techniques and equipment and methods of structural inspection, is now possible to use these new technologies to better manage risk and reliability of the structure of the FPSO, with that, the inspections and methods are more rational and efficient. The Risk-Based Inspection is the tool for monitoring operation of industrial plants with systemic use of technology in conjunction with risk analysis and reliability. His concept is applicable to various branches of industry. The companies began their implementation of oil by refineries. The group of ABS Consulting with PETROBRAS has been developing and implementing these new technologies in inspections of hulls of FPSO's. Applied successfully in the units of the Campos basin, these methods are used by the group of Risk-Based Inspection to improve the efficiency of all the steps involved with the structural integrity of the unit. (author)

Performance of on-site Medical waste disinfection equipment in hospitals of Tabriz, Iran

Directory of Open Access Journals (Sweden)

Hassan Taghipour

2016-10-01

Full Text Available Background: The number of studies available on the performance of on-site medical waste treatment facilities is rare, to date. The aim of this study was to evaluate the performance of onsite medical waste treatment equipment in hospitals of Tabriz, Iran. Methods: A various range of the on-site medical waste disinfection equipment (autoclave, chemical disinfection, hydroclave, and dry thermal treatment was considered to select 10 out of 22 hospitals in Tabriz to be included in the survey. The apparatus were monitored mechanically, chemically, and biologically for a six months period in all of the selected hospitals. Results: The results of the chemical monitoring (Bowie-Dick tests indicated that 38.9% of the inspected autoclaves had operational problems in pre-vacuum, air leaks, inadequate steam penetration into the waste, and/or vacuum pump. The biological indicators revealed that about 55.55% of the samples were positive. The most of applied devices were not suitable for treating anatomical, pharmaceutical, cytotoxic, and chemical waste. Conclusion: Although on-site medical waste treating facilities have been installed in all the hospitals, the most of infectious-hazardous medical waste generated in the hospitals were deposited into a municipal solid waste landfill, without enough disinfection. The responsible authorities should stringently inspect and evaluate the operation of on-site medical waste treating equipment. An advanced off-site central facility with multi-treatment and disinfection equipment and enough capacity is recommended as an alternative.

The use of NPAR [Nuclear Plant Aging Research] results in plant inspection activities

International Nuclear Information System (INIS)

Gunther, W.; Taylor, J.

1989-01-01

The US NRC's Nuclear Plant Aging Research (NPAR) Program is a hardware oriented research program which has produced a large data base of equipment and system operating, maintenance, and testing information. Equipment and systems which have a propensity for age related degradation are identified, and methods for detecting and mitigating aging effects have been evaluated. As plants age, it becomes increasingly important that NRC inspectors be cognizant of plant aging phenomena. This paper describes the NPAR information which can enhance inspection activities, and provides a mechanism for making pertinent research available to the inspectors. 7 refs., 2 figs

Modern equipment of radiation intrascopie for inspection of welding

International Nuclear Information System (INIS)

Sosnin, F.R.

1976-01-01

The systems are described of radiation intrascopy of controlled objects studied by x-raying and the effective transformation of the shadow x-ray image into light-shadow one. In order to increase the range of controlled thicknesses and to improve the flaw detector sensitivity of the control, the electron-optical devices and telesivion technology are applied. So it becomes possible, through the amplification of the image, to use the high resolving power of the eye. Four types of modern equipment with amplification of the image have been defined, depending on x-rays and light converters. The main technical characteristics of some devices are given. The motion mechanisms of the controlled objects are considered. All kinds of radiation intrascopy systems developed up to the present time have the sensitivity of control of steel welded objects with thickness 5-50 mm which is 2 to 4 times greater than the sensitivity of the radiographic control method. The x-ray-television control is 2 to 4 times more efficient than radiographic one and is preferable from the safety point of view

Continuous improvement in manufacturing and inspection of fuel; Mejora continua en fabricacion e inspeccion de combustible

Energy Technology Data Exchange (ETDEWEB)

Domingon, A.; Ruiz, R.

2015-07-01

The manufacturing and inspection process of fuel assemblies in ENUSA is characterized by its robustness acquired over the last thirty years of experience in manufacturing. The reliability of these processes is based on a qualified processes and continuous improvement in the design and upgrading of equipment and optimization of software and manufacturing processes. Additionally, management and quality control systems have been improved in both software and measuring business objectives. this article emphasizes the improvements made over the past five years in management, production and inspection of fuel assemblies. (Author)

Analysis of QA audit checklist for equipment suppliers

International Nuclear Information System (INIS)

Tian Xuehang

2012-01-01

Eleven aspects during the equipment manufacturing by the suppliers, including the guidelines and objectives of quality assurance, management department review, document and record control, staffing and training, design control, procurement control, control of items, process control, inspection and testing control, non-conformance control, and internal and external QA audit, are analyzed in this article. The detailed QA audit checklist on these above mentioned aspects are described and the problems found in real QA audit are listed in this article. (authors)

The use of x-ray imaging technology in cargo inspection

International Nuclear Information System (INIS)

Palgan, Renato D.

2009-01-01

The aftermath of the September 11,2001 terrorist attack in the United States has brought a significant change in the conduct of trade and commerce among nations. The introduction on non-intrusive cargo inspection equipment, most x-ray and gamma ray scanners, among customs administrations worldwide has been widely employed and incorporated in their respective cargo examination procedures as part of their security initiative to deter terrorist threats. In compliance with our international commitment and agreement passed by the World Customs Organization which required the use of modern technology in cargo inspection, the Bureau of Customs had acquired 30 units of container x-ray scanners in 2006 from China that became operational in 2007 and the acquisition of which was guided by the following objectives: maximize collection of government revenues,facilitate trade and commerce, prevent smuggling, and safeguard the public and environment against the entry of hazardous and harmful substance. In this light, this paper discusses the brief background of the non-intrusive container inspection system project of the Bureau of Customs, an overview of the technical features of x-ray imaging technology acquired, the procedures in the application of x-ray inspection in containerized cargo, the radiation safety infrastructures and considerations, and a review of some major accomplishments after its two years of existence. (author)

Performance-based inspection and maintenance strategies

International Nuclear Information System (INIS)

Vesely, W.E.

1995-01-01

Performance-based inspection and maintenance strategies utilize measures of equipment performance to help guide inspection and maintenance activities. A relevant measure of performance for safety system components is component unavailability. The component unavailability can also be input into a plant risk model such as a Probabilistic Risk Assessment (PRA) to determine the associated plant risk performance. Based on the present and projected unavailability performance, or the present and projected risk performance, the effectiveness of current maintenance activities can be evaluated and this information can be used to plan future maintenance activities. A significant amount of information other than downtimes or failure times is collected or can be collected when an inspection or maintenance is conducted which can be used to estimate the component unavailability. This information generally involves observations on the condition or state of the component or component piecepart. The information can be detailed such as the amount of corrosion buildup or can be general such as the general state of the component described as ' high degradation', ' moderate degradation', or ' low degradation'. Much of the information collected in maintenance logs is qualitative and fuzzy. As part of an NRC Research program on performance-based engineering modeling, approaches have been developed to apply Fuzzy Set Theory to information collected on the state of the component to determine the implied component or component piecepart unavailability. Demonstrations of the applications of Fuzzy Set Theory are presented utilizing information from plant maintenance logs. The demonstrations show the power of Fuzzy Set Theory in translating engineering information to reliability and risk implications

In service inspection of pipes based on risk methods

International Nuclear Information System (INIS)

Mendoza G, G.; Viais J, J.; Carmona C, M.

2006-01-01

The politics of the Nuclear Regulatory Commission (by its initials in English NRC) of the United States of America on the use of the Probabilistic Safety Analysis (PSA) in activities of nuclear regulation it foments the use of this analysis technique to improve the decisions making, to reduce the unnecessary work in maintenance aspects, inspection and tests and to improve the regulatory efficiency. The inspection programs in service (ISI by its initials in English) developed by the American Society of Mechanical Engineers (by its initials in English ASME) it has been the one primary mechanism to prove the mechanical equipment in plants of nuclear energy, these programs indeed have been carried out in plants of nuclear energy by more of two decades. Their purpose is to identify the conditions, such as indications of cracks that are precursory of flights and ruptures which violate the integrity principles of the pressure frontier. The inspection in service activities include ultrasonic tests, surface tests and penetrating liquids test, also activities that include the scaffolds construction, removal of insulations and welding polishing. The inspections in service every 18 months during the times outside of service are executed. One of the objectives is to lower the costs of the inspections during the times outside of service and to reduce the exposure to the radiation by part of the personnel during these times out for inspections, while it is increased or it maintains the personnel's safety and the reliability. As part of the methodology a pipe segment is selected for which a fault in any point has the same consequences, being calculated the fault probability of the tube using the dimensions of the segment. In this work the inspection in service methodology is applied based on risk to an aspersion system of low pressure of the Laguna Verde Nucleo electric Central. For this system a reduction in the number of welding to inspect of 103 to only 15 is obtained

Lessons learned in testing of Safeguards equipment

International Nuclear Information System (INIS)

Pepper, Susan; Farnitano, Michael; Carelli, Joseph

2001-01-01

Upgrade Travel Funding' - This subtask provides funding for the upgrade of DIS equipment installed in the field; E.125.3, 'DIS Radiation Field Characterization' - This subtask provides for the procurement by the IAEA of radiation measurement equipment and technical assistance for the characterization of radiation conditions in the locations where DIS will be installed. This will help the IAEA ensure that the design specifications for the equipment are consistent with the location where the instrument will be used; E.125.4, 'DIS Design Limit Testing and Advise to Strengthen IAEA's Current Equipment Qualification Criteria' - Under this subtask, Wyle Laboratories and Quanterion Solutions will conduct SDIS design limit testing, including harsh environmental testing and accelerated aging, to determine the expected lifetime and produce a design limit report to include maximum operating environment vs. design limit analysis. Additionally, this task will include the development of a strengthened environmental qualification test plan and reliability and maintainability definition methodology for all safeguards equipment. The implementation of new equipment by the Department of Safeguards is costly. Expected costs associated with the implementation of equipment include capital costs, training and in some cases travel. The cost is dramatically increased when operational issues arise due to the costs of studying the issues, modifying and upgrading the equipment and additional travel. The U.S. Support Program believes that the IAEA's Division of Safeguards Technical Support (SGTS) must strengthen its equipment-testing program to ensure that the equipment it approves for inspection use is reliable and will not place additional burden on the Department of Safeguards' maintenance and inspection staff. The U.S. Support Program recognizes that SGTS already requires a series of fundamentally important and revealing tests, but we believe that additional tests should be added to the testing

The Expert System Application For Inspection Of The Power Plants

International Nuclear Information System (INIS)

Josowidagdo, L.

1997-01-01

This paper describes the application of expert system to evaluate and consider the problem encountered in this fields are complex and time consuming. As as example several factors affecting system voltage selections are load magnitude, distance from the main power supply, safety, standards, cost of utilization and service system equipment, and future load growth. The inspection deal with interactions between alternatives, uncertainties, and important non financial parameter. Several complex problems are multiple objective functions, multiple constraints, complex system interactions, the need for accuracy, the need for trade off, optimization, and coordination of the decision making process. ASDEP is one of the expert system for electric power plant design that describe the application of the artificial intelligence to design of a power plan's electrical auxiliary system. In this circumstance this paper will elaborate another aspect for using the expert system in the inspection

消毒供应中心设置总质检班对物品清洗消毒灭菌质量的影响%Effect of a general quality inspection group on quality of cleaning, disinfection,and sterilization of medical equipment in central sterile supply department

Institute of Scientific and Technical Information of China (English)

钱云娟; 刘经纬; 朱玉华; 周美玲

2013-01-01

目的 探讨消毒供应中心设立总质检班次对提高各种污染物品清洗和灭菌质量的作用.方法 2009年10月始重新调整班次职责,设置专职总质检班,依据卫生部对消毒供应中心清洗消毒灭菌质量的规定,建立“日常监测记录表”对污染器械、物品清洗质量进行监测并记录,以确保清洗、消毒、灭菌各环节的工作质量,为全院提供合格的无菌产品.结果 2009年10月至2012年3月设立总质检班后污染器械清洗不合格数下降；无菌物品采样细菌培养均为无菌生长,100％合格.结论 总质检班护士每日实行常态化检查督促,及时发现并纠正清洗环节的问题,协助护士长做好难点、弱点、重点的质量管理,能在第一时间纠正偏差,使消毒供应中心器械清洗工作质量得以及时有效的持续改进.%Objective To explore the effect of a general quality inspection group on quality of cleaning,disinfection,and sterilization of medical equipment in central sterile supply department (CSSD).Methods In accordance with Ministry of Health,we reorganized the responsibilities of working groups and assigned a specific general quality inspection group in October 2009.The group formed a daily checking table and were designated to inspect and track down the cleaning process of contaminated equipment and articles,thereby ensuring appropriate cleaning,disinfection and sterilization to provide qualified sterile products for the hospital.Results Numbers of unqualified equipment and articles after cleaning enjoyed a downward trend from October 2009 through March 2012.Bacterial cultures found no germs grew in samples of sterile products.All the equipment and articles that went through processing in CSSD were qualified.Conclusion The general quality inspection group made regular checking and inspection a daily routine,which corrected problems in cleaning timely and helped the head nurse to manage the thorny points,the blind sides

Present state of 'Mutsu', the general inspection of safety and the repair of shielding

International Nuclear Information System (INIS)

1980-01-01

The Agency has carried out the works based on the plan for the repair of shielding and the general inspection of safety in the nuclear ship ''Mutsu'' also in 1979. As for the repair of shielding, the permission by the prime minister to alter the nuclear reactor installation was obtained. The contents of the alteration are the repair of primary and secondary shieldings and the additional construction of a tank for storing liquid waste. As for the general inspection of safety, the tests for confirming the functions of main machinery and equipments have been carried out since January, 1979. A set of testing apparatuses was made as the preparation for the flaw detection test of steam generator tubes. As for the general inspection of softwares, the re-evaluation of the design of nuclear reactor plant and the analysis of the accidents in nuclear reactor plant were almost completed. Considering the accident of TMI No. 2 reactor, the inspection of softwares is in progress. The contract for these repair and inspection is not yet made, and the negotiations are under way. The nuclear ship ''Mutsu'' was brought to Sasebo Port in October, 1978, and dry-docked in July, 1979. As the result of inspection, any rust and wear were not found on the bottom plates, rudder and propeller. The survey of environmental radioactivity in Sasebo and Ominato, the budget for the repair and inspection, and the movement of the government are also reported. (Kako, I.)

Use of operator-provided, installed C/S equipment in IAEA safeguards

International Nuclear Information System (INIS)

Shea, T.; Rundquist, D.; Gaertner, K.; Yellin, E.

1987-01-01

Developing solutions for complex safe guards problems in close cooperation with Operators is becoming more common, especially as the IAEA continues to operate under zero-growth limitations. This has in practice taken on various forms; from the extreme case of very specific equipment developed and constructed by the State/Operator for use in only one facility, to the more normal case where only the development is carried out by the State/Operator. This practice has advantages and disadvantages. For example, to ensure that Agency inspections will be carried out in a predictable manner, it will be in the Operator's interest to ensure that any equipment he provides is of the highest quality, meets all national safety requirements, and is installed and maintained in such a manner that it will provide years of service. Agency equipment performs its intended function in a reliable manner, but with very specific, limited applications in mind, improvements in reliability over that obtained with normal Agency equipment are to be expected. Also, the authors experience is that reaching acceptable arrangements for the use of State- of Operator-supplied equipment is often far more straightforward than when arranging to apply Agency equipment

Software Formal Inspections Guidebook

Science.gov (United States)

1993-01-01

The Software Formal Inspections Guidebook is designed to support the inspection process of software developed by and for NASA. This document provides information on how to implement a recommended and proven method for conducting formal inspections of NASA software. This Guidebook is a companion document to NASA Standard 2202-93, Software Formal Inspections Standard, approved April 1993, which provides the rules, procedures, and specific requirements for conducting software formal inspections. Application of the Formal Inspections Standard is optional to NASA program or project management. In cases where program or project management decide to use the formal inspections method, this Guidebook provides additional information on how to establish and implement the process. The goal of the formal inspections process as documented in the above-mentioned Standard and this Guidebook is to provide a framework and model for an inspection process that will enable the detection and elimination of defects as early as possible in the software life cycle. An ancillary aspect of the formal inspection process incorporates the collection and analysis of inspection data to effect continual improvement in the inspection process and the quality of the software subjected to the process.

Remote inspection with multi-copters, radiological sensors and SLAM techniques

Science.gov (United States)

Carvalho, Henrique; Vale, Alberto; Marques, Rúben; Ventura, Rodrigo; Brouwer, Yoeri; Gonçalves, Bruno

2018-01-01

Activated material can be found in different scenarios, such as in nuclear reactor facilities or medical facilities (e.g. in positron emission tomography commonly known as PET scanning). In addition, there are unexpected scenarios resulting from possible accidents, or where dangerous material is hidden for terrorism attacks using nuclear weapons. Thus, a technological solution is important to cope with fast and reliable remote inspection. The multi-copter is a common type of Unmanned Aerial Vehicle (UAV) that provides the ability to perform a first radiological inspection in the described scenarios. The paper proposes a solution with a multi-copter equipped with on-board sensors to perform a 3D reconstruction and a radiological mapping of the scenario. A depth camera and a Geiger-Müler counter are the used sensors. The inspection is performed in two steps: i) a 3D reconstruction of the environment and ii) radiation activity inference to localise and quantify sources of radiation. Experimental results were achieved with real 3D data and simulated radiation activity. Experimental tests with real sources of radiation are planned in the next iteration of the work.

Remote inspection with multi-copters, radiological sensors and SLAM techniques

Directory of Open Access Journals (Sweden)

Carvalho Henrique

2018-01-01

Full Text Available Activated material can be found in different scenarios, such as in nuclear reactor facilities or medical facilities (e.g. in positron emission tomography commonly known as PET scanning. In addition, there are unexpected scenarios resulting from possible accidents, or where dangerous material is hidden for terrorism attacks using nuclear weapons. Thus, a technological solution is important to cope with fast and reliable remote inspection. The multi-copter is a common type of Unmanned Aerial Vehicle (UAV that provides the ability to perform a first radiological inspection in the described scenarios. The paper proposes a solution with a multi-copter equipped with on-board sensors to perform a 3D reconstruction and a radiological mapping of the scenario. A depth camera and a Geiger-Müler counter are the used sensors. The inspection is performed in two steps: i a 3D reconstruction of the environment and ii radiation activity inference to localise and quantify sources of radiation. Experimental results were achieved with real 3D data and simulated radiation activity. Experimental tests with real sources of radiation are planned in the next iteration of the work.

Strategic plan for the development of IAEA safeguards equipment

International Nuclear Information System (INIS)

Khlebnikov, N.

2001-01-01

Full text: The need for a top-down Safeguards Strategy to focus departmental objectives was recognized by the Programme Performance Appraisal System (PPAS) performed on the Equipment Development Project in 1999. The Department of Safeguards prepared at the end of 2000 a 5-year Strategic Plan to identify the changes and improvements expected to take place over the 2001-2005 period. Those Strategic Objectives were supposed to be used to properly plan IAEA Safeguards activities and define appropriate and coherent R and D programmes. The present paper describes the strategic directions that the IAEA will follow in the area of equipment development in order to meet the Safeguards Department long-term objectives for 2001-2005. The paper, which is derived from the IAEA Strategic Equipment Development Plan, prepared by the Division of Technical Support, includes two parts: general principles and policies applicable to all equipment development tasks; specific strategic guidance. The paper will not describe the detailed plans which are prepared based on the strategic plan on a biannual basis. Equipment development activities have been divided in five major projects (NDA, Seals, Surveillance, Unattended Monitoring and Remote Monitoring). Strategic directions for each of these projects will be described in the paper. Separate sections will deal with equipment development strategic guidance in the area of additional protocol inspections, JNFL projects, illicit trafficking and Trilateral Initiative. (author)

Reticle inspection equipment productivity increase using SEMI specification for reticle and pod management

Science.gov (United States)

Taylor, Ron; Downey, Jack; Wood, Jeffrey; Lin, Yen-Hung; Bugata, Bharathi; Fan, Dongsheng; Hess, Carl; Wylie, Mark

2016-10-01

In this work, the SEMI specification for reticle and pod management (E109) with internal reticle library support has been integrated for the first time on KLA-Tencor's TeronTM and TeraScanTM reticle inspection tools. Manufacturing Execution System scheduling reticle jobs and Automated Material Handling System scheduling to transfer pods simultaneously have also been integrated and tested. GLOBALFOUNDRIES collaboratively worked with KLA-Tencor to successfully implement these capabilities. Both library and non-library scenarios have been demonstrated for comparison in a real production environment resulting in productivity increase of approximately 29% by making use of the library. Reticle re-qualification test cases were used for the comparison in this work.

Laser Shearography Inspection of TPS (Thermal Protection System) Cork on RSRM (Reusable Solid Rocket Motors)

Science.gov (United States)

Lingbloom, Mike; Plaia, Jim; Newman, John

2006-01-01

Laser Shearography is a viable inspection method for detection of de-bonds and voids within the external TPS (thermal protection system) on to the Space Shuttle RSRM (reusable solid rocket motors). Cork samples with thicknesses up to 1 inch were tested at the LTI (Laser Technology Incorporated) laboratory using vacuum-applied stress in a vacuum chamber. The testing proved that the technology could detect cork to steel un-bonds using vacuum stress techniques in the laboratory environment. The next logical step was to inspect the TPS on a RSRM. Although detailed post flight inspection has confirmed that ATK Thiokol's cork bonding technique provides a reliable cork to case bond, due to the Space Shuttle Columbia incident there is a great interest in verifying bond-lines on the external TPS. This interest provided and opportunity to inspect a RSRM motor with Laser Shearography. This paper will describe the laboratory testing and RSRM testing that has been performed to date. Descriptions of the test equipment setup and techniques for data collection and detailed results will be given. The data from the test show that Laser Shearography is an effective technology and readily adaptable to inspect a RSRM.

Inspection surveys of x-ray inspection systems: results of five years and implications on future management of radiation risks

International Nuclear Information System (INIS)

Maharaj, H.P.

1999-01-01

Until the mid-1980s, federal inspectors performed radiation surveys annually on individual x-ray inspection systems which were operated for security screening purposes in federal facilities nationwide, and problems identified were corrected. The surveys were undertaken because of perceived high radiation risks and a need to ensure worker and public external exposures were minimized. The x-ray inspection systems are federally regulated under the Radiation Emitting Devices (RED) Act and, initially they were assessed by model type against the design, construction and performance criteria specified in the applicable RED regulations (Schedule II, Part IV) and were found compliant. A subsequent study not only demonstrated a much lower radiation risk attributed to a combination of technological advances in x-ray system design with narrow primary beams, high efficiency detectors and image processing capability, but also stressed the need for proper equipment maintenance and continued education of operators and maintenance personnel. Survey frequency was thus reduced to once every 2-3 years in accordance with a 1993 federal operational standard (Safety Code 29). The radiation protection principles in Safety Code 29 are similar to those of the 1996 International Atomic Energy Agency (IAEA) Basic Safety Standards for the protection against ionizing radiation and the safety of radiation sources. The purpose of this study was to assess inspection-survey data from 1993 through 1997 to elicit guidance toward the future management of radiation risks associated with the operation of such x-ray systems. (author)

Increasing for effectiveness of inspection of the use of radioactive substances well logging

International Nuclear Information System (INIS)

Hesty Rimadianny

2015-01-01

One of the utilization of nuclear power is the use of radioactive substances for well logging. To ensure the achievement of radiation safety and security in the use of radioactive substances for well logging activities BAPETEN carries out inspections in accordance with the mandate as sepulated in the Government Regulation No. 29 of 2008 on the Licensing Resource Utilization Ionizing Radiation and Nuclear Materials. Besides referring to the implementation of Government Regulation inspection also refers to BAPETEN Chairman Regulation No. 5 of 2009 on Radiation Safety in the Use of Radioactive material for well logging. In 2014, of 18 facilities inspected the most significant findings include the availability of equipment safety and security of radioactive substances, as well as the availability and suitability of documents and records of safety and security of radioactive substances for well logging activities. Based on these findings BAPETEN needs to make efforts to increase the effectiveness of inspections on the use of radioactive substances for well logging. Increasing the effectiveness of these inspections include a commitment for the frequency of well logging inspection, the number of qualified of inspectors in accordance with the established procedures and optimizing the law enforcement process which includes the application of administrative sanctions in the form of a written warning, license suspension, revocation until reporting to law enforcement. Besides, BAPETEN need to improve the effectiveness of outreach programs and legal guidance as a precaution in the long run. (author)

Laser Safety Inspection Criteria

International Nuclear Information System (INIS)

Barat, K

2005-01-01

A responsibility of the Laser Safety Officer (LSO) is to perform laser safety audits. The American National Standard Z136.1 Safe use of Lasers references this requirement in several sections: (1) Section 1.3.2 LSO Specific Responsibilities states under Hazard Evaluation, ''The LSO shall be responsible for hazards evaluation of laser work areas''; (2) Section 1.3.2.8, Safety Features Audits, ''The LSO shall ensure that the safety features of the laser installation facilities and laser equipment are audited periodically to assure proper operation''; and (3) Appendix D, under Survey and Inspections, it states, ''the LSO will survey by inspection, as considered necessary, all areas where laser equipment is used''. Therefore, for facilities using Class 3B and or Class 4 lasers, audits for laser safety compliance are expected to be conducted. The composition, frequency and rigueur of that inspection/audit rests in the hands of the LSO. A common practice for institutions is to develop laser audit checklists or survey forms. In many institutions, a sole Laser Safety Officer (LSO) or a number of Deputy LSO's perform these audits. For that matter, there are institutions that request users to perform a self-assessment audit. Many items on the common audit list and the associated findings are subjective because they are based on the experience and interest of the LSO or auditor in particular items on the checklist. Beam block usage is an example; to one set of eyes a particular arrangement might be completely adequate, while to another the installation may be inadequate. In order to provide more consistency, the National Ignition Facility Directorate at Lawrence Livermore National Laboratory (NIF-LLNL) has established criteria for a number of items found on the typical laser safety audit form. These criteria are distributed to laser users, and they serve two broad purposes: first, it gives the user an expectation of what will be reviewed by an auditor, and second, it is an

Guidelines for evaluation of anchorage adequacy for safety-related equipment typically used on WWER-type NPPs

International Nuclear Information System (INIS)

Masopust, R.

1999-01-01

This report describes the criteria which should be met when the capacity evaluation of anchorage of safety related equipment is performed for the WWER type NPPs. It should be noted that these criteria were developed specifically for anchorage of WWER type equipment and components to the concrete or steel building structures and they cover different types of anchor bolts and other anchorage details which are typical just for the existing, constructed or reconstructed WWER type NPPs. The screening approach for verifying of equipment anchorage presented in this report is based on a combination of inspections, calculations, and engineering judgement

37Ar monitoring techniques and on-site inspection system

International Nuclear Information System (INIS)

Duan Rongliang; Chen Yinliang; Li Wei; Wang Hongxia; Hao Fanhua

2001-01-01

37 Ar is separated, purified and extracted from air sample with a low temperature gas-solid chromatographic purifying method, prepared into a radioactive measurement source and its radioactivity is measured with a proportional counter. Based on the monitoring result, a judgement can be made if an nuclear explosion event has happened recently in a spectabilis area. A series of element techniques that are associated the monitoring of the trace element 37 Ar have been investigated and developed. Those techniques include leaked gas sampling, 37 Ar separation and purification, 37 Ar radioactivity measurement and the on-site inspection of 37 Ar. An advanced 37 Ar monitoring method has been developed, with which 200 liters of air can be treated in 2 hours with sensitivity of 0.01 Bq/L for 37 Ar radioactivity measurement. A practical 37 Ar On-site Inspection system has been developed. This research work may provide technical and equipment support for the verification protection, verification supervision and CTBT verification

Shell Inspection History and Current CMM Inspection Efforts

Energy Technology Data Exchange (ETDEWEB)

Montano, Joshua Daniel [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-01-26

The following report provides a review of past and current CMM Shell Inspection efforts. Calibration of the Sheffield rotary contour gauge has expired and the primary inspector, Matthew Naranjo, has retired. Efforts within the Inspection team are transitioning from maintaining and training new inspectors on Sheffield to off-the-shelf CMM technology. Although inspection of a shell has many requirements, the scope of the data presented in this report focuses on the inner contour, outer contour, radial wall thickness and mass comparisons.

Application of risk based inspection methodology of API 581 BRD to oil pipelines

Energy Technology Data Exchange (ETDEWEB)

Pezzi Filho, M. [Petrobras, Rio de Janeiro (Brazil); Freire, J.L.F.; Maragone, F.. [Pontifica Univ. Catolica, Rio de Janeiro (Brazil)

2004-07-01

In response to public concerns regarding the safe operation of pipelines, operators are relying on risk management to balance the demands of pipeline integrity and service competitiveness. This paper presented a procedure for calculating the probability of failure according to the API 581 BRD RB I methodology that uses data collected from 3 existing oil pipelines subject to internal corrosion. The risk exposure that the pipeline may be subjected to during its remaining operating life was evaluated. Risk is a function of the probability of failure and the consequences of that failure. Therefore, if the consequences of the failure are assumed to remain unchanged for a given equipment under specific operational conditions, then risk reduction will only be achieved by decreasing the probability of failure and through management of the inspection process. It was shown that if the confidence on the damage rate and on the inspection effectiveness is known, then it is possible to design an alternative to an existing inspection plan. This calls for pig inspections at 5 year intervals to ensure that the probability of failures for pipelines will be under a certain level of tolerable risk. 9 refs., 4 tabs., 3 figs.

Randomization of inspections

International Nuclear Information System (INIS)

Markin, J.T.

1989-01-01

As the numbers and complexity of nuclear facilities increase, limitations on resources for international safeguards may restrict attainment of safeguards goals. One option for improving the efficiency of limited resources is to expand the current inspection regime to include random allocation of the amount and frequency of inspection effort to material strata or to facilities. This paper identifies the changes in safeguards policy, administrative procedures, and operational procedures that would be necessary to accommodate randomized inspections and identifies those situations where randomization can improve inspection efficiency and those situations where the current nonrandom inspections should be maintained. 9 refs., 1 tab

In-Service Inspection system for coolant channels of Indian PHWRS - evolution and experience

International Nuclear Information System (INIS)

Puri, R.K.; Singh, M.

2006-01-01

In-Service Inspection (ISI) is the most important of all periodic monitoring and surveillance activities for assuring the structural integrity of coolant channels in the life extension and management of pressurized heavy water reactors (PHWR-CANDU). Indian PHWRs (220 MWe) are characterized by consists by 306 coolant channels in each unit. These channels have to be inspected for various parameters over the operating life of the reactor. ISI of coolant channels necessitated the indigenous development of an inspection system called BARCIS (BARC Channel Inspection System) at Bhabha Atomic Research Center. BARCIS consists of mainly three parts; drive and control unit, special sealing plug and an inspection head carrying various NDT sensors. Five such systems have been built and deployed at various power plants. The paper deals with the development of the BARCIS system for meeting the ISI requirements of coolant channels, development cycle of this system from its conception to evolution to the present state, challenges, data generated and experience gained (ISI of nearly 900 coolant channels has been completed). Prior to BARCIS, pressure tube gauging equipment for pre-service inspection of coolant tubes was developed in 1980. Moreover a tool for ISI of coolant channels in dry condition was developed in 1990. The paper also describes evolution of various contingency procedures and devices developed over the last one decade. Future plans taking into account technological advancement, changes in the scope of inspection due to design and operating experiences and plant layout will also be covered. The paper describes the efforts put in to develop drive and control mechanism to suit the different vault layouts. The drive mechanism is responsible for linear and rotary movement of the inspection head to carry out 100% volumetric inspection. Special emphasis has been laid on the safety devices required during the inspection activity. Special measures for heavy water retention in

In-service inspection of the vessels of nuclear submarine reactors

International Nuclear Information System (INIS)

Saglio, R.; Mercier L'Abbe, G.

1977-02-01

Description is given of a machine of automatic inspection of the reactor vessels of nuclear submarines, that was developed by the French Atomic Energy Commission (CEA). A focused ultrasound testing method is used. The equipment such described meets the safety requirements prescribed for the primary circuits of nuclear submarine boiler plants. The sensitivity and resolution power of the apparatus allow such high precision to be obtained as rupture mechanics gains a credibility that could not have been obtained with using conventional apparatus [fr

Inspection of internal tank welds using the ACFM inspection method

International Nuclear Information System (INIS)

Topp, D.A.; Lugg, M.C.

2009-01-01

The paper describes recent developments of the ACFM technique and describes several case studies where ACFM has been used to inspect the internal plate welds on large steel storage tanks in refineries. For weld inspection, conventional methods such as magnetic particle inspection or vacuum box testing are generally used. This paper presents comparisons of the results from ACFM with those from the conventional methods, from which conclusions are drawn as to the benefits this technique offers in terms of cost, time savings and inspection reliability. (author)

Approach to the assessment of the performance of nondestructive test methods in the manufacture of nuclear power station equipment

International Nuclear Information System (INIS)

Michaut, J.P.

1996-01-01

The safety of a nuclear power station lies largely in the possibility of ensuring, at the time of in service inspections on major equipment, that the extent of faults which may appear or develop is not greater than that of faults detrimental to behavior in service. This assurance is based on performance demonstration of the nondestructive test methods used for inspecting the equipment in service. This is the subject of numerous studies in various countries. To ensure that manufacturing faults likely to downgrade the safety of the equipment are not discovered in service, it seems desirable to make sure that the performance of the nondestructive test (NDT) methods which are going to be used in manufacture will be at least as high as those used in service and that they are therefore capable of guaranteeing detection of faults clearly less important than really harmful faults. The performance of NDT methods and their consistency with those which can be used in service is evaluated before the start of manufacture on a mock-up representative of the equipment itself. Information is given on research in progress on the bimetal welding of a pressurizer spray nozzle

Inspection maintenance and planning of shutdown in thermal electric generating plants

International Nuclear Information System (INIS)

Dezordi, W.L.; Correa, D.A.; Kina, M.

1984-01-01

The schedule shutdown of an industrial plant and, more specifically, of an electrical generating station, is becoming increasingly important. The major parameters to be taken into account for the planning of such a shutdown are basically of economic-financial nature such as costs of the related services (materials, equipment, manpower, etc), loss of revenue caused by the station's shutdown as well as by the station availability, and other requirements expected from it by the Load Dispatch and consumers. Improving the equipment's performances and the station's availability are the fundamental objectives to be strived for. The authors present in this paper, in an abridged form, the planning tools used for thermal electric generating plants shutdowns for inspections, maintenance and design changes implementation. (Author) [pt

Underwater inspection, repair and reconstitution of water reactor fuel

International Nuclear Information System (INIS)

1988-06-01

On-site fuel examination plays an important role for evaluation of fuel irradiation performance under reactor operating conditions. Also fuel assembly repairs are economically very attractive for operating nuclear utilities. The status of the processes of examination and repair, equipment used and research plans in Member States are reviewed in these Proceedings. All presentations were divided into three sessions: inspection diagnostic: facilities, techniques, and programmes (8 papers); repair and reconstitution techniques (6 papers); power plant experience (6 papers). A separate abstract was prepared for each of these 20 papers. Refs, figs and tabs

PWR fuel inspection and repair technology development in the Republic of Korea

International Nuclear Information System (INIS)

Park, J.Y.

1998-01-01

As of September 1997, 10 PWRs and 2 PHWRs generate 10,320MW electricity in Korea. And another 8 PWRs and 2 PHWRs will be constructed by 2006. These will need about 400 MTU of PWR fuels and 400 MTU of PHWR fuels. To improve average burnup, thermal power, fuel usability and plant safety, better poolside fuel service technologies are strongly recommended as well as the fuel design and fabrication technology improvements. During the last twenty years of nuclear power plant operation in Korea, more than 4,000 fuel assemblies has been used. At the site, continuous coolant activity measurement, pool-side visual inspection and ultrasonic tests have been performed. Some of the fuels are damaged or failed for various reasons. Some of the defected fuels were examined in hot cell to investigate the cause of failure. Even though 30 PWR fuel assemblies were repaired by foreign engineers, fuel inspection and repair technologies are not established yet. Various kind of design for the fuel make the inspection, repair and reconstitution equipment more complex. As a result, recently, a plant to obtain overall technology for poolside fuel inspection, failed fuel repair and reconstitution through R and D activities are set forth. (author)

RPII Inspection and Licensing Activities and Annual Inspection Programme for 2012

International Nuclear Information System (INIS)

2012-04-01

The purpose of this document is to promote transparency in the activities of the RPII. It explains aspects of the internal workings of the Regulation and Information Management Division of the Institute to aid understanding of the processes and decisions of that Division which may impact on licensees and other interested parties. The objective of the report is to provide an overview of inspection activities of the RPII, to examine the evolution in licensee numbers and to outline the rationale in developing annual inspection programmes. All inspection activities are now carried out within the framework of a quality management system including; inspection planning, the training of inspectors, the conduct of inspections, as well as post inspection follow up and review. This report also provides an overview of the main features of the quality system

Regulatory inspection practices for industrial safety (electrical, mechanical, material handling and conventional aspects)

International Nuclear Information System (INIS)

Agarwal, K.

2017-01-01

Regulatory Inspection (RI) of BARC facilities and projects are carried out under the guidance of BARC Safety Council (BSC) Secretariat. Basically facilities and projects have been divided into two board categories viz. radiological facilities and non-radiological facilities. The Rls of radiological facilities should be carried out under OPSRC and of non-radiological facilities under CFSRC. Periodicity of inspection shall be at least once in a year. The RI of projects is carried out under concerned DSRC. RI practices with industrial safety which includes electrical, mechanical, material handling and conventional aspect for these facilities starts with check lists. The inspection areas are prepared in the form of checklists which includes availability of approved documents, compliance status of previous RIT and various safety committee's recommendations, radiological status of facilities, prompt reporting of safety related unusual occurrences, major incident, site visit for verification of actual status of system/plant. The practices for inspection in the area of electrical safety shall include checking of maintenance procedure for all critical class IV system equipment's such as HT panel, LT panel, transformer and motors. Load testing of Class III system such as D.G. set etc. shall be carried out as technical specification surveillance schedule. Status of aviation lights, number of qualified staff, availability of qualified staff etc. shall be form of inspection

Coke drums inspection and evaluation using stress and strain analysis techniques

Energy Technology Data Exchange (ETDEWEB)

Haraguchi, Marcio Issamu [Tricom Tecnologia e Servicos de Manutencao Industrial Ltda., Piquete, SP (Brazil); Samman, Mahmod [Houston Engineering Solutions, Houston, TX (United States); Tinoco, Ediberto Bastos; Marangone, Fabio de Castro; Silva, Hezio Rosa da; Barcelos, Gustavo de Carvalho [Petroleo Brasileiro S.A. (PETROBRAS), Rio de Janeiro, RJ (Brazil)

2012-07-01

Coke drums deform due to a complex combination of mechanical and thermal cyclic stresses. Bulges have progressive behavior and represent the main maintenance problem related to these drums. Bulge failure typically result in through-wall cracks, leaks, and sometimes fires. Such failures generally do not represent a great risk to personnel. Repairs needed to maintain reliability of these vessels might require extensive interruption to operation which in turn considerably impacts the profitability of the unit. Therefore the condition, progression and severity of these bulges should be closely monitored. Coke drums can be inspected during turnaround with 3D Laser Scanning and Remote Visual Inspection (RVI) tools, resulting in a detailed dimensional and visual evaluation of the internal surface. A typical project has some goals: inspect the equipment to generate maintenance or inspection recommendations, comparison with previous results and baseline data. Until recently, coke drum structural analysis has been traditionally performed analyzing Stress Concentration Factors (SCF) thought Finite Element Analysis methods; however this technique has some serious technical and practical limitations. To avoid these shortcomings, the new strain analysis technique PSI (Plastic Strain Index) was developed. This method which is based on API 579/ ASME FFS standard failure limit represents the state of the art of coke drum bulging severity assessment has an excellent correlation with failure history. (author)

In-vessel inspection before head removal: TMI II, Phase III (tooling and systems design and verification)

International Nuclear Information System (INIS)

Carter, G.S.; Ryan, R.F.; Pieleck, A.W.; Bibb, H.Q.

1982-09-01

Under EG and G contract K-9003 to General Public Utilities Corporation, a Task Order was assigned to Babcock and Wilcox to develop and provide equipment to facilitate early assessment of core damage in the Three Mile Island Unit 2 reactor vessel head. Described is the work performed, the equipment developed, and the tests conducted with this equipment on various mockups used to simulate the constraints inside and outside the reactor vessel that affect the performance of the inspection. The tooling developed provides several methods of removing a few control rod drive leadscrews from the reactor, thereby providing paths into which cameras and lights may be inserted to permit video viewing of many potentially damaged areas in the reactor vessel. The tools, equipment, and cameras demonstrated that these tasks could be accomplished

Remotely controlled inspection and handling systems for decommissioning tasks in nuclear facilities

International Nuclear Information System (INIS)

Schreck, G.; Bach, W.; Haferkamp, H.

1993-01-01

The Institut fur Werkstoffkunde at the University of Hanover has recently developed three remotely controlled systems for different underwater inspection and dismantling tasks. ODIN I is a tool guiding device, particularly being designed for the dismantling of the steam dryer housing of the KRB A power plant at Gundremmingen, Germany. After being approved by the licencing organization TUEV Bayern, hot operation started in November 1992. The seven axes remotely controlled handling system ZEUS, consisting of a three translatory axes guiding machine and a tool handling device with four rotatory axes, has been developed for the demonstration of underwater plasma arc cutting of spherical metallic components with great wall thicknesses. A specially designed twin sensor system and a modular torch, exchanged by means of a remote controlled tool changing device, will be used for different complex cutting tasks. FAUST, an autonomous, freediving underwater vehicle, was designed for complex inspection, maintenance and dismantling tasks. It is equipped with two video cameras, an ultrasonic and a radiologic sensor and a small plasma torch. A gripper and a subsidiary vehicle for inspection may be attached. (author)

Technology Assessment of the Inspection Readiness Plan in Chemical Weapons Convention Challenge Inspections

National Research Council Canada - National Science Library

Woodley, Anthony

1998-01-01

...) Challenge Inspections. The CWC is an intrusive inspection. The Challenge Inspection allows for a team of international inspectors to inspect on very short notice a naval facility suspected of violating the CWC...

Process Improvement to the Inspection Readiness Plan in Chemical Weapons Convention Challenge Inspections

National Research Council Canada - National Science Library

Triplett, William

1997-01-01

...) Challenge Inspection. The CWC is an intensive inspection. The Challenge Inspection allows for a team of international inspectors to inspect a naval facility suspected of violating the CWC on very short notice...

General inspection strategy for fault diagnosis-minimizing the inspection costs

International Nuclear Information System (INIS)

Reinertsen, Rune; Wang Xiaozhong

1995-01-01

In this paper, a general inspection strategy for system fault diagnosis is presented. The procedure presented in this paper, is an improvement of methods described in papers by , and . This general strategy provides the optimal inspection procedure when the inspections require unequal effort and the minimum cut set probabilities are unequal. This feature makes the procedure described in this paper more useful for practical applications than the most recent procedure presented in the paper by Najmus-Saqib and Ishaque, which requires the minimum cut set probabilities to be equal. The inspection strategy described in this paper is based on first inspecting the basic event that will provide the maximum information gain per unit cost invested. The information gain is measured by the decrease of Shannon entropy. A detailed tutorial example is presented

Cargo container inspection test program at ARPA's Nonintrusive Inspection Technology Testbed

Science.gov (United States)

Volberding, Roy W.; Khan, Siraj M.

1994-10-01

An x-ray-based cargo inspection system test program is being conducted at the Advanced Research Project Agency (ARPA)-sponsored Nonintrusive Inspection Technology Testbed (NITT) located in the Port of Tacoma, Washington. The test program seeks to determine the performance that can be expected from a dual, high-energy x-ray cargo inspection system when inspecting ISO cargo containers. This paper describes an intensive, three-month, system test involving two independent test groups, one representing the criminal smuggling element and the other representing the law enforcement community. The first group, the `Red Team', prepares ISO containers for inspection at an off-site facility. An algorithm randomly selects and indicates the positions and preparation of cargoes within a container. The prepared container is dispatched to the NITT for inspection by the `Blue Team'. After in-gate processing, it is queued for examination. The Blue Team inspects the container and decides whether or not to pass the container. The shipment undergoes out-gate processing and returns to the Red Team. The results of the inspection are recorded for subsequent analysis. The test process, including its governing protocol, the cargoes, container preparation, the examination and results available at the time of submission are presented.

Robot technology in remote inspection and repair

International Nuclear Information System (INIS)

Lowe, D.B.

1981-01-01

The development of remotely controlled equipment for use in a hostile (eg radioactive) environment is reviewed. Inspection and repair work in the core vessel of a nuclear reactor is a particular example of the need for robot devices. Devices with the ability to reach out after entering the interior of the reactor and perform specified operations some distance from the entry axis are needed. It is also necessary to design with tool retrieval emergencies in mind. Should an accident or malfunction prevent withdrawal of the equipment by normal means there must be a fail-safe mechanism of collapse and withdrawal. Visual contact with the device, usually by closed circuit TV is also necessary. Recent developments are described. These include stereoscopic imaging, a flexible arm of increased reach, dexterity and strength, and a computerized robotic arm with seven degrees of freedom to be deployed by the flexible arm. Microprocessors are used to analyse information and command functions. A current solution of the need for precise positioning and tracking of a NDT head round a reactor core is illustrated. (U.K.)

Inspection Database

Data.gov (United States)

U.S. Department of Health & Human Services — FDA is disclosing the final inspection classification for inspections related to currently marketed FDA-regulated products. The disclosure of this information is not...

Annual report of the group for maintenance of electronic equipment

International Nuclear Information System (INIS)

Popovic, B.

1965-01-01

Maintenance and repair of the RA reactor control and safety systems were uniformly distributed during the whole year and were done according to the annual plan. A series of repairs of he electronic equipment as well as exchange of electronic components and elec tonic tubes. The testing and calibration of control and protection circuits were done regularly according to the needs and operation state of the reactor and according to the instructions. Inspections, repairs and reconstructions well as operating characteristics of individual elements as well as complete electronic circuits during 1965 have shown da the systems of control and safety are still in good condition. Somewhat higher number of failures due to aging of electronic tubes is a regular consequence of equipment and instrumentation aging [sr

75 FR 6865 - Airworthiness Directives; The Boeing Company Model 737-700 (IGW) Series Airplanes Equipped With...

Science.gov (United States)

2010-02-12

... replacing aging float level switch conduit assemblies, periodically inspecting the external dry bay system... Model 737-700 (IGW) Series Airplanes Equipped With Auxiliary Fuel Tanks Installed in Accordance With... airworthiness directive (AD) for certain Model 737-700 (IGW) series airplanes. This proposed AD would require...

Safety procedures in operation of inspection and maintenance of pressure reduction and metering stations

International Nuclear Information System (INIS)

Villas Boas, Ademar Jose; Biesemeyer, Marco Aurelio R.

2000-01-01

Each local Natural Gas Distribution Company in Brazil has its own working procedures for operations of inspection and maintenance on equipment and accessories connected to the gas network. Some of these Companies developed a better elaborated and documented way of working routines, while others only work based on their operators experience. The objective of this work is to create a standard procedure for operations of inspection and maintenance of Pressure Reducing Stations and Metering Stations, mainly the ones concerned to safety aspects. This work has no intention of exhausting all aspects related to this subject but to become the first step to standardize these types of operations among Natural Gas Distribution Companies. (author)

Controlling the quality of replacement parts in nuclear station, class 1E equipment

International Nuclear Information System (INIS)

Pierson, R.K.; Clemons, R.W.

1984-01-01

Nuclear station owners have traditionally purchased replacement parts for Class 1E equipment from the original supplier of the equipment. By this method, part and equipment quality could be maintained. In recent years, however, this traditional source of parts has continuously declined as an increasing number of original equipment suppliers stop producing Class 1E equipment or no longer stock parts for older equipment. When replacement parts for Class 1E equipment are not obtainable from the original suppliers, equipment owners have created a variety of methods for assuring the quality of parts obtained from other sources. A standard that provides direction and guidance for maintaining the quality of Class 1E equipment when repaired with parts from alternate sources is, therefore, needed to assure the methods in use are satisfactory and to alert the equipment owners to additional acceptable methods. The standard has now been proposed. IEEE Standard P934 (June, 1983 Draft): ''Requirements for Replacement Parts for Class 1E Equipment in Nuclear Power Generating Stations'' (Ref-3) consist of an introductory section followed by sections on part selection, procurement, replacement (including inspections and tests), non-conforming conditions and records. The proposed standard also includes a non-mandatory appendix on acceptable procurement methods and a summary intended to assist the user in selecting a proper procurement method

Optical fiber inspection system

Science.gov (United States)

Moore, Francis W.

1987-01-01

A remote optical inspection system including an inspection head. The inspection head has a passageway through which pellets or other objects are passed. A window is provided along the passageway through which light is beamed against the objects being inspected. A plurality of lens assemblies are arranged about the window so that reflected light can be gathered and transferred to a plurality of coherent optical fiber light guides. The light guides transfer the light images to a television or other image transducer which converts the optical images into a representative electronic signal. The electronic signal can then be displayed on a signal viewer such as a television monitor for inspection by a person. A staging means can be used to support the objects for viewing through the window. Routing means can be used to direct inspected objects into appropriate exit passages for accepted or rejected objects. The inspected objects are advantageously fed in a singular manner to the staging means and routing means. The inspection system is advantageously used in an enclosure when toxic or hazardous materials are being inspected.

Capacity of the equipment family SICOM to inspect fuel elements; Capacidad de los equipos familia SICOM para inspeccionar elementos de combustible

Energy Technology Data Exchange (ETDEWEB)

Sanchez Siguero, A.; Sola, A.

2013-07-01

To check the status where the fuel assemblies are after has been operating in the core of nuclear plants, inspections have been conducted to carry out an improvement in the behavior of alloys used in pods of fuel, the control of corrosion of these pods because of heat, reducing the transfer of heat due to the oxide and with the support of visual inspections monitor the physical integrity of the fuel elements.

Scarab III Remote Vehicle Deployment for Waste Retrieval and Tank Inspection

International Nuclear Information System (INIS)

Burks, B.L.; Falter, D.D.; Noakes, M.; Vesco, D.

1999-01-01

The Robotics Technology Development Program now known as the Robotics Crosscut Program, funded the development and deployment of a small remotely operated vehicle for inspection and cleanout of small horizontal waste storage tanks that have limited access. Besides the advantage of access through tank risers as small as 18-in. diameter, the small robotic system is also significantly less expensive to procure and to operate than larger remotely operated vehicle (ROV) systems. The vehicle specified to support this activity was the ROV Technologies, Inc., Scarab. The Scarab is a tracked vehicle with an independently actuated front and rear ''toe'' degree-of-freedom which allows the stand-off and angle of the vehicle platform with respect to the floor to be changed. The Scarab is a flexible remote tool that can be used for a variety of tasks with its primary uses targeted for inspection and small scale waste retrieval. The vehicle and any necessary process equipment are mounted in a deployment and containment enclosure to simplify deployment and movement of the system from tank to tank. This paper outlines the technical issues related to the Scarab vehicle and its deployment for use in tank inspection and waste retrieval operation

Regulatory inspection of the egyptian gamma irradiator using a proposed inspection checklist

International Nuclear Information System (INIS)

Abdel-Ghani, A.H.

2000-01-01

Regulatory inspections are one of the most important elements of a regulatory programme. It shall be performed in all areas of the regulatory responsibility and during all phases of siting, design, construction, commissioning, operation, maintenance and decommissioning of an irradiator facility. The egyptian mega gamma irradiator operating since december 1979 has a Co-60 source of about 400 kilo curies and is used mainly for sterilization of medical supplies and pharmaceuticals and for preservation of some food stuffs. The constructor (Nordion international Inc.) recommended an extensive inspection programme. In accordance with the international and national (2.3) regulations as well as the licensing conditions, the competent authority (NCNSRC) shall perform regulatory inspections both announced and unannounced. In order to facilitate the inspection task and to harmonize the inspection reports a checklist for inspection is proposed which can be used also as an inspection report form

New concepts, requirements and methods concerning the periodic inspection of the CANDU fuel channels

International Nuclear Information System (INIS)

Denis, J.R.

1995-01-01

Periodic inspection of fuel channels is essential for a proper assessment of the structural integrity of these vital components of the reactor. The development of wet channel technologies for non-destructive examination (NDE) of pressure tubes and the high technical performance and reliability of the CIGAR equipment have led, in less than 1 0 years, to the accumulation of a very significant volume of data concerning the flaw mechanisms and structural behaviour of the CANDU fuel channels. On this basis, a new form of the CAN/CSA-N285.4 Standard for Periodic Inspection of CANDU Nuclear Power Plant components was elaborated, introducing new concepts and requirements, in accord with the powerful NDE methods now available. This paper presents these concepts and requirements, and discusses the NDE methods, presently used or under development, to satisfy these requirements. Specific features regarding the fuel channel inspections of Cernavoda NGS Unit 1 are also discussed. (author)